ML20082H994
| ML20082H994 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/30/1991 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20082H991 | List: |
| References | |
| NUDOCS 9108270070 | |
| Download: ML20082H994 (71) | |
Text
_ . _ _____
CLINTON POWER STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1,1991 - JUNE 30,1991 a
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January 1, 1991 - June 30, 1991 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE CLINTON POWER STATION Prepared by Radiological Environmental Group Radiation Protection Department August 29, 1991
.. . . _ _ _ . . . . _ _ . . _ . - _ _ _ _ . . . _ _ _ _ _ . . . _ . . _ _ _ _ _ _ . _ . _ . . _ _ . .__.m._ __ _
TABLE OF C9NTENTS SECTION PAGE
- 1. Executive Summary . . . . . . . . . . . . . . . . b
- 2. Introduction. . . . . . . . . . . . . . . . . . . 6
- 3. Supplemental Information.-. . . . . . . . . . . . 15
- 4. Effluent and Waste Disposal Data. . . . . . . . . 22
- 5. Meteorological Data and Dispersion Estimates. . . 37
- 6. Dose Measurements and Assessments . . .. . . . . 50
- 7. Changes to the Offsite Dose Calculation Manual. . 61
- 8. ODCM Operational Requirement Reports. . . . . . . 63
- 9. Major Changes to Radioactive Waste Treatment .
Systems . . . . . . . . . . . . . .. . . . . . . 67
- 10. New Locations for Doso Calculation and/or Environmental Monitoring. . . . . . . . . . . . . 68 1
i 4
I.
LIST OF TAQLER EAGE Table 1: Airborne Effluents - Summation of All ,
22 Releases . . . . . . . . . . .. . . . . . .
Table 2: Airborne Effluents . . . . . . . . . . . . . 23 Table 3: Radioactive Gaseous Waste LLD Values . . . . 25 Table 4: Waterborne Effluents - Summation of All Releases . . . . . . . . . . . . . . . .. . 27 Table 5: Waterborne Effluents . . . . . . . . . . . . 28 l Table 6: Radioactive Liquid Waste LLD Values. . . . . 29 Table 7: Solid Waste and Irradiated Puel Shipments. . 32 l Table 8: Corrections to Data Reported in Previous l Semiannual Reports . . . . . . . . . . . . . 34 l
Table 9: Effluent Data Not Available for Previous Semiannual Report. . . . . . . . . . . . . . 36
! Table 10: Meteorological Data Availability . . . . . . 38 Table 11: Classification of Atmospheric Stability. . . 42 Table 12: Joint Wind Frequency Distribution by Stability Class. . . . . . . . . . . . . . . 43 Table 13: Maximum Offsite Doses and Dose Commitments to Members of the Public . . . . 50 Table 14: Calculated Doses to Members of the Public L During Use of the Road in the Southeast i
Sector within the C."S Site Boundary. . . . . 54 Table 15: Calcul sted Doses to Members - of the Public During Use of the Agricultural Acreage in the South-Southwest Sector within the CPS Site Boundary. . . . . . . . . . . . . . . . . 55 Table 16: Calculated Doses to Members of the Public During Use of Clinton Lake in the Northwest Sector within the CPS Site Boundary. . . . . 56 l
- _ , . _ . - . . . . - . _ _ _ - . ~ . _ . . _ . _ . _ _ . - . _ _ _ _ . _ . _ _ _ _ _ . _ . . . _ _ _ _ . _ .m.
TABLE Table 17: Calculated Doses to Members of the Public During Use of the Department of Conservation Recreation Area in the East-Southeast Sector within the CPS Site Boundary . . . . . . . . . . . . . . . . . . 57 Table 18: Calculated Doses to Members of the Public Southwest Sector within the CPS Site Boundary . . . . . . . . . . . . . . . . . . 58 Table 19: Calculated Doses to Members of the Public West-Southwest Sector within the CPS Site Boundary . . . . . . . . . . . . . . . . . . 59 Table 20: Calculated Doses to Members of the Public South-Southeast Sector-within the CPS Site 2 Boundary . . . . . . . . . . . . . . . . . . 60 3
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LIST OF FIGURES TABLE Figure 1: CPS Airborne Effluent Release Points . . . . 7
-Figure 2: CPS Waterborne Effluento Release. Pathway . . 8 Figure 3: Effluent Exposure Pathways . . . . . . . . . 13 Figure 4: . CPS 1991 Monthly Liquid Radwaste Discharge Total. . . . . . . . . . . . . . . 21 Figure 5: CPS Wind Rose: 10-meter . . . . . . . . . . 39 L Figure 6: CPS Wind Rose: '60-meter . . . . . . . . . . . 40 l-l Figure 7: Clinton Power Station Distribution of Atmospheric Stability Class. . . . . . . . . 41 l Figure 8:-Areas Within the CPS Site Boundary Open to Members of the Public . . . . . . . . . . 53 4
.L ,
SECTION 1 EXECUTIVE
SUMMARY
. _ _ _ _ _ _..._.._._____.-__.____.__.m._._..._. _ _ _ . _ -
t EXE_Q1TTIVE
SUMMARY
The Semiannual Radioactive Effluent Release Report is a detailcd description of all radioactive releases (both gaseous and liquid) from the Clinton Power Station (CPS)_and the resulting radiation doses for the period from January 1 through June 30, 1991. This report includos a detailed meteorol'gical section which provides the weather history of the area during this period. This
'information is used to calculate the dose to the public.
The report also includes a summary of the amounts of radioactive material contained in solid waste that is packaged and shipped for offsite disposal at federally-approved burial facilities. In addition, this report notifies the U.S. Nuclear Regulatory Commission (NRC) staff of changes to CPS's Offsite Dose Calculation Manual (ODCM) and exceptions to the CPS effluent i monitoring program which must be reported per ODCM Opcration Requirements 2.7.1.b and 3.9.2.a.
The NRC requires that nuclear power stations be designed, constructed, and operated in such'a way that the amount of radioactive material in effluent releases to unrestricted areas is kept As Low As Beasonably Achievable (ALARA). To assure these criteria are met, the NRC has established limits governing the release of radioactivity in effluents.
CPS was operated in compliance with established limits during this report period. The maximum radiation dose delivered to the inhabitants of the area surrounding CPS, due to radioactivity released from the station, was very small. The radiation dose to people in the vicinity of CPS was calculated for a continuous gaseous release by using the concentration of radioactive material and the weather conditions at the time of the release.
Radiation dose to the public was also calculated for liquid batch releases using the concentration of radioactive material and the nonradioactive dilution flow at the time of the release. These doses were only a small fraction of the limit for the most exposed member of the public.
5
SECTION 2 INTRODUCTION l
l
INTRODUCTION Clinton Power Station is located in Harp Township, DeWitt County approximately six miles east of the city of Clinton in east-central Illinois. Clinton Power Station is a 985 megawatt gross '
, electrical power output boiling water reactor. The reactor and generating units were supplied by General Electric, Sargent and Lundy Fngineers served as architect-engineer, and Baldwin Associoces was the constructor.
Construction of CPS began in the mid 1970's. Fuel load began in September of 1986 with initial criticality achieved on February 27, 1987. Commercial operation commenced in April 1987 and the reactor reached 100% power for the first time on September 15, 1987. :
Airborne effluents are released from CPS via two gaseous effluent release points to the environment: the Common Station Heating, ,
Ventilating, and Air Conditionina (HVAC) Stack and the Standby Gas Treatment System (SGTS) Vent (see Figure 1). Each release ;
point is continuously monitored and a program of periodic :
sampling and analysis is conducted as specified in the ODCM.
Liquid effluents from CPS are released in batch mode and are 4 sampled and analyzed prior to release. Liquid effluents, variable from 10-60 gallons per minute (GPM) or 50-300 GPM, combine with Plant Service Water flow (minimum of approximately 5000_GPM) and Plant Circulating Water ficw (0-567,000 GPM) in the Sealwell prior to entering the 3.4 mile discharge flume to Lake l
Clinton (see Figure 2).
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CPS AIRBORNE EFFLUENT RELEASE POINTS Figure 1 TURENE BULDN3 RADWASTE AND !
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l GASEOUS EFFLUENT RELEASE POINT CHARACTERISTICS 1
HVAC EXHAUST STACK SGTS EXHAUST S7ACK RELEASE POlHT HEIGHT (m) 61 61 BUli. DING HEIGHT (m) 58 58 HELEASE PCINT GEOMETRY DUCT P!PE RELEASE POINT AREA (m8 ) 11.15 0.15 RELEASE POINT DIAMETER (m) 3.77' O.44 ANNUAL AVERAGE FLOW RATE (fr 8/ min) 237.000 4000 VERTICAL EXJT VELOCITY (m/sec) 10.02 12.49 7
l
CPS WATERBORNE EFFLUENTS RELEASE PATHWAY Figure 2 PLANT SERVICE WATER
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LIQUID RADWASTE DISCHARGE LINE (10-60 OR 50-300 GPM) h . RADIATION MONITOR ALARM /TEP SETPO(NT C4LCULATED BASED ON EAGi DATCH ISOTOPIC #ULYS;S N'O DILUTION FLOW
>4 ISOLATION VALVE TERM 1?uTES RELEASE ON HlGH RADIATION, H:GH RELEASE FLOW RATE OR LOW C COMPOSITE SAMPLER DMON ROW RAW COLLECTS APPROX!MATELY 20 mi EVERY CD M:N'JIIS FROM THE DISCHARGE FLUME FOR MONTHLY ANALYS:S SEALWELL LAKE P LANT CIRCULATING .__ CLINTON WATER (0-567,000 GPM) DISCH.^RGE FLUME 3,4 MILES 8
1 i'
l Reaulatorv Limits i
The NRC requires nuclear power plants to be designed, constructed 1 and operated in such a way that the radioactivity in effluent releases to unrestricted areas is kept ALARA. To assure these criteria are met, each license authorizing nuclear reactor operation includes Radiological Effluent Technical Specifications' (RETS) governing the release of radioactive c'fluents (Code of Federal Regulations, Title 10, Part 50, Appendix I). The RETS designate the limits for release of effluents, as well as the limits for doses to the general public from the release of radioactive liquids and gases. Keeping releases within these i
operating limits demonstrates that the ALARA principle is being met. ,
L The dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas is limited to:
- Less than or equal to 3 mrom per year to the total body.
'i
-and-
- Less than or equal to 10 mrem per year to any organ.
The dose to air due to release of noble gases in gaseous effluents is limited to:
- Less than or equal to 10 mrad per year for gamma radiation.
-and-Less than or equal to 20 mrad per year for beta radiation.
The dose to a member of the general public from iodine-131, tritium-and all particulate radionuclides with a half-life greater than eight days in gaseous effluents is limited to:
Less than or equal to 15 mrom per year to any organ.
These ALARA limits are a fraction of the dose limits established by the Environmental Protection Agency (EPA). In its Environmental Dose Standard of 40CFR190, the EPA established dose limits for members of the public in the vicinity of a nuclear power plant. These dose limits are:
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Less than or equal to 25 mrem per year to the total body.
Less than or equal to 75 mrom per year to the thyroid.
-and-Less than or equal to 25 mrem per year to any other organ.
See Section 3 for more information on regulatory limits.
Processino and Monitorina Effluents are strictly controlled at CPS to ensure radioactivity released to the environment is minimal and does not exceed release limits. Effluent controls include the operation of radiation monitoring systems in the plant and offsite environmental sampling and-analysis programs. In-plant radiation monitoring systems are used to provide a continuous indication of radioactivity and are also used to collect particulate and radiciodine samples. These samples are analyzed in a laboratory to identify the specific concentration of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition to complement the information provided by real-time monitoring instruments.
Beyond the plant itself, a radiological environmental monitoring program is maintained in accordance with Federal Regulations.
The basic purpose of the program is to assess the radiological impact on the environment due to the operation of the Clinton Power Station. Implicit in this purposa is the regulatory requirement to trend and assess radiation exposure rates and radioactivity concentrations that may contribute to human radiation exposure. The program consists of two phases, preoperational and operational. During the preoperational phase of the program, the baseline for the local radiation environment was established. The operational phase of the program includes the objective of making confirmatory measurements to verify that the in-plant controls for the release of radioactive material are functioning as designed. Assessment of the operational impact of cps on the environment is based on data collected since initial reactor criticality.
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. . - . - - - - - - . . - - - ~ . ~ . - - . - - - - - -
ExDosure Pathways Radiological exposure pathways are the means by which people may become exposed to radioactivity released from nuclear facilities.
