U-601799, Semiannual Radioactive Effluent Release Rept Jul-Dec 1990
| ML20066K554 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/31/1990 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| U-601799, NUDOCS 9102270254 | |
| Download: ML20066K554 (74) | |
Text
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U.f.01799 I L*J0 91 ( 02 20; . it ILLINDIS POWER um CLINTON ICWI:R M ATION. P O ItoX 676. CLINTON. ILL INDIS 01727 007h. *ll'i.lTilONL (217110kbkhi - - . .
iebruary 20, 1991 Docket No. 50 461 Document Control Desk Nuclear Regulatory Commist. ion Washington, D.C. 20555 Subj ec t: Clinton Power Station Screiennual Rndionetiv L Lif.lutnt Ptli.Att_EitEIl
Dear Sir:
Attached is the Semiannual Radioactive Effluent Release Report for Clinton Power Station (CPS) for the period of July 1,1990 December 31, 1990. This submittal in provided in accordance with the requirements of section 6.9.1.7 of the CPS Technical Specif1 cations..
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l July 1, 1990 - December 31, 1990 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE CLINTON POWER STATION e 1
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I TABLE OF CONTENTE SECTION' EAQI
- 1. Executive Summary . . . . . . . . . . . . . . . . 5
- 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 . . . . . . . . 54
- 7. Changes to the Offsite Dose Calculation Manual and the Solid Waste Process Control Program . . . . . . . . . . . . . . . . . . . . . 65
- 8. Limiting Condition for Operhtion Reports and ODCM Operational Requirements . . . . . . . . . . 66
- 9. Major Changes to Radioactive Waste Treatment Systems . . . . . . . . . . . . . . . . . . . . . 71 ,
- 10. New Locations for Dose Calculation and/or
. Environmental Monitoring. . . . . . . . . . . . 72 1
v' . T LIST OF__TABLER PAGE Table 1: Airborne Effluents - Summation of All Releases . . . . . .. . . . . . . . . . . . 22
-Table 2: Airborne Effluents . . . . . . . . . . . . . 23 Table 3: Rhdioactive Gaseous Waste LLD Values . . . . 25 Table ~4: Waterborne Effluents - Summation of All Releases . . . . ...... . . .. . . . . 27 Table-5: Waterborne Effluents . . . . . . . . . . . . 28 Table 6: Radioactive Liquid Waste LLD Values. . . . . 29 Table 7 Solid-Waste and Irradiated Fuel Shipments. . 32 Table 81 Corrections to Data Reported-in' Previous
- Semi-Annual Reports. . . . . . . . . . . . . 34 Table 91 -Effluent. Data Not Available for Previous Semiannual: Report.~. . . . . . . . . . . . . 36 Table:10:sMeteorological Data Availability . . . .
. . 38 Table 118 Classification of Atmospheric Stability. . . 42 Table.128 Joint Wind Frequency Distribution by Stability Class. ... . . . . . . . . . . . . 43 Table 13:: Annual Average Relative concentrations . . . 50 Table =141 Maximum offsite Doses and Dose Commitments ~to Members of the Public . ... . 54 Table 15: Calculated Doses to1 Members of the-Public During Use of the Road in the Southeast
-Sector within the CPS Sit 6 Boundary. . . ._ . 58 Table 16: 1 Calculated' Doses to Members of the Public During Use-of the Agricultural Acreage in the South-Southwest Sector within.the CPS Site Boundary; . ............ . . 59
, Table 17:' Calculated Doses to Members of the Public During Use of Clinton Lake in the Northwest Sector within the CPS Sito Boundary. . . . . 60 l
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EAQI Table 18: 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 . . ............ . . . . 61 Table 19: Calculated Doses for the Residents in the Southwest Sector within the CPS Site Boundary . ............. . . . . 62 Table 20 Calculated Doses for the Residents in the West-Southwest Sector within the CPS Site Boundary . . . . . . . . . . .. . . . . . . 63 Table 21 Calculated Doses for the Residents in the south-Southeast Sector within the CPS Site Boundary . ...... . . . . . . . . . . . 64 1
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LIST OF,_ FIGURES
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l Figure 1: CPS Airborne Effluent Release Points. . . . . 7 ,
Figure 2: CPS Waterborne Effluents Release Pathway. . . 8 Figure 3: Effluent Exposure Pathways. . . . . . . . . . 13 Figure 4: CPS 1990 Monthly Liquid Radwaste Discharge Total . . . . . . . . . . . . . . . 21 Figure St CPS Wind Rose: 10-meter. . . . . . . . . . . 39 Figure 6: CPS Wind Roset 60-meter. . . . . . . . . . . 40 Figure 7: Clinton Power Station Distribution of Atmospheric Stability class . . . . . . . . . 41 :
Figure 8: Areas Within the CPS Site Boundary open to Members of the Public. . . . . . . . . . . 57 I
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EXKGRTIEE MiMARY i
The Semiannual Radioactivo Effluent Release Report is a detailed description of all radioactivo releases (both gaseous and liquid) ,
from the Clinton Power Station (CPS) and the resulting radiation dosos for the period from July 1 through December 31, 1990. This report includes a detailed meteorological section which provides the weather history of tho area during this period. This information is used to calculate the doso 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 offsito 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 Doso Calculation Manual (ODCM) and Solid Waste Process Control Program (PCP), and exceptions to the CPS offluent monitoring program which must be reported por ODCM operation 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
. radioactivo material in offluent releases to unrestricted areas is kept As Low As Beaconably behievablo ( A1 ARA) . To assure those critoria are mot, the NRC has established limits governing the release of radioactivity in offlucnts.
CPS was operated in complianco with establinhed limits during this report period. The maximum radiation dono delivered to the inhabitants of the area surrounding CPS, duo to radioactivity released from the station, was very small. The radiation doso to people in-the vicinity of CPS was calculated for a continuous gaseous roloaso by using the concentration of radioactivo material and the weather conditions at the timo of the release.
Radiation dose to the public was also calculated for liquid batch releases using the concentration of radioactivo material and the nonradioactive dilution flow at the time of the release. Thoso dosos were only a small fraction of the limit for the most exposed member of the public.
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INTRODUCTLQH ,
Clinton Power Station is located in Harp Township, DeWitt County approximately six miles cast of the city of Clinton in cast-central Illinois. Clinton Power Station is