The major pathways of concern are those which could cause the highest calculated radiation dose. These pathways are determined from the type and amount of radioactivity released, the environmental transport mechanism and use of the environment.
The environmental transport mechanism includes the meteorological characteristics of the area which will be defined by wind speed and wind direction at the time of the release. This information is used to evaluate how the radionuclides will be distributed in the area. The most important factor in evaluating the exposure pathway is the use of the environment by the people living around CPS. Factors such as location of homes in the area, use of cattle for milk and meat, and the growing of gardens for vegetable consumption are very important considerations in evaluating exposure pathways. Figure 3 illustrates the various effluent exposure pathways considered.
The radioactive gaseous effluent exposure pathways include direct radiation, deposition on plants and soil, and inhalation by animals and humans. The radioactive liquid effluent exposure pathways include drinking water, fish consumption and direct exposure from the lake.
Dose Assessment Whole body radiation involves the exposure of all organs in the human body to ionizing radiation. Most background radiation exposures consist of whole body exposure although specific organs can receive radiation exposure from distinct radionuclides.
These radionuclides enter the body through inhalation and ingestion and seek different organs depending on the nuclide.
For example, radioactive iodine selectively concentrates in Jhe thyroid, radioactive cesium collects in muscle and liver tissue, and radioactive strontium in mineralized bone.
Tne total dose to organs from a given radionuclide also depends on the amount of activity in the organ and the amount of time that the radionuclide remains in the body. Some radionuclides remain for very short periods of time due to their rapid radioactive decay and/or elimination rate from the body, while others may remain longer.
The radiation dose to people in the area surrounding CPS is calculated for each release using the concentrations or radioactive material and the weather conditions present at the time of the release. The dose is calculated in all sixteen geographical sectors surrounding CPS and takes into account the location of the nearest residents, vegetable gardens producing 11
I broad leaf vegetables, dairy and meat animals in all sectors.
The calculated dose also uses the concept of a " maximum exposed individual" and " standard man", and the maximum use factors for the environment, such as how much milk an average person drinks and how much air a person breathes in a year.
See Tables 13-20 of Section 6 for more detailed information on dose to the public.
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RELEASES DILUTED BY ATMOSPHERE g
1 o AIRBORNE ANIMALS RELEASES CLINTON POWER (MILK, MEAT) PLUME EXPOSURE STATION AND INHALATION
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CONSUMED BY PEOPLE M DYLAKE M l BY ANIMALS g m i
.jj CONSUMED DRINKING WATER ff ,
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Gaseous Effluents Gaseous effluent radioactivity released from CPS is classified into two categories, 1) noble gas, and 2)-icdine-131, iodine-133, tritium and.all radionuclides in particulate form with half-lives greater than eight days.- Noble gases, such as xenon and krypton, are biologically and chemically nonreactive; these radionuclides cause external radiation exposure. Iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than eight days are the major contributors to internal dose.
See Tables 1, 2, 3 and 9 of Section 4 for more detailed
-information on gaseous effluents.
Liauid Effluents Radioactivity in liquid effluents consists of radioactive fission and activation products, tritium and entrained noble gases.
See Tables 4, 5, 6 and 9 of Section 4 for more detailed information on liquid effluents.
Solid Wa te Shioments In order to reduce the radiation exposure to personnel and maintain the ALARA concept, the NRC and the Department of Transportation (DOT) have established limits on the types of radioactive waste and the amount of radioactivity that may be packaged and shipped offsite for burial or disposal. To ensure that CPS is complying with these regulations, the types of waste and the radioactivity present are reported to the NRC.
See Table 7 of Section 4 for more detailed information on solid waste shipments.
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SECTION 3 SUPPLEMENTAL INFORMATION
-1
I. REGULATORY LIMITS A. Gaseous Effluents
- 1. In accordance with Title 10 of the Code of Federal Regulations (CFR), Part 20, the maximum permissible concentrations for gaseouc effluents shall not exceed the values given in 10CFR20, Appendix B, Table II, Column 1. To ensure these concentrations are not exceeded, dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
- a. Noble gases - Less than or equal to 500 mrem / year to the total body.
- Less than or equal to 3000 mrom/ year to the skin.
- b. Iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than eight days:
Less than or equal to 1500 mrem / year to any organ.
- 2. In accordance with Title 10 of the Code of Federal Regulations, Part 50, Appendix I, air dose due to noble gtses released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- a. Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any calendar quarter.
- b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.
- 3. In accordance with 10CFR50, Appendix I, dose to a member of the public (from iodine-131, iodine-133, tritium and all radionuclides in particulate form.
with half-lives greater than eight days) in l
l 15 i
l l
gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. Less than or equal to 7.5 mrom to any organ, during any calendar quarter,
- b. Less than or equal to 15 mrem to any organ, during any calendar year.
B. Liquid Effluents
- 1. The concentration of radioactive material released in liquid offluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulations, 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-04 microcuries per milliliter total activity.
- 2. The dose or dose commitment to a member of the public from radioactive materials in IJguid effluents released to unrestricted areas shall be limited to:
- a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.
- b. Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ during any calendar year.
II. MAXIMUM PERMISSIBLE CONCENTRATION A. Gaseous
- 1. -The maximum permissible concentrations (MPC) for gaseous effluents are specified in Title 10 of the Code of Federal Regulations, Part 20, Appendix B, Table II, Column 1. However, the MPCs of 10CFR20 are not utilized directly for limiting gaseous effluents. The CPS ODCM establishes requirements to limit-the release rate of effluents such that discharges of gaseous radioactive material will 16
not' result in dose rates, to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA , higher than those which would occur if average annual concentrations exceeded MPC limits. The maximum permissible dose rates for gaseous releases are:-
- a. ODCM Operation Requirement 3.4.1.a (Dose rate at and beyond the site' boundary from gaseous effluents in the form of noble gases).
Less than or equal to 500 mrem / year to the total body.
Less than or equal to 3000 mrem / year to the skin.
- b. ODCM Operation Requirement 3.4.1.b (Dose rate at and beyond the site boundary from gaseous effluents in the form of iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than eight days).
Less than or equal to 1500 mrem / year to any organ.
E. Liquids
- 1. The maximum permissible concentrations (MPC) for liquids are those listed in 10CFR20, Appendix B, Table II, Column 2, with the most restrictive MPC (whether soluble or insoluble) being used in all cases. For dissolved and entrained noble gases the MPC of 2.0E-04 microcuries per milliliter is applied. This MPC is based on the Xe-135 MPC in air (submersion' dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.
'III. AVERAGE ENERGY The CPS ODCM limits the dose equivalent rates due to the release of fission and activation gases to less than or equal to 500 mrem per year to the total body and less than or equal to-3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents 17
l as described in Regulatory Guide 1.21, " Measuring, i Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", is not applicable.
IV. MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY A. Fission and Activation Gases
_ principal gamma emitters. The HVAC and SGTS release points are continuously monitored, and the average release flow rates for-each release point are used to calculate the total activity released in a given time period.
- 2. Tritium is collected by passing a known volume of the sample stream through a gas washer containing a known quantity of demineralized water. The collected samples are distilled and analyzed by liquid scintillation. The tritium released was calculated for each release point from the measured tritium concentration, the volume of the sample, the tritium collection efficiency, and the stack exhaust flow rates.
B. Iodines Iodine is continuously collected on a charcoal cartridge filter via an isokinetic sampljng assembly on each release point. Filters are normally exchanged once per week and analyzed on an HPGe system. The daily average flow rates for each release point are averaged for the duration of the sampling period and these results, along with isotopic concentrations, are used to determine total activity released during the time period in question.
C. Particulates Particulates are continuously collected on a filter paper via an isokinetic sampling assembly on each release point. Filters are normally exchanged once per week and analyzed on an HPGe system. Flow rates and total activity are determined in the same manner as for iodines.
18
l D. Liquid Effluents Each tank of liquid radwaste is sampled and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative sample is obtained. Samples are analyzed on an HPGe system and release permits are generated based on the values obtained from the isotopic analysis and the most recent values for tritium, gross alpha, iron-SS, strontium-89 and strontium-90. An aliquot based on release volume is saved and added to composite containers. The concentrations of composited isotopes and the volumes of the releases associated with these composites establish the proportional relationships that are then utilized for calculating the total activity released for these isotopes.
V. BATCH F- -2S A. miquid 1st Otr 91 2nd Otr 91
- 1. Number of batch releases: 18 4
- 2. Total time period for batch releases: 1,736 min. 363 min.
- 3. Maximum time period for batch release: 128 min. 95 min.
- 4. Average time period for batch release: 96 min. 91 min.
- 5. Minimum time period for batch release: 87 min. 85 min.
- 6. Average stream flow during periods of release:- 9.95E+04 1.22E+05 liters per minute
- 7. Total waste volume: 1.60E+06 3.65E+05 liters
- 8. Total dilution volume: 1.73E+0B 4.43E+07 liters l
19
D. Gaseous 1st Otr 91 2nd Otr 91
- 1. Number of batch releases. 0 0
- 2. Total time period for batch releases: N/A N/A
- 3. Maximum time period for batch release: N/A N/A
- 4. Average time period for batch release: N/A N/A
- 5. Minimum time period for batch release: N/A N/A VI. DESCRIPTION OF ERROR ESTIMATES ,
A .- Gaseous and Liquid Effluents
. Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:
ET= ((E1 )2 + (E2) + ...(En) 3 where, ET = total percent error E1....En = percent error due to calibration standards, laboratory analysis, instruments, sample flow, etc.
20
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SECTION 4 EFFLUENT AND WASTE DISPOSAL DATA i
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TADLE 1 AIRDORNE EFFLUENTS - DUMMATION OF ALL RELEASED Data Period January 1, 1991 - June 30, 1991 Est Contir.uous Modo Totai l Nuclido Category Unit lot Quarter 2nd Quarter Error, 1 A. Fission & Activation Gases
- 1. Total P.sloaco 2 Ci 0.00E+00 0.00E+00 30
- 2. Averago Release Rato for Porlod uCi/coe 0.00E+00 0.00E+00
- 3. Porcer.4 of Applicable Limit t 0.00E+00 0.00E+30 B. Iodino-131
- 1. Total Release Ci 0.00E+00 0.00E400 31
- 2. Average Roloano Rato for Period pCi/sec 0.00E+00 0.00E+00
- 3. Porcent of Applicablo Limit 1 0.00E+00 0.00E+00 C. Particulates
- 1. Particulatos Released with Half-lives >8 Days C1 3.90E-Oi 3.01E-03* 24
- 2. Avorago Releano Rato for Period gCi/ soc 5.02E-05 3.83E-04*
- 3. Porcent of Applicablo Limit t 4.21E-04 1.22E-04*
- 4. Cross Alpha Activity Rolcased C1 4.02E-07 3.06E-08 D. Tritium
- 1. Total Release Ci 1.73E-02 1.29E400 105
- 2. Averago Releano Rate for Period pCi/coc 2.32E-03 1.64E-01
- 3. Percent of Applicable Limit t 5.87E-07 4.37E-05 1 It should be noted that the lower the actual samplo activity is with respect to background activity, the greator the counting error. Largo errors are reported for the varioun components of CPS gaseous offluents because of consistently low sampic activity.
2 ' Notation: Ar. ntry of 0.00E+00 does not represent the absence of radionuclido but indicatos that the concentratium of the nuclide was below the Lower Limit of Detection (LLD) value listed in Tablo 3.
- Reported values include Sr-89 and Sr-90 values based on first quarter 1991 camplos analysos and seco'd quarter 1991 ventilation exhaust rates.
22
TABLE 2 AIRBORNE EFFLUENTS ' Curies)3 Data Period: January 1, 1991 - June 30, 1991 Continuous Modo Nuclide Third Quarter Tourth Quarter A. Gases Kr-85 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E+00 Xe-133 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 Xo-135m 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 Otherst Ar-41 0.00E+00 0.00E+00 Total 0.00E+00 0.00E+00 B. Iodines I-131 0.00E+00 0.00E+00 I-132 0.00E+00 0.00E+00 I-133 0.00E+00 0.00E+00 I-134 0.00E+00 0.00E+00 I-135 0.00E+00 0.00E400 Total 0.00E+00 0.00E+00 C. Particulates w/ Half-lives
>8 Days Sr-89 0.00E+00 C.00E+00*
.Sr-90 0.00E+00 0.00C+00*
Cs-134 0.00E+00 0.00E+00 CP 137 0.00E+00 0. 00E4 00 Ba-140 0.00E+00 0.00E+00 3 Notation: An entry of 0.00E+00 does not represent the absence of a radionuclido but indicates that the concentration of the nuclide was below the LLD valvo listed in Table 3.
- Reported values are estimated based on first quarter 1991 composite analyses and second quartor 1991 ventilation exhaust rates.
23 4
4 TABLE 2 (Cont'd)
AIRBORNE EFFLUENTS (Curies)3 Data Period: January 1, 1991 - June 30, 1991 Continuous Mode Nuclide First Quarter Second Quarter others:
Cr-51 1.88E-04 2.95E-03 Mn-54 2.90E-05 1.03E-05 Co-58 5.27E-06 0.00E+00 Fe-59 0.00E+00 0.00E+00 Co-60 1.68E-04 4.78E-05 Zn-65 0.00E+00 0.00E+00 Ag-110m 0.00E+00 0.00E+00 Co-141 0.00E+00 0.00E+00 Co-144 0.00E+00 0.00E+00 Total 3.90E-04 3.01E-03 3 Notation: An entry of 0.00E+00 does not represent the absence of a radionuclide but indicates that the concentration of the nuclide was below the LLD value listed in Table 3.
24
TADLE 3 RADIOACTIVE GASEOUS WASTE LLD VALUES LOWER LIMIT OF TYPE OF DETECTION (LLD)"
ACTIVITY ANALYSIS fuci/ml)
Principal Gamma Emitterab ,c 1x10~4 H-3c 1x10-6 I-131 d 1x10-12 1-133 d 1x10-10 Principal maa Emitters b,o 1x10-11 (I-131, others)
Gross Alpha f 1x10~11 Sr-89, Sr-909 1x10~11 Table 3 Notations aThe LLD is defined, for purposes of these specifications, as the ,
smallest concentration of radioactive material in a sample that will yield a net count, above system background. that will be detected with 95% probability with only 5% probability of falaely concluding that a blank observation represents a "real" signal. <
For a particular measurement system, which may include radiochemical separation:
4.66 sb LLD =
E x V x 2.22 x 10 6 x y x exp (-Aot) 25
Table 3 Notations (Cont'd)
Where r LLD iu the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb is the standard deviation of the background counting rate i or of the counting rate of a blank sample as appropriate, as counts por minuto, E is the counting officiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10 6 is the number of disintegrations por minute per microcurie, ;
Y is the fractional radiochemical yield, when applicable, A is the radioacti for the particular radionuclido (sec-je)decay and constant at for plant affluents is the elapsed time between the midpoint of sample collection and the time of counting (sec).
Typical values of E, V, Y, and at should be used in the calculation. r It should be recognized that the LLD is defined as an a nrlori (before the fact)-limit representing the capability of a measurement system and not as an a nosteriori (af ter the fact) limit for a particular measurement.
D The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xc-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, I-131, Cs-134, Cs-137, Cc-141 and Ce-144 in-iodine and particulate releases. This list does not mean that only these nuclides are to be considered.
Other gamma peak ~ that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report.
c Monthly grab sample and analysis d Continuous charcoal sample analyzed weekly
" Continuous particulate sample analyzed weekly f
Composite particulate sample analyzed monthly 9Composite pr.rticulate sample analyzed quarterly 26
TADLE 4 WATERDORNE EFFLUENTD - SUKMATION OF .'.LL *i '4 LEADED Data Period January 1, 1991 - June 30, 1991 BATCH MODE Est. Total Nuclide Category Unit lot Quarter 2nd Quarter Error, 4 A. Fission & Activation Products
- 1. Total Release Ci 6.41E-03 1.37E-03* 17
- 2. Average Diluted Concentration pCi/ml 3.68E-08 3.07E-08*
- 3. Percent of Applicable Limit % 8.97E-02 4.37E-0?*
D. Tritium
- 1. Total Release ci 9.11E-01 3.87E-01 16
- 2. Average Diluted Concentration pCl/ml 5.23E-06 8.67E-06
- 3. Percent of Applicable Limit % 1.74E-01 l 2.89E-01 C. Dissolved and Entrained Gasgs
- 1. Total Release Ci 0.00E+00 0.00E+00 11+
- 2. Average Diluted Concentration pCi/ml 0.00E+00 0.00E+00
- 3. Percent of Applicable Limit % 0.00E+00 0.00E+00 D. Gross Alpha Radioactivity Released Ci 0.00E+00 0.00E+00 57 E. Volume of Waste gal. 4.23E+05 9.64E+04 11 Released liters 1.60E+06 3.65E+05 F. Volume of Dilution gal. 4.56E+07 1.17E+07 2.6 Water Used liters 1.72E+08 4.43E+07
- Reported values include Fe-55, Sr-89 and Sr-90 values based on first quarter 1991 sample analyses and Second Quarter discharge volumes.
4 Notation: An entry of 0.00E+00 does not represent the absence of a radionuclide but indicates that the concentration of'the nuclide was below the LLD value listed in Table 6.
+ This error is associated with the gamma spectroscopy system, j oven though noble gas ercivity is <LLD.
i 27
TADLE 5 WATERDORNE EFFLUENTS (Curics)5 Data Period: January 1, 1991 - June 30, 1991 Batch Mode Nuclide First Quarter Second Quarter A. Tritium 9.11E-01 3.87E-01 B. Fission & Acti-vation Products Cr-51 0.00E+00 6.00E-04 Mn-54 1.54E-03 1.26E-04 Co-58 2.50E-04 0.00E+00 Co-60 4.13E-03 5.34E-04 Fe-55 4.87E+04 1.11E-04*
Fe-59 0.00E+00 0.00E+00 Zn-65 0.00E+00 0.00E+00 Sr-99 0.00E+00 0.00E+00*
Sr-90 0.00E+00 0. 00E+ 00*
Mo-99 0.00E+00 0.00E+00 Sb-124 0.00E+00 0.00E+00 I-131 0.00E+00 0.00E+00 I-133 0.00E+00 0.00E+00 I-135 0.00E+00 0.00E+00 Cs-134 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E400 Ba-140 0.00E&OO 0.00E400 La-140 0.00E+00 0.00E+00 Co-141 0.00E+00 0.00E+00 Ag-110m 0.00E+00 0.00E+00 Total 6.41E-03 1.37E-03 C. Dissolved and Entrained Gases Kr-85 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E400 Xe-133 0.00E+00 0.00E+00 Xe-133m 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 Xe-135m 0.00E+00 0.00E&OO Xe-138 0.00E400 0.00E+00 Total 0. 0 0 E+30 *.,
0.00E+00
'*o 5 Notation: An entry of 0.00E+00 does not represent the absence of a radionuclide but indicates that the concentration of the nuclide was below the LLD value listed l in Table 6.
- Reported value is estimated based on first quarter 1991 sample analyses and second quarter 1991 discharge volumes.
28
TADLE 6 RADICACTIVE LIQUID WASTE LLD VALUES LOWER LIMIT OF TYPE OF DETECTION (LLD)"
__ ACTIVITLAlfALYJ.'3
_ (nQi/mii Principal Gamma Emitters b 5x10~7 I-131 1x10-0 Dissolved and Entrained Gasos 1x10'S (Gamma Emitters)
H-3 1x10-5 Gross Alpha 1x10-7 Sr-89, Sr-90 5x10-8 Fe-55 1x10-6 Table 6 Notations aThe LLD is defined, for purposes of these requirements, an the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4.66 sb LLD =
E x V x 2.22 x 10 6 x y x exp (-Aat) 29
lable 6 flotations (Cont'd)
Whore:
LLD is the "a priori" lower limit of detection as defined above, as microcuries por unit mass or volume, sd is the standard deviation of the background counting rate or of the counting rate of a blank samplo as appropriato, as counts por minuto, E is the counting officiency, as counts por disintegration, V is the sample size in units of mass or volume, 2.22 x 10 6 is the number of disintegrations per minuto por microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioacti}e decay constant for the particular radionuclido (soc- ) and .
At for plant offluents is the elapsed time between the midpoint of sample collection and the timo of counting (soc).
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a nriori (before the fact) limit representing the capability of a measurement system and not as an a nosteriori (after the fact) limit for a particular measurement.
b The principal gamma emitters for which the LLD requirement applies 'ncludo the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce Ce-144 shall also be measured, but with an LLD of 5 x 10~gl41.This list .
does not mean that only those nuclides are to be detected and reported. Other gamma peaks that are measurable, together with those of the abcVe nuclidos, shall also be analyzed and reported in the Semiannual Radioactive Effluent Roloaso Report.
30 7__. p..y..- 9, m.-y-., , .
,,,,7,,,,,e,,,,7 7,,m,,,,...,y;,,,-,,3.,,,w.,, pw,,,,,p-,,,mw,~,y,,-,, . _ - ,,..,4%.-% ,,c., % r en..- ,oy._.,5 -__<r- -c ., . ,
RQLID WASTE AND IRRADI ATED FUEL DJ11 die}{TH During this reporting period there were thirty-eight (38) radioactive waste shipments and no irradiated fuel shipments from CPS as reported in Table 7. All wasto shipped in this reporting period was classified as class A. In addition, the CPS OCDM requires reporting of the following information for solid waste shipped offsite during the ' port period:
- 1. Total curio quantity: 439 curies as determined by dose-to-curio and sample concentration methodology ostimates.
- 2. Principal radionuclidos: Soo Tabic 7, A.2 for listing of monsured radionuclidos.
- 3. Source of waste and processing employed: Rosins, filter sludges and evaporator bottoms downtored or solidified in cement. Compacted and non-compacted dry active wasto.
- 4. Type of container: LSA, Type A, and Strong Tight Container.
- 5. Solidification agent or absorbent: Coment, Aquaset I and II, and Petroset I and II (no absorbents used).
l l
l 31
_ - . _ _ . _ _ _ _ _ _ _ _ ~ __ . _ - _ _ _ _ __. .__ _ _ ___ _ _._.. -
TABLE 7 SOLID WASTE AND IRRADIATED FUEL SilIPMENTS January 1, 1991 - June 30, 1991 A. SOLID WASTE S!!IPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-MONTl! EST. TOTAL
- 1. TYPE OF WASTE UNIT PERIOD ERROR, %
- a. Resins, m3 1.44E+02 filter sludges, C1 4.38E602 25 evaporator bottoms, etc.
- b. Dry compactible m3 2.83E+01*
waste, contaminated Ci 9.98E-01 25 equipment, etc.
- c. Irradiated components m3 0.00E400 control rods, etc. Ci 0.00E+00 0
- d. Other m3 0.00E+00 Ci 0.00E+00 0
- Actual Volume Reduced by Waste Processor
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION NUCLIDE PERCENT NAME ABUNDANCE CURIES
- a. Fe-55 47.20% 2.07E+02 Co-60 38.72% 1.70E+02 Mn-54 8.28% 3.63E+01 Cr-51 4.25% 1.86E+01 OTIIER 1.56% 6.83E+00
- b. Fe-55 53.66% 5.35E-01 Co-60 23.84% 2.38E-01 Cr-51 12.20% 1.22E 01 Mn-54 8.49% 8.47E-02 Co-58 1.79% 1.79E-02 OTilER 0.008% 7.98E-05
- c. NONE N/A N/A
- d. NONE N/A N/A 32
TABLE 7 (Cont'd)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1991 - June 30, 1991
- 3. SOLID WASTE DISPOSITIOli ,
NUMBER OF SalIPMENTS MODE OF TRANSPORTATIO!1 DESTINATIO!1 24 Truck Richland, WA 4 Truck Barnwell, SC 2 Truck Quadrox 8 Truck SEG B. IRRADIATED FUEL SHIPMENTS (Disposition) .
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION NONE N/A N/A l
l l
l-l 33 1
TABLE 8 CORRECTIONS TO DATA REPORTED IN PREVIOUS BEMIANNUAL REPORTS I. CORRECTION TO VOLUME OF WASTE S11IPPED A. Parameter of concern: First half of 1990, Table 5, Section A, Item 1.b.
- 1. Reported Value 7.32E+02 m 3 Corrected Value 8.19E+01 m 3 II. CORRECTION TO JOINT WIND FREQUENCY DISTRIBUTION A. Parameter of concerns 1990 Stability Class A Wind Speed at 60 Motor Level.
- 1. a) Reported value: SGW, 8-12 MPH, 9.02E 01 b) Corrected Value: SSW, 8-12 MPH, 9.20E 01
- 2. a) Reported value: NW, >24 MPH, 2.70E 01 b) Corrected value: NW, >24 MPH, 2.00E 01 B. Parameter of concern: 1990 Stability Class E Wind Speed at 60 Meter Level.
4
- 1. a) Reported value: N, 19-24 MPH, 4.00E 01 b) Corrected values N, 19-24 MPH, 4.00E 00
- 2. a) Reported value: NNE, 19-24 MPH, 6.00E 01 b) Corrected value: NNE, 19-24 MPH, 6.00E 00
- 3. a) Reported value: NC, 19-24 MPil,-7.00E 01 b) Corrected value: NE, 19-24 MPil, 7.00E 00
- 4. a) Reported value: ESE, 19-24 MPil, 1.00E 01 b) Corrected value: ESE, 19-24 MPH, 1.00E 00
- 6. a) Reported value: SJE, 19-24 MPil, 2.30E 00 b) Corrected value: SSE, 19-24 MPil, 2.30E 01 l 7. a) Reported value: SSW, 19-24 MPH, 1.24E 01 b) Corrected value: SSW, 19-24 MPH, 1.24E 02
- 9. a) Reported value: WSW, 19-24 mph, 1.20E 00 b) Corrected value: WSW, 19-24 MPil, 1.20E 01 34 i
l-
M TADLE B (Cont'd)
CORRECTIONS TO DATA REPORTED IN PREVIOUS SEMIANNUAL REPORT i
II. CORREC.TIoll TO JOINT WIND TREQUENCY DISTRIBUTION (Cont'd)
D. 10. a) Reported value TOTAL, 19-24 MPit, 3.36E 01 b) Corrected value, TOTAL, 19-24 MPil, 3.36E 02 C. Parameter of concern! 1990 Stability Class G Wind Speed at 10 Meter Level.
- 1. a) Reported valuot ESE, TOTAL, 2.10E 01 b) Corrected valuot ESE, TOTAL, 3.10E 01
- 2. a) Reported valuot NNW, TOTAL, 2.00E-01 b) Corrected value NNW, TOTAL, 2.00E 01 35
TABLE 9 EFFLUENT PREVIOUS DATA SEMIANNUAL NOT AVAILADLE REPORT {0R Data Periods October 1, 1990 - December 31, 1990 Nuclide Category Unit Fourth Quarter 1990 A. Airborne Effluents
- 1. Sr-89 Ci 0.00E+00
- 2. Sr-90 Ci 0.00E+00 B. Waterborne Effluents
- 1. Fe-55 Ci 0.00E+00
- 2. Sr-89 Ci 0.00E+00
- 3. Sr-90 Ci 0.000400 6 Nothtion: An entry of 0.00E+00 does not represent the absence of a radionuclide out indicates that the l
concentration was below the LLD value listed in Table 3.
36
SECTION 5 METEOROLOGICAL DATA l
l
NETEOROLOGICAL DATA AND DISPER8 YON ESTIHhTKg i-I' The meteorological monitoring program began at the Clinton Power Station site on April 13, 1972. The meteorological system consists of a tower 199 feet high with two levels of l instrumentation, at the 10-meter and 60-meter levels. Wind directions and speeds at the 10-meter and 60-meter levels are measured by a combined cup and vane sensor. The temperature at these levels is sensed by an aspirated dual temperature sensor.
One-half of the dual sensor at each elevation is used for ambient temperature while the other half is used to provide a differential tenperature between the 10- and 60-meter levels.
Dew-point is measured at the 10-meter level with an aspirated dew-point sensor. Precipitation is measured at ground level by a tipping bucket rain gauge.
Meteorological monitoring instruments have been placed on. the Clinton-Power Station microwave tower at the 10-meter level to act as a backup to the existing meteorological tower.
'Clinton Power Station meteorological data is transmitted to the Main control Room via a dedicated telephone line. There the signals are received and converted to a 4 to 20 milliamp signal and fed individually to a microprocessor and chart. recorders.
The microprocessor is part of the Clinton Power Station Radiation Monitoring System. Meteorological data is available via the microprocessors in the Main Control Room, Technical Support Center and Radiation Protection office.
Dispersion modeling for effluents for normal operation of Clinton Power Station is a straight-line, sector-averaged Gaussian plume model designed to estimate average relative concentration at various receptor points. The model was developed in accordance with routine' release analysis procedures specified in Regulatory Guide 1.111. For joint frequency input data, periods of calm are '
distributed in accordance with a directional distribution. For hourly input data, periods of calm are assigned the previous hour's-wind direction. Periods of calm are assigned a wind speed value of half-the specified instrument threshold value. .See Tables'10-12 and Figures 5-7 for more detailed information on meteorology-and dispersion data.
37
- ,_...._ _ _ .. _ ._ ....._._ , _ ..,._ ._.,_.. _ _.._,_ ._.,. _ .._._... .._ -._ ._ __ ~ . _ _ . _ _
l 1
l TADLE 10 METEOROLOGICAL DATA AVAILADILITY Data Periodt January 1, 1991 - June 30, 1991 Percent of Valid Parameter Hours Durinct Perind
- 1. Wind Speed
- a. 10-meter Sensor 88%
- b. 60-meter Sensor 85%
- 2. Wind Direction l
- a. 10-meter Sensor 88%
1
- b. 60-meter Sensor 85%
- 3. Temperature a
- a. 10-meter 88%
- b. Temperature Difference (10m-60m) 84%
- 4. Percent of hours for which valid 84.4%
10-meter Wind Speed, Wind Direction,
& Delta Temperature were available
- 5. Percent of hours for which valid 81.9%
60-meter Wind Speed, Wind Direction, 1
& Delta Temperature were available 38
- , _. _ ~ . . . _ _ _ _ . , _ _ _ _ _ _ . ..__ _. . _ . _ _
I FIGURE 5 CPS.WIllD ROSE: 10-METER Data Period: January 1, 1991 - June 30, 1991 N
NNV NNE 3.0% 4.0%
NV NC 5.4 8 P, 7,1 y,
=
VNV 6.7% .-
[-M ENE 5.93%
% s b \ ._-
,// -
h, w' ,/
4.0% b- I IIIIIIIIIE\M 5%
gd. ,
m, x v j \ *s, '*
/ / s \ 's, VSV / \\
Est 4,45% y @ ,
4,1 y, N
SV ;
6.8% @ S[
= 6.2%
\
E l
> 24 MPH h 19 - 24 MPH 13 - 18 MPH shs 8 - 12 MPH
[ 4 - 7 MPH 39 1 -3 MPH L
. . - . . . . - - - - . . - . . . - ~ . - - - - - . . . _ . - - _ . - - . . _ . . _ . . - . . . _ - - .
I FIGURE 6 CPS WIND ROSE 60-METER Data Period: January 1, 1991 - June 30, 1991 N
NNV NNE 3.59% 4.2%
NV NE i 5.83% 6.38%
=
VNV E ENE 4.46% = 2 6.1 %
s -
M s
... {. .s 4.36% I - I N I 6.5%
t 0. 6 <. **
K W/
VSV / ,/ ESE 5.6% 3.7%
=
=
=
=
=
E SV =
7.6% - S[
5.06%
33 gg Vind Speed Key
> 24 MPH l g f 19 - 24 MPH I
13 - 18 MPH
( 8 - 12 MPH r 4 - 7 MPH 40 ,
1 -3 MPH
Ld td J l LD f d -J Ld Q
r g
m m a W T m kt Z <
$ El a H k Z nh o>q o it m it mit H lt zn a sM aN 3J"*. me*
>N J O 0 0 N w"J WN H >
N N N WN H
>N J
W 2
wx wexe%sx;b h hd weh2h wy w En a o ao o E w xn as as wg as 98 x 2- 00 +- ZN to m um W- M
- td .-
u sm
- 3 $ 2 3 ['] @ []'] j Hm o,_
M w -
o A O o Z4" OHO c o
O m 7cU 3 Dm
<g f,g,rf777'm <x yN;s .
y,;xss
.o m 9
m 0;; I 7
9?Y,kN' l co "2
- c:s 5m <:t y
[]w'fLj)%;yy;qyce$'g,7 M'hil5!I$ 4, / xs xx
/
w s:ma "
cr is ///,4,g,,h: 6 X L'c ', A ^ ^3\
~ ^ uc J o o ,- h8 @. ,X X X'X. E8 h / / wxx x
/
o ax /g,;$$:+'amS E Zo D* h g
%g,"fk,wl5:if;p$w$f'f' kF gygi:3hkIjhk'q,ikh qp>
d g 'xy*f>(>Dh'(x)b, sX y Nx b
x 0 1 u o u- 8 sx Z o ,0 -
e
- m,,f , y e,,s,9 p y #;f,/0 cyvyyy , c3;g +pe,,w on w cvs>vsA<gy-o R&
V, % i <
. . f/
, / f .
~
o .o
~u y,,vj,
/:9,7,,,xy i
'N
'Ns '< xs x xNsxfv x<ya eo ex c e y . _ .
,a p a. sy, ' sx 'N s syy mo N
\sN N c 3 o
~~
\ s Ee m
y ~s xNNNss N N> -
m W s s' \ N o h 54 A y 41
TABLE 11 CLASSIFICATION OF ATMOSPHERIC STADILITY Stability Pasquill Defining Classification Categories Conditions Extremely unstable A -0.900<ATs-0.019 Modcrately unstable B -0.019<ATs-0.017 Slightly unstable C -0.017<ATs-0.015 Neutral D -0.015<6TS-0.005 Slightly stable E -0.005<ATs 0.015 Mod rately stable P 0. 015 < ATs 0. 04 0 Extremely stable G O.040<6Ts 0. 00 Invalid ATS-0.900 or AT>0.900 AT = temperature difference in Celsius degrees per meter f '
'h'
+
42
.. - . _ - . . . _ . - _ _ _ - _ . _ _ . _ , _- ~ . _ _ _ - . _ _ _ _ _ _ - - . . . - _
1ABLE 12, Pope 1 of 7 JOINT ltIND FREQUENCY DISTRIDUTION BY STADILITY CLASS Data Period: January 1, 1991
- June 30, 1991 11ABillTY tt451 A VIWD $ PEED (MrW) At 10 utite Ltytt Dftttflow 13 47 8 12 13 1E 19 24 >24 Tot AL _
u 3.00E 00 1.60E 01 2.20E 01 1.50E 01 0.00E 01 0.00E 01 5.60E 01 hwE 3.00E 00 1.20E 01 1.30E 01 1.20E 01 0.00E 01 0.00t 01 4.00E 01 EE 3.00E 00 1.80E 01 4.00E 01 1.80E 01 2.00E 00 0.00E 01 8.10E 01 eke 8.00E 00 1.90E 01 5.50E 01 3.60E 01 1.00E 00 0.00E 01 1.19E 02 E 2.00E 00 2.40E 01 4.00E 01 3.80E 01 9.00E 00 0.00E 01 1.13E 02 ESE 2.00E P3 2.$0E 01 3.0DE 01 8.00E 00 0.00E 01 0.00E 01 6.50E 01 SE 6.00E 00 3.80E 01 3.90E 01 2.00E 00 0.00E 01 0.00E 01 8.50E 01
$$t 9.00E 00 3.20E 01 3.70E 01 1.10E 01 0.00E 01 O 00E Oi , 8.90E 01 8 5.00E 00 2.70E 01 6.50E 01 3.30E 01 7.00E 00 0.00E 01 1.37E 02
$$W 3.00E 00 2.20E 01 6.40E 01 3.60E 01 0.00E 01 0.00E 01 1.25E 02 SW 3.00E 00 1.90E 01 6.60E 01 3.60E 01 0.00E 01 0.00E 01 1.24E 02 WSW 2.00E 00 8.00E 00 3.50E 01 2.10E 01 4.00E 00 2.00E 00 7.20E 01 V 1.00E 00 4.00E 00 2.00E 01 1.30E 01 1.00E 01 4.00E 00 5.20E 01 WW 1.00E 00 7.00E 00 1.30E 01 1.20E 01 3.00E 01 1.90E 01 8.20E 01 WW 2.00E 00 1.70E 01 3.10E 01 1.20E 01 1.30E 01 3.00E 00 7.80E 01 WWW 5.00E 00 9.00E 00 2.90t Q1., 1.10E 01 0.00E 01 0.00t 01 5.40t 01 10TAL 5.80E 01 2.97E 02 5.99E 02 3.14t 02 7.60E 01 2.80E 01 1.37E 03 PERIOOS OF CALM (NOUR$): 4.00E 00 WlWD $PtfD (MPW) At 60 Mf f Er t E VE L DIRECTION 13 47 8 12 13 18 19 24 324 total.
N 2.00E 00 1.50E 01 1.60E 01 1.50E 01 8.00E 00 0.00E 01 5.60E 01 kWE 3.00E 00 6.00E 00 1.00E 01 5.00E 00 1.00E 01 0.00E 01 3.40E 01 NE 2.00E 00 8.00E 00 1.30E 01 3.t )E 01 1.30E 01 8.00E 00 8.00E 01 ENE 6.00E 00 9.00E 00 2.40E 01 2.70E 01 3.10E 01 1.40E 01 1.11E 02 E 2.00E 00 1.20E 01 1.80E 01 3.50E 01 2.10E 01 3.50E 01 1.23E 02 ESE 3.00E 00 1.10E 01 2.60E 01 1.60E 01 5.00E 00 0.00E*01 6.10E 01 SE 1.00E 01 2.80E 01 2.60E 01 1.10E 01 1.00E 00 0.00E 01 7.60E 01 sst 5.00E 00 1.90E 01 2.10t 01 2.40E 01 9.00E 00 1.00E 00 7.90E 01
$ 6.00E 00 2.00E 01 3.90E 01 5.00E 01 1.30E 01 9.00E 00 1.37E 02
$5W 3.00E 00 8.00E 00 5.00E 01 6.00E 01 1.40E 01 2.00E 00 1.37E 02 SW 2.00E 00 7.00E 00 4.50E 01 5.00E 01 1.60E 01 0.00E 01 1.20E 02 WSW 3.00E 00 4.00E 00 2.90E 01 2.50E 01 1.70E 01 5.00E 00 8.30E 01 W 0.00E 01 4.00E 00 1.50E 01 7.00t 00 5.00E 00 1.00E 01 4.10E 01 WW 0.00E 01 6.00E 00 1.00E 01 7.00E 00 6.00E 00 3.30E 01 6.20E 01 WW 1.00E 00 1.20E 01 2.80E 01 9.00E 00 9.00E 00 2.60E 01 8.50E 01 WWW i.00E 00 8.00E 00 3.00E 01 1.30E 01 2.00E 00 1.00E 00 5.50E 01 TOTAL 4.90E 01 1.77E 02 4.00E 02 3.90E 02 1.80E 02 1.44E 02 1.34E 03 PER100$ OF EALM (HOUR $): 2.00E 00 43
- - -- - .~ __ . -. - - - _ - - . -- --- - - .- .. --
l l
1ABLE 12 Pepe 2 of 7 JOINI WIND PREQUfWCY DisfRIButlDN SV $1AllLITY CLAS5 Data Period: January 1, 1991 June 30, 1991
$fABILITY CLA$$ $
gik0 ttttD (MPN) At 10 MEftR Ltytt Ditttt f DN i3 47 8 12 13 18 19 24 *26 707A1_.
N 0.006 01 1.00E 00 3.00t 00 3.00E 00 0.00E 01 0 00t 01 r.00t 00 NWE 0.00E 01 1.00E 00 1.00t 00 0.00E 01 3.00E 00 0.00t 01 $.00E 00 NE 0.00E 01 3.00E 00 3.0^t 00 3.101 00 2.00t 00 0.00t 01 1.100 01 ENE 0.004 01 0.00E 01 5.00E 40 0.90E 01 0.0DE 01 0.00E 01 $.00E 00 E 0.00t 01 2.00t 30 2.00E 06 U.00E 01 0.00t 01 0.008 01 4.00t 00 ftE 0.00t 01 $.00t 06 4.00t 00 1.00E 00 0.00E 01 0.00E 01 1.00t 01
$E 0.00E 01 3.00E (0 2.00E 00 0.00E 01 0.00E 01 0.00E 01 $,00E 00
$$E 0.00E 01 3.00E 00 0.00t 01 0.00E 01 0.00E 01 0.000 01 3.00t 00
$ 1.00E 00 3.00E 00 2.00E 00 3.00t 00 0.00E 01 0,00t 01 9.00E 00
$5W 0.00E 01 0.00E*01 2.00E 00 3.00t 00 0.00E 01 0.00t 01 5.00t 00 SW 0.00E 01 1.00t 00 0.00E 01 1.00E 00 0.00t 01 0.00t 01 2.00t 00 WsV 0.00E 01 1.00E 00 1.00t 00 1.00E 00 0.00t 01 0.00t 01 3.000 00 W 0.00E 01 0.00t 01 4.00t 00 6.00t 00 1.00t 00 2.00E 00 1.30t 01 WNW 0.00E 01 0.00E 01 0.00t 01 4.00t 00 6.00t 00 1.00t 00 1.10E 01 WW 0.00E 01 1.00t 00 4.00t 00 3.00t 00 0.00t 00 0.00t 01 8.00E 00 NEW 0.00E 01 0.00E 01 0.00E 01 8.00t 00 0.00t 01 0.00t 01 8.00t 00 TOTAL 1.00t 00 2.40E 01 3.30E 01 3.60E 01 1.20E 01 3.00t 00 1.09E 02 F'[R100$ OF CALM (HQ)R$): 0.00E-01 WIND $ PEED (MPH) At 60 MEff R LEVEL Q1pf tflDW 13 47 8 12 13 18 19 24 >24 total N 0.00E 01 0.00E 01 3.00E 00 5.00t 00 2.00E 00 0.00E 01 1.00E 01 WWE 0.00E 01, 0.00E 01 0.00E 01 1.00E 00 0.00E 01 4.00E 00 5.00t 00 NE 0.00E 01 0.00E 01 1.00E 00 3.00t 00 2.00E 00 3.00E 00 9.00E 00 ENE 0.00E*01 0.00E 01 2.00E 00 4.00E 00 0.00E 01 0.00E 01 6.00t 00 E 0.00E 01 0.00E 01 3.00E 00 0.00t 01 2.00t 00 0.006 01 $.00E 00 (St 0.00E 01 0.00E 01 6.00t 00 1.00t 00 0.00E 01 0.00t 01 7.00E 00
$E 0.00E 01 0.00E 01 2.00t 00 2.00E 00 1.000 00 0.00t 01 5.00E 00
$st 0.00E-01 1.00t 00 2.00E 00 0.00t 01 0.00E 01 0.00E 01 3.00E 00 8 1.00t 00 4.00E 00 2.00E 00 1.00E 00 1.00E 00 1.00[ 00 1.00E 01 stW 0.00t*01- 0.00E-01 1.00t 00 3.00E 00 2.00t 00 0.00t 01 6.00E 00
$W 0.00E 01 1.00t 00 0.00E 01 0.00E 01 1.00t 00 0.00E 01 2.00t 00 WsW 0.00E 01 1.00t 00 1.00E 00 0.00E 01 1.00E 00 0.00E 01 3.00[ 00 W 0.00E 01 0.00E 01 4.00E 00 2.00E 00 4.00E 00 3.00t 00 1.30E 01 WWW 0.00E 01 0.00E 01 0.00E 01 3.00t 00 1.000 00 6.00E 00 1.00E 01 NW - 0.00E 01 0.00E 01 0.00E 01 1.00t 00 2.00E 00 0.00E 01 3.00E 00 NWW 0.00E 01 1.00E 00 2.00E 00 1.00E 00 4.00E 00 0.00E 01 8.00E 00 TOTAL 1.00E 00 8.00t 00 2.90f 01 2.70t 01 2.300 01 1.70E 01 1.05E 02 PERIODS OF CALM (HOURS): 0.00E 01 44
, -' - =yw-ys, -y--+=w v- ,r , -ce w '-< - --w- ---=v- w g- - e---w-
l 1
i i
1ABLE 12. Page 3 of 7 J0lWT W1WD fit 0UthCY Ottititufl0N SY STABill!Y CLAtt Date Period: Jeruary 1,1991 Jme 30,1991 11tBitITY CLAll C y, lwd tottD (kru) At 10 WEtte Livik Diptet10N 13 47 8 12 13 18 19 24 *24 tota L W 0.00t 01 3.00E 00 4.00t 00 2.00t 00 0.00t 01 J.00f 01 0.00E 00 NWt 0.00t 01 1.00t 00 2.00t 00 '.00t 00 1.00t 00 C.00t C1 8.00t 00 Wt 0.00E 01 1.00t 00 6.00t 00 5.00t 00 0.00t 01 v.00E 01 1.20t 01 EWE 0.00t 01 4.00t 00 6.00t 90 1.00t 00 0.00t 01 0.00t 01 1.10t 01 E 0.00E 01 6.00t 00 1.00t (* 0.00t 01 0.00t 01 0.00t 01 7.00t 00 ESE 1.00t 00 1.00t 00 2.00t 00 0.00E 01 0.00t 01 0.00t*01 4.00t 00 5t 0.00t 01 2.00t 00 4.00f 00 1.00t 00 0.00t 01 0.00t 01 7.001 00
$$t 0.00t 01 0.00t 01 0.00t 01 0.00t 01 0.00t 01 0.00E 01 0.00t 01 8 0.00E 01 1.00t 00 4.001 00 3.00t 00 0.00E 01 0.00t 01 8.001 00
$$W 0.00E 01 1.00t 00 6 ODE 00 2.00t 00 0.00t 01 0.00t 01 9.00E 00 SW 0.00t 01 0.00t 01 0.00t 01 2.00t 00 0.00t 01 0.00t 01 2.00t 00 V5W 0.00E 01 1.00t 00 0.00t 01 3.00t 00 1.00t 00 0.001 01 5.00t 00 W 0.00t 01 0.00E 01 1.00t 00 7.00t 00 0.00t 01 1.00t 00 9.00t 00 WW 0.00E 01 1.00t 00 2.00t 00 6.00t 00 1.00t 00 3.00t 00 1.30t 01 WW 0.00E 01 1.00t 00 3.00t 00 6.00t 00 1.00t 00 0.00t 01 1.10t 01 WWW 0.006 01 1.00t 00 2. ppt 00 3.00t 00 0.00t 01 0.00t 01 6.00t 00 TOTAL 1.00t 00 2.40t 01 4.3at 01 4.50t 01 4.00t 00 4.00E 00 1.21E 02 PERIOOS OF CALM (HCUR$): 0.00E 01 I
WlWD $PtfD (MON) 41 60 MEttR ttVfL.
OIRECflow 13 47 8 12 13 18 19 24 >24 TOTAL W 0.00E 01 2.r0E 00 0.00E 01 4.00t 00 4.00t 00 0.00E 01 1.00t 01 NWE r!.0CE 01 2.00t 00 4.00t 00 2.00E 00 3.001 00 1.00t 00 1.20t 01 ht 0.00E 01 0.00E 01 1.00t 00 1.00f 00 6.00t 00 3.00t 00 1.10t 01 .
ENE 0.00E 01 1.00t 00 1.00t 00 3.00t 00 3.00t 00 0.00t 01 8.00t 00 t 0.00E 01 0.00E 01 3.00E 00 4.00E 00 0.00E 01 0.00t*01 7.00t 00 Ett 1.00C 00 1.00E 00 0.00E 01 2.00t 00 0.00t 01 0.00E 01 4.00t 00
$t 0.00t 01 0.00E 01 3.00E 00 2.00t 00 0.00E 01 0.00t 01 5.00t 00 S$t 0.00E-01 0.00E 01 0.00t 01 1.00t 00 1.00t 00 0.00E 01 2.00t 00
$ 0.00E 01 1.00t 00 0.00E 01 4.00f 00 2.001 00 0.00E-01 7.00t 00
$$W- 0.00E 01 1.00t 00 1.00t 00 5.00t 00 1.00t 00 0.00t 01 8.00t 00 SW 0.00E 01 0.005 01 0.00E 01 1.00E 00 2.00t 00 0.00E 01 3.00E 00 WSW 0.00E 01 1.00E 00 0.00E 01 2.00t 00 2.00E 00 1.00t 00 6.00E 00 W 0.00E 01 0.00E 01 0.00E 01 3.001 00 3.00t 00 0.00E 01 6.00E 00 WWW 0.00E 01 1.00t 00 0.00t 01 4.00t 00 2.00t 00 4.00t 00 1.10t 01 NW 0.00E 01 0.00E-01 2.00E 00 6.00t 00 6.00t 00 1.00t 00 1.50E 01 kWV 0.00t 01 1.00t 00 1.00t 00 1.00t 00 1.00t 00 0.00E 01 4.00f 00 TOTAL 1.00E 00 1.10t 01 1.60t 01 4.50t 01 3.60E 01 1.00E 01 1.19E 02 l
! Ptt100$ OF CALM (MOURS): 0.00E 01 45 1
1' i
l l_-
_-_ ___ . . _ _ _ _ _ _ _ _ _ . _ _ _ ._. ._____.m_ _ _ _ _ _ _ _ m.__ _ _
TABLE 12, Page 4 of 7 l
J0thf WIND FREQUENCY 0!$1RIBUllDN BY $1AllLl1T CLA$$
Data Period: January 1,1991 Jme 30,1991
$1491LifY CLAtt g WIND Settb (MPW) AT 10 WEff e LEVil bl Ri tT
- DN 13 47 8 12 13 18 19 24 >24 TOTAL N 0.00E 01 6.00t 00 5.80t 01 3.20t 01 1.00t 00 0.00E 01 9.70t 01 Nkt 1.00t 00 1.00t 01 1.90E 01 1.50t 01 0.00t 01 0.00t 01 4.50t 01 l Nt 5.00t 00 1.50t 01 3.00t 01 8.00t 00 0.00t 01 0.00t 01 5.80t 01 thE 6.000 00 1.40t 01 1.00E 01 0.00t 01 0.00t*01 0.00t 01 3.00E 01 E 3.00t 00 2.80E 01 8.00t 00 0.00t 01 0.00t 01 0.00t 01 3.90t 01 E$E 3.00t 00 1.70t 01 1.00t 01 0.00t 01 0.00t 01 0.00t 01 3.00t 01 St 0.00E 01 1.70t 01 1.668 01 5.00t 00 0.00E 01 0.00E 01 3.80E 01
$$E 1.00E 00 1.300 01 1.30E 01 5.00t 00 0.00t 01 0.00E 01 3.20t 01 8 1.00t 00 1.00t 01 2.20E 01 1.70E 01 & JOf 00 0.00E 01 5.40E 01
$$W 0.00E 01 1.70E 01 4.10E 01 1.60t 01 2.00E 00 0.00E 01 7.60E 01 SW 2.00t 00 4.00t 00 1.20E 01 5.00t 00 0.00E 01 0.00E 01 2.30E 01 Wsw 2.00E 00 8.00t 00 1.80E 01 7.00t 00 0.00E 01 0.00E 01 3.50t 01 W 2.001 00 1.00E 01 2.20t 01 1.40E 01 3.00E 00 0.00E 01 5.10t 01 WNW 2.00t 00 8.00'; 00 3.30t 01 2.60t 01 0.00t 01 1.00t 00 7.00E 01 NW 2.00t 00 1. ' F, 01 3.40t 01 1.20E 01 0.00t 01 0.00t 01 5.90t 01 NwV 4.00E 00 1.10t 01 3.10E 01 9.00t 00 0.00t 01 0.00E 01 5.50E 01 101AL 3.40E 01 1.99E 02 3.77E 02 1.71E 02 1.00E 01 1.00E 00 7.92t 02 PERIDOS OF CALM (HOUR $): 7.00t 00 WINO $PitD (upM) At 60 ptttR Ltytt Q,EtCTION 13 47 B 12 13 18 19 24 >24 TOTAL N 0.00E 01 1.00t 01 3.50t 01 5.80t 01 9.00t 00 1.00E 00 1.13E 02
, NNE 0.00E 01 6.000 00 1.10E 01 1.40E 01 1.20t 01 3.00E 00 4.60E 01 NE 0.00E 01 5.00E 00 7.00t 00 2.70t 01 1.30E 01 0.00E 01 5.20t 01 ENE 3.00E 00 1.10E 01 5.00t 00 6.001 00 1.00t 00 0.00E 01 2.60E 01 t 1.00t 00 7.00t 00 1.80E 01 1.20t 01 2.00E 00 0.001 01 4.000 01 E5E 3.00E 00 6.00t 00 1.70E 01 4.00t 00 0.00t 01 0.00E 01 3.00E 01 SE 0.00E 01 7.00t 00 1.00E 01 1.20E 01 2.00E 00 2.00E 00 3.30E 01
$5E 0.00t 01 3.00E 00 1.50t 01 9.00t 00 7.00t 00 3.00t 00 3,70t 01
$ 0.00E 01 3.00E 00 1.50E 01 1.90t 01 1.10E C1 8.00E 00 5.60E 01
$$W 0.00E 01 1.00E 00 1.80E 01 3.50E 01 9.00E 00 8.00t 00 7.10E 01 SW 0.00E 01 0.00t 01 1.30t 01 9.00E 00 3.00E 00 0.00E 01 2.50t 01 VSV 2.00t 00 3.00t 00 1.30E 01 1.30E 01 5.00E 00 0.00E 01 3.60E 01 W 0.00E 01 3.00t 00 1.80t 01 2.00t 01 8.00E 00 3.00E 00 5.20t 01 WWW 2.00E 00 1.00t 00 6.00t 00 2.30E 01 5.000 00 1.00t 00 3.80t 01 NW 0.00E 01 5.00E 00 1.10t 01 2.60E 01 8.00t 00 0.00t 01 5.00t 01 WNV 0.00[:01 5.00E 00 1.70E 01 1.40E 01 0.00t 01 0.00t 01 3.60E 01 TOTAL 1.10E 01 7.60E 01 2.29E 02 3.01E 02 9.50E 01 2.90E 01 7.41t 02 PERICO$ OF CALM (HCURS): 1.90t 01 1
46
TABLE 12, Page 5 of 7 J0thi WINO IRE 00EWCY OlSTRIBUT:DW SY $1ABitif f CL ASS Data Period: Jaiuary 1, 1991 Jtrie 30, 1991 iTAlltifY CLAft E VlWD SPEED (WPP) At 10 utfEt LEVEL DIREttt04 13 47 8 12 13 18 19 24 >24 TOTAL W 2.00E 00 1.20E 01 8.00E 00 3.00E 00 0.00E 01 0.00E
- 01 2.50E 01 Wht 8.00E 00 1.70E 01 1.50E 01 5.00E 00 0.00E 01 0.00E 01 4 $0E 01 NE 5.00E 00 3.20E 01 1.10E 01 1.00E D0 1.00E Ou 0.00E 01 5.00E 01 EWE 5.00E 00 1.70E 01 2.00E 00 0.00E 01 0.00E 01 0.00E 01 2.40t 01 E 2.00E 00 2.40E 01 0.00E 01 0.00E 01 0. DOE 01 0.004 01 2.60E 01 ESE 6.0DE 00 1.60E 01 0.00E 01 0.00t-01 0.00E 01 0.0DE 01 2.20E 01 SE 8.00E 00 3.40E 01 1.4DE 01 0.00E 01 0.00E 01 0.0DE 01 5.60E 01 SSE 1.00E 01 3.90E 01 1.00E 01 1.DDE DO 0.00E 01 0.00E 01 6.00[ 01 8 8.00E 00 4.70E 01 5.20E 01 2.20t 01 1.00E 00 0.00E 01 1.30E 02 SSW 6.00E 00 5,.70E 01 8.00E 01 1.50E 01 0.00E 01 0.00E 01 1.58E 02 SW 6.00E 00 3.10E 01 2.20t 01 4.00E 00 0.00E 01 0.00E 01 6.3DE 01 WSW 1.00E 00 1.20E 01 1.10E 01 2.00E 00 0.00E 01 0.00E 01 2.60E 01 W 0.00E 01 1.80E 01 1.2DE 01 1.00E 00 0.00E 01 0 DOE 01 3.10t 01 WWW 5.00E 00 3.00E 01 1.40E 01 3.00t DO 0.00E 01 0.00E-01 5.20t 01 WW 5. DOE 00 1.5DE 01 9. DOE 00 0.00E 01 0.00E 01 0.00t 01 2.90E 01 kWW i.00E 00 8.00E DO __}.00t 00 0.00E 01 0.00E 01 0.00t 01 1.20E 01 TOTAL 7 SOE 01 4.09E 02 2.63E 02 5.7Lt 01 2.00E 00 0.00E 01 8.091 02 PERIODS OF CALM (HOU85): 0.00E 01 VlWD SPEED (MPH) At 60 MLIEW LEVEL DIRECTION i3 47 8 12 13 18 19 24 >24 10 fat N 1.001 00 2.00E 00 1.20E 01 7.00E 00 3.00E 00 0.00E 01 2.50E 01 WWE 1.00: DO 1.00E 01 7.00E 00 1.20E 01 3.00E 00 0.00E 01 3.30E 01 NE 1.00E DO 4.00E D0 1.30E 01 2.70E 01 1.00E 00 2.00E 00 4.80E 01 ENE 1.00E 00 1.00E 00 1.40E 01 8. DOE 00 0.00E 01 0.00E 01 2.40E 01 E 1.00E 00 0.00E 01 1.40E 01 9.00E 00 0.00E 01 0.00E 01 2.40E 01 Est 0.00E 00 6.00t 00 8.00E 00 1.00E 00 0.00E 01 0.00E 01 1.50t 01 SE 3.00E DO 7 DOE 00 1.70E 01 7.00E 00 4.00E DO 0.00E 01 3.80E 01
$$E 3.00E 00 8.0vE 00 3.30t 01 1.70E 01 3. DOE 00 0.00E 01 6.40E 01 S 1.00E 00 1.00E 01 3.90E 01 4.90E 01 2.40E 01 9.00E 00 1.32E 02 SSW 2.00E 00 5.00E 00 3.90E 01 7.20E 01 3.20E 01 2.00E 00 1.52E 02 SW 1.00E 00 - 5.00E 00 2.60E 01 3.70E 01 7.00E DO 0.00E 01 7.BOE 01 WSW 0.00E 00 0. DOE 01 2.20E 01 4. DOE 00 5.00E 00 0.00t 01 3.10E 01 W 1.0DE DO 2. DOE 00 1.20E 01 9.00t DO 3.00E 00 0.00E 01 2.70E 01 VWV 0.00E 00 2.00E 00 1.40E 01 1.10E 01 2.00E 00 0.00E 01 2.90E 01 NW 0.00E 00 9.00E DO 2.40E 01 9. DOE 00 0. DOE 01 0.00E 01 4.20E 01 hvW 0.00E 00 5.00E 00 6.00E 00 3.00E 00 0.00E 01 0.00E 01 1.40E 01 TOTAL 1.60E 01 7.60E 01 3.02E 02 2.62E 02 8.70E 01 1.30E 01 7.26t 02 PERl(DS OF CALM (HOURS): 1.00E 00 47 l
1 l
l 1 ABLE 12, Page 6 of 7 JOINT WIND FREQUENCY DISTRIBUTION DY STADILITY CLASS Data Period: January 1, 1991 June 30, 1991
$TA0lll?Y CLA51.f WIND Sttt0 (utH) A t 10 ht it t_,1DIl Ditttfl0W 13 47 6 12 13 18 19 24 *24 10?AL W i.00t 00 2.00t 00 0.00t 01 0.00t 01 0.00E 01 0.00E 01 3.00t 00 WWE 3.00t 00 1.10t 01 0.00t 01 0.00t 01 0.00t 01 0.00t 01 1.40t 01 ht 5.00t 00 2.70t 01 0.00E 01 0.00s 01 0.00E 01 0.00t 01 3.20t 01 tht 7.00t 00 1.30E 01 0.00t 01 0.00t 01 0.00t 01 0.00t 01 2.00t 01 E 7.00t 00 5.00t 00 0.00t 01 0.00t 01 0.00E 01 0.00t 01 1.20t 01
($t 9.00t 00 5.00t 00 0.00t 01 0.00E 01 0.00t 01 0.00t*01 1.400 01
$t 9.00t 00 1.10E 01 2.00t 00 0.00E 01 0.00t 01 0.00E 01 ?.20I 01 str 9.00t 00 2.50c 01 2.00t 00 0.00t 01 0.00t 01 0.00t 01 3.60t 01 5 6.001 00 1.50t 01 1.80t 01 0.00t 01 0.00t 01 0.00t 01 3.90t 01
$5W 5.00t 00 2.40t 01 1.40C 01 0.00C 01 0.00t 01 0.00t 01 4.30t 01 SW 5.00t 00 1.60[ 01 4.00t 00 0.00t 01 0.00E 01 0.00t 01 2.50t 01 VSW 2.00t 00 1.10E 01 3.00t 00 0.00E 01 0.00t 01 0.00t 01 1.60t 01 W 5.00E 00 9.00t 00 2.00t 00 0.00E 01 0.00t 01 0.00t 01 1.60t 01 WWW 0.00E 01 8.00t 00 0.00t 01 0.00t 01 0.00t 01 0.00t 01 8.00t 00 WW 2.00t 00 4.00E 00 0.00t 01 0.00t 01 0.00t 01 0.ME 01 6.00t 00 WWW 1.Ont 00 1.00t 00 0.00t 01 0.00t 01 0.00E 01 0.00t 01 2.00t 00 107AL 7.60t 01 1.87E 02 4.50t 01 0.00t 01 0.00t 01 0.00E 01 3.08t 02 PtRI005 0F CALM (HOUR $): 0.00E 01 WIND SPitD (MtH) At 60 MtitR l ylk Ditttit0N 13 47 8 12 13 18 ,,,,_i_9 .2 4 - >?4 total W 0.00E-01 0.00E 01 3.00t 00 0.00E-01 0.00t 01 0.00E-01 3.00t 90 -
siht 2.00t 00 2.00t 00 7.00E 00 1.00t 00 0.00t 01 0.00t 01 1.20t 01 WE 0.00E 01 0.00E 01 8.00E 00 9.00t 00 0.00E 01 0.00E 01 1.70t 01 ENE 0.00E 01 0.00E 01 1.40E 01 5.000 00 0.00F 01 0.00t 01 1.901 0) t 0.00t 01 3.00t 00 9.00t 00 6.00t 00 0.00t 01 0.00t 01 1.80E 01 E st 2.00E 00 6.00E 00 2.00t 00 0.00t 01 0.00E 01 0.00E 01 1.00t 01 st 4.00E 00 5.00t 00 5.00t 00 1.00t 00 0.00E 01 0.00t 01 1.50t 01
$$t 2.00t 00 8.00E 00 9.00t 00 9.00t 00 1.00E 00 0.00t 01 2.90t 01 S 2.00t 00 2.00t 00 2.10E 01 8.00t 00 1.30E 01 0.001 01 4.600 01
$$W 1.00t 00 3.00t 00 1.50t 01 1.40t 01 1.00t 01 0.00E 01 4.30t 01 SW 2.00t 00 3.00t 00 1.50t 01 1.70t 01 0.00t 01 0.00E 01 3.70E 01 Wsw 0.00E 01 4.00E 00 8.00E 00 1.20E 01 1.00E 00 0.00E 01 2.50t 01 V 0.00E 01 5.00E 00 3.00t 00 1.00E 00 0.00t 01 0.00E 01 9.00t 00 WWW 0.00t 01 2.00E 00 6.00E 00 1.00t 00 0.00t 01 0.00t 01 9.00E 00 WV 0.00t 01 2.00t 00 6.00t 00 0.00t 01 0.00t 01 0.00t 01 n 00t 00 kWW 1.00t 00 2.00E 00 4.00t 00 0.00E 01 0.00t-01 0.00t 01 7.00E 00 101AL 1.60E 01 4.70t 01 1.35E 02 8.40E 01 2.50t 01 0.00E 01 3.07E 02 PERICOS OF CALM (HOURS): 0.00t 01 48
l 1ABLE 12, Page 7 of 7 JOINT WIND FREQUENCY DISTRIBUTIOh DY STABILITY CLASS Data Pertoo- Jaruary 1,1991 June 30, 1991
[TA,1C
_ ITY CLASS G ML,q,,1P l[MMP*) AT 10 METER LEVEL DIRECT 10W 13 47 8 12 13-1b 19 24 >24 TOTAL _.
N 2.00E 00 1.00E 00 0.00E 01 0. DOE 01 0.00E 01 0.00E 01 3.00E 00 kWE 4.00E 00 1.40E 01 0.00E 01 0.00E 01 0.00E 01 0.00E 01 1.80E 01 WE 5.00E 00 1.10t 01 0.00E 01 0.00E 01 0.00E 01 9.00E 01 1.60t 01 EWE 4.00E 00 6.00E 00 0.00E-01 0.00E 01 0.00E 01 0.00E 01 1.00E 01 E 1.20E 01 3.00E 00 0.00E-01 0.00E 01 0.00E 01 0.00E 01 1.50E 01 ESE 3.00E 00 2.00E DO 0.00E-01 0.00E 01 0.00E 01 0.0DE 01 5.00E 00 SE 1.00E 00 5.00E 00 0.00E 01 0.00E 01 0.00E 01 0.00E 01 6.00E 00
$$E 1.00E 00 8.00E 00 1.00E DO 0.00E 01 0.00E-01 0.00E 01 1.00E 01 8 2.00E 00 6.00E 00 1. DOE 00 0.00E-01 0.00E-01 0.00E 01 9.00E 00
$$W 5. DOE 00 3.00E 00 4. DOE DO 0.00E-01 0.00E 01 0.00E 01 1.20E 01 SW 4.00E 00 1. DOE 01 0.00E 01 0.00E 01 0.00E 01 0.00E-01 1.40E 01 WSW 2.00F 00 8.00E 00 0.00E 01 0.00E 01 0.00E 01 0.00E 01 1.00F 01 W 2.00E 00 0. DOE-01 1.00E 00 0.00C 01 0.00E 01 0.00E 01 3.00E 00 WWW 3.00E 00 3.00E 00 0.00E 01 0.00E+01 0.00E 01 0.00E 01 6.00E 00 JW 4.00E DO 1.00E no 0.00E 01 0.00E 01 0.01E-01 0.00E 01 7.00E 00 WWW 2,00E 00 _Q,00E 01 0.00E-01 0.00E 01 0.00E 01 0.00E-01 2.00E 00 TOTAL 5.80E 01 8.10E 01 7. DOE 00 0.00E 01 0.00E-01 0.00E-01 1.46E 02 PEkl005 0F CAL 1 (P5tRS): 0.00E Gi V1WO SPEED (MPw) At 60 METER LEVEL 01 RECT 10N 1-3 47 8 12 13 18 19 24 324 TOTAL M 1.00E 00 0.00E-01 0.00E 01 0.00E 01 0. DOE -C1 0.00E 01 1.00E 00 NWF 4.00t 00 1.00E 00 0 DOE-01 0.00E 01 0.00E C1 0.00E 01 5.00E 00 7
NE 0.00E 01 1.00E 00 2.00E 00 8.00E 00 0.00E 01 0.00E 01 1.10E 01 ENE 0.00E-01 4.00E 00 4.00E 00 1.3DE 01 0.00E-01 0.00E-01 2.10E 01 E 1.00E 00 2.00E 00 1.00E 01 2.00E 00 0.00E 01 0.00E-01 1.50E 01 ESE 3.00E 00 3.00E 00 2. DOE 00 0 00E-01 0.00E-01 0.00E-01 8.00E 00
/ SE 1,00F 00 6.00E 00 2,00E 00 0.00E 01 0.00E-01 0.00E 01 0 e0E 00 SSE 0.00E-01 4.00E 00 5.00E 00 0.00E 01 1.00E 00 0.00E 01 1.00E 01 S 0.00E 01 0.00t-01 2.00E 00 5.00E 00 1.00E 00 0.00E 01 8.00E 00 SSW 0.00E 01 0.00E 01 1.00E 00 7.00E 00 3.00E 00 1.00t 00 1.20E 01 Sk 0.00E-01 3. DOE 00 2.00E 00 5.00E CO 0.00E-01 0.000 01 1.00E 01 WSW 0.00E 01 2. DOE 00 3.00E 00 5.00E 00 0.00E 01 0.00E 01 1.60E 01 W 1.00E 00 4.00E 00 0.00E 01 3.00E 09 0.00E 01 0.00E 01 8.00E U0 kWW 0.00E 01 2.00E 00 1.00E 00 1.00E 00 0.00E-01 0.00E-01 4.00E 09 hw 0.00E 01 1.00E 00 4.00E 00 0.00E 01 0.00E 01 0.00F-01 5.00E 00 WWV 0.00E 01 2.00E 00 1.00E 00 0.00E 01 0.00E-01 0.00E 01 1100L_Qg TCTAL 1.10E 01 3.50E 01 4.10E 01 5.30E 01 5.00E 00 1.00E 00 1.46E 02 PERIOOS OF CALM (HOURS): 0.00E-01 49
2 s
SECTION 6 DOSE MEASUREMENTS AND ASSESSMENTS at 4-
TABLE 13 MAXIMUM
- OFFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUDLIC Data Period: January 1, 1991 - June 30, 1991 DOSE **
Source _first Ouarter Second Ouarter A. Waterborne Effluents (mrem) Organ 7.33E-03 1 7.10E-04 1 Total Body 6.96E-04 2 7.68E-05 2 B. Airborne Effluents
- 1. Iodines and Particulates Organ 7.41E-05 3 2.84E-05 4 (mrem) __
Total Body 6.36E-05 5 2.81E-05 0
- 2. Noble Gases: Gamma 0.00E+00 0.00E+00 (mrad)
Beta 0.00E+00 0.00E+00 7 7 C. Direct Radiation (mrem) N/A N/A THERE ARE NO OTHER URANIUM FUEL CYCLE FACILITIES WITHIN 8 KM OF CPS
- " Maximum" means the largest fraction of the corresponding Appendix I dose design objective.
- The numbered footnotes on the following page briefly explain how each maximum dose was calculated, including the organ and predominant pathway (s).
50
. = . _ - . . _- .. - ._ = . .~ -, - . . _ _ _
Footnotes for Table 13
- 1. Dose to the aoult gastrointestinal tract and lower large intestine (GI-LLI) by the fish pathway. Calculated using methodology contained in the CPS Offsite Dose calculation Manual (ODCM).
- 2. Dose to the adult total body by the fish pathway. Calculated using methodology contained in the CPS ODCM.
- 3. Dose to the infant skin via the inhalation, cow milk, and ground-plane pathways. Calculated at 4.5 miles Southeast using methodology contained in the CPS ODCM.
- 4. Dose to the infant lung via the inhalation, cow milk and ground-plane pathways. Calculated at 4.5 miles North using methodology contained in the CPS ODCM.
- 5. Dose to the infant total body via the inhalation, cow milk and ground-plane pathways. Calculated at 4.5 miles Southeast using methodology contained in the CPS ODCM.
- 6. Dose to the infant total body via the inhalation, cow milk and ground-plane pathways. Calculated at 4.5 miles North using methodology contained in the CPS ODCM.
- 7. In accordance with CPS ODCM section 7.2, dose caused by direct radiation from CPS for this reporting period will be reported in the July through December 1991 Semiannual Radioactive Effluent Release Report.
4 51 5 _.
. - _ . . - . _ . - ~
DOSES TO MEMRERS OF THE PUBLIC WITHIN THE BITE DOUNDARX CPS Offsite Dose Calculation Manual section 7.? requires that the Semiannual Radioactive Effluent Release Report include an assessment of the radiation doses from radioactive liquids and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents shall be used for determining the gaseous pathway doses.
Within the CPS site boundary there are seven areas which are open to members of the public as identified by CPS ODCM Table 3.4-4 (see Figure 8):
A road at 0.495 kilometers (0.3 miles) in the SE sector
- Agricultural actuage at 1.372 kilometers (0.9 miles) in the SSW sector A portion of Clinton Lake at 0.335 kilometers (0.2 miles) in the NW sector The Department of Conservation Recreation Area at 1.287 kilometers (0.8 miles) in the ESE sector A residence at 1.219 kilometers (0.8 miles) in the SW sector A residence at 2.414 kilometers (1.5 miles) in the WSF sector A residence at 2.736 kilometers (1.7 miles) la the SSE sector At all of the above locations, the plume, inhalation and ground-plane exposure pathways are used for dose calculations. No other exposure pathways were identified by the 1990 Annual Land Use Census. All dose calculations were performed using the methodology contained in the CPS ODCM.
l 52
FIGURE O AREA 8 WITHIN THE CPS SITE BOUNDARY OPEN TO MEMBERS OF THE PUBLIC "' 2 "
CLINTON e , f S s WMAROA a
,,,,, WAPELLA
. ...... . . ....... . m .. .. . .
(e. ,
e . . ..... ... . m .. .. ,,. ....,..., ......
. .......... .,c........... .......... ....
, ......... ,.,u.. .. ... ............... ......
8 '
8 1 6 5
~
- " . 5 $.
- E e --
I d
- 6 % -
m NC.P.5.
/ '
wAcon co.
PIATT CO.
WELDON R re h,, ,
- "'1 C I S C O
%,r 'o.
.c Co.
.: s FARMER .. 4 DELANhIb ,, .
CHAMPAIGN 74 53
.. . - . . - . - - . . . - - . - - - . . . . -.. . . ~ . . .. -
. _ - . . . - . _ . _ . _ . . . - . . . _ _ . _ - . . . . . . _ . _ < ~ _ _ _ _ . _ _ . _ . . .
_ . _ . - ~ . . . _ - - - . . _
TABLE 14 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING-USE OF THE ROAD IN THE SOUTHEAST SECTOR WITHIN THE-CPS SITE BOUNDARY
-Data Period: January 1, 1991 - June 30, 1991 Exposure Pathway QIggng Dose (mromi plume
- total body 0.00E+00 skin 0.00E+00 ground plane
- total body 7.15E-05 skin 8.42E-05 inhalation; four highest organ doses:
teen lung 3.13E-06 child lung 2'.56E-06 adult lung 2.25E-06 infant lung 1.61E-06
- Doses via these pathways are not dependent upon age-group.
54
h TABLE 15 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE AGRICULTURAL ACREAGE IN THE 80UTH-SOUTKWEST SECTOR WITHIN THE CPS SITE BOUNDARY
-Data Period: .7anuary 1,-1991 - June 30, 1991
-Exposure Pathway Oraans Dose (mrem) plume
- total. body 0.00E+00 skin 0.00E+00 ground plane
- total body 4.21E-05 skin 4.95E-05 inhalation; four highest organ doses:
teen lung 1.88E-06 child lung 1.58E-06 adult lung 1.55E-06 infant lung 9.70E-07 j i
- Doses via these pathways are not dependent upon age-group.
.I 55
. . . - - .,. , . - . . - - . . . , . - . . - . , . - , - . . -____________--_-_a
i TABLE 16 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF CLINTON LAKE IN THE NORTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: January 1, 1991 - June 30, 1991 Exposure Pathway Orcans Dose (mrpRl plume
- total body 0.00E+00 skin 0.00E+00 ground plane
- total body 5.75E-05 skin 6.76E-05 inhalation; four highest organ doses:
teen lung 9.05E-06 adult lung 8.21E-06 child lung 7.81E-06 teen GI-LLI 6.64E-06
- Doses via these pathways are not dependent upon age-group.
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l 56 1
TABLE 17 CA7,CULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE DEPARTMENT OF CONSERVATION RECREATION AREA IN THE EAST-SOUTHEAST SECTOR WITHIN THE CPS SITE DOUNDARY Data Period: January 1, 1991 - June 30, 1991 Exposure Pathway Orcans Dose (mrem) plume
- total body 0.00E+00 skin 0.00E+00 ground plane
- total body 8.01E-06 skin 9.43E-06 inhalation; four highest organ doses:
teen lung 7.32E-07 adult lung 6.65E-07 child lung 6.32E-07 teen GI-LLI S.38E-07
- Doses via these pathways are not dependent upon age-group.
57
TABLE 18 CALCULATED DOSES FOR THE RECIDENTS IN THE SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: January 1, 1991 - June 30, 1991 Exoosure Pathway Orcans Dose (mreml plume
- total body 0.00E+00 skin 0.00E+00 ground plane
- total body 4.25E-04 skin 5.00E-04 inhalation; four highest organ doses teen l'Ing 2.18E-05 adult lung 1.90E-05 child lung 1.87E-05 teen GI-LLI 1.36E-05
- Doses via these pathways are not dependent upon age-group.
1 i
l l
58
. . _ . . . . _-.- _ _ _ . . . _ _ ~ _ _ _ . . _ . - - . . . . . . _ . - _ . . . . _ . _ . . _ .
TABLE 19 CALCULATED DOSES FOR.THE RESIDENTS IN THE WEST-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY
-Data Period: January 1, 1991 - June 30, 1991 Exoosure Pathway Oraans Dose (mrem) plume
- total body 0.00E+00 skin 0.00E+00 ground plane'* total body 1.83E-04 '
skin 2.16E-04 inhalation; four highest organ doses:
teen lung 5.24E-06 child-lung 4.43E-06 adult lung- 4.37E-06 infant lung 2.70E-06 E'
- - Doses via.these pathways are not dependent upon age-group.
4 59 u_ . - - . _ . . . - . . . - - . ~ . - . , . - , , ,
TABLE 20 CALCULATED DOSES FOR THE RESIDENTS IN THE SOUTH-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: January 1, 1991 - June 30, 1991 Exposure Pathway Oraans Dose (mrem) plume
- total body 0.00E+00 skin 0.00E+00 ground plane
- total body 1.36E-04 skin 1.60E-04 inhalation; four highest organ doses:
teen lung 3.23E-06 child lung 2.65E-06 adult lung 2.37E-06 infant lung 1.67E-06
- Doses via these pathways are not dependent upon age-group, 60
4 -A-N2 wWM, + u k Jnb J-+--man -'> u4 A_ 4 ,
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- A-a w - s- - - A L- u n.L ~ w,,,. s,, u -
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SECTION 7 CHANGES TO THE OFFSITE DOSE-CALCULATION MANUAL s
i 3
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l l-
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL I i
j In accordance with CPS Technical Specification 6.14 and ODCM section 7.2, changes to the CPS ODCM shall be reported as a J part of or concurrent with the Semiannual Radioactive =
Effluent Release Report.
Revision 7 to the CPS ODCM was reviewed and approved by the CPS Facility Review Group on February 7, 1991, and approved by the CPS Power Plant Manager on February 8, 1991. A summary of revision is provided on the following page. The CPS ODCM revision 7 is submitted concurrent with this ;
report.
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ODCM Revision 7 S_UEMARY OF REVIS1QH Page xi Revised List of Effective pages to reflect revision 7 affected pages.
xii Revised List of Effective Pages to reflect revision 7 affected pages.
2-31 On Remedial Requirement 3 added clarification that all flows diverted from Plant Service Water must be taken into account when Plant Service Water flow rate is being estimated when performing liquid radwaste discharges.
3-5 Changed the routine sampling frequency for grab samples for principal gamma emitters and H-3 to weekly instead of monthly on the station HVAC Exhaust and the Standby Gas Treatment System Exhaust.
5-7 Added sampling location CL-15 and removed sampling location CL-94 from the airborne radiciodine and particulates locations.
5-12 Corrected a typographical error.
5-20, Corrected typographical errors.
21,22 5-28, Added sampling locations not previously shown on 30,31 maps which show REMP sampling locations.
9-4 Corrected typographical errors.
62
,e ma+r- 5 A J - J&asa a m--m-- A- - ~r 4 - A 4-"4--m*--AL SECTION 8 ODCM OPERATIONAL REQUIREMENT REPORTS 1
I
. _ _ _ _ _ _ _ _ _ _ _ . _._._--___m . _._ _ _.__._ _ _ __ _ _ _ . _ . - _ . __ __
ODCM OPERATION REOUIREMENT REPORTS In accordance with ODCM sections 2.7.1 and 3.9.2 inoperable radioactive liquid and gaseous effluent monitoring instrumentation channels remaining in an inoperable condition for greater than 30 days shall be reported in the Semiannual Radioactive Effluent Release Report.
During the January 1, 1991 - June 30, 1991, reporting period, two inoperability conditions require reporting. Two additional inoperability conditions which were restored in July and August 1991 are also being reported in lieu of waiting until the July - December 1991 Semiannual Radioactive Effluent Release Report. These conditions are described below.
One additional inoperability condition not required to be included in the Semiannual Radioactive Effluent Release Report is being included in this section for informational purposes. This condition is described following the four cases referenced above.
C.ase 1 Information:
Operability Requirement: ODCM Table 2.7-1, item 1.a Date Entered: 7-5-90 at 1130 Date Restored: As of 6-30-91, the instrument had not been restored to an operable condition.
Explanation:
Information pertinent to the cause of ORIX-PR040, Liquid Radwaste Discharge Process Radiation Mointor (PRM), inoperability can be found in the July 1, 1990 -
December 31, 1990, Semiannual Radioactive Effluent Release Report.
Troubleshooting and electrical alignment followed by monitor calibration is expected to begin in early August. Following this effort, the monitor will be returned to an operable status.
The primary reason for the extended inoperability period on this monitor was the continued effort to troubleshoot and repair other process radiation monitors which are required to be in service continually or on a frequent basis.
63
Case 2 Information:
Operability Requirement: ODCM Table 2.7-1, item 2.c Date Entered: 11-10-90 at 0000 Date Restored: 7-17-91 at 1740 Explanation:
Information pertinent to the cause of 1RIX-PR004, Fuel Pool Heat Exchanger Service Water PRM, inoperability can be found in the July 1, 1990 - December 31, 1990, Semiannual Radioactive Effluent Release Report.
High radiation background levels in the area of the monitor hindered the calibration process on this monitor. The identification and correction of this problem was the primary reason for the delay in returning the monitor to operacility.
On June 6, 1991, temporary shielding was erected which entirely surrounded 1RIX-PR004. This effort sufficiently reduced background to acceptable levels.
Following calibration and the performance of a Channel Functional Test, the monitor was restored to operability on July 17, 1991.
. Case 3 Information:
Operability Requirement: ODCM Table 2.7-1, item 2.b Date Entered: 6-4-91 at 0600 Date Restored: 8-3-91 at 1955 l
l- Explanation:
1RIX-PR030, Shutdown Servive Water Effluent PRM calibration lapsed on the date referenced above. Due to primary calibration being performed on this monitor, l
operability was not restored within 30 days.
l Following the satisfactory completion of primary calibration, the monitor was returned to service.
l 64 l
. -- - . . . = - . . - .
Case 4 Information:
Operability Requirement: ODCM Table 2.7-1, item 2.b Date Entered: 6-22-91 at 1420 Date Restored: 7-30-91 at 2130 Explanation:
1RIX-PR039, Shutdown Servive Water Effluent PRM calibration lapsed on 6-22-91. Due to ongoing primary calibration efforts on 1RIX-PR038 referenced in Case 3 above, resources were not available to return the monitor to service within 30 days.
Following satisfactory calibration the monitor was returned to service.
Case 5 Information:
Operability Requirement: ODCM Table 3.9.1-1, item 2.a Date Entered: 4-3-91 at 2000 Date Restored: 4-12-91 at 1320 Explanation:
On April 3, 1991, Illinois Power Engineering identified that the calibration constants determined during previous calibrations on the Offgas Post-Treatment PRMs, 1RIX-PR035 and 1RIX-PR041, High Range Noble Gas Detector had not been correctly established due to an error contained in the setpoint methodology for these monitors. The non-conservative setpoint that had been established for these monitors means that the monitors were inoperable to the extent that they would have not actuated an clarm or effected automatic isolation of the offgas sysytem at the intended setpoint in the event of a fuel leak or fuel damage or a high radioactivity condition in the offgas system. This condition had existed since initial operation of the facility. However, the condition did not result in the potential for an unmonitored release since the offgas system discharges.through the HVAC common stack which has its own monitors (and alarms) and the post-traetment monitors themselves continued to monitor, indicate and record radioactivity levels in the pcst-treatment portion of the offgas system. Manual isolation of the offgas system was also still possible in the event of a high radioactivity condition which would cause the HVAC common stack alarms to actuate.
In addition, it should be noted that the offgas 65
pre-treatment monitor was also available to monitor and indicate offgas radioactivity levels at the pre-treatment point.
Upon determination that the non-conservative setpoint condition existed, the monitors were declared inoperable, and per the Remedial Requirement specified in ODCM Table 3.9.1-1, samples were periodically taken and analyzed until the monitors were restored to operable status. In addition, a plant condition report was initiated to document and investigate the cause of the condition. The setpoint methodology was subsequently corrected, and the monitors were returned to operable status on April 12, 1991.
66
g4,_.. _ ,-ssa--_-.4.,,' a s. .
A Aa .A.- . >_a4u. age u.__.p._.s_..m 4.s2.2.J h J._ .,.s.p. .m . u.Lawa s 4 . .,A. s._MA.iJ.A...ha.m.. 4a... J J w 4 A m_e 4.A.__1w a & A.
j SECTION 9 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS l
MAJ.OR C_H2LNGES TO RADIOACTIVE WASTE TRFATHENT SYSTEMS In accordance with the CPS ODCM section 7.2, licenc_a-initiated major changes to the liquid, gaseous or solid radioactive waste treatment systems shall be reported in the Semiannual Radioactive Effluent Release Report. No major changes to the Waste Treatment Systems were reviewed and approved during this reporting period.
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- - - - - - - - - 1
4 4 W g-4 .a
-- e.~< % - 4 SECTION 10 NEW LOCATIONS FOR DOSE CALCULATION AND/OR ENVIRONMENTAL MONITORING L
I t l I
. -cs, . ._
NEW LOCATIONS FOR DOSE CALCULATION AND/OR ENVIRONMENTAL MONITORING In accordance with CPS ODCM section 7.2, new locations for dose calculations and/or environmental monitoring identified by the Annual Land Use Census shall be repceted in the Semiannual Radioactive Effluent Release Report. l The 1991 Annual Land Use Census began on July 29, 1991, and as of August 29, 1991, had not be completed. Results of the j 1991 Annual Land Use Census will be provided in the '
Semiannual Radioactive Effluent Release Report to be submitted af ter January 1, 1992.
l l
68
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3 9O- EC-~!O N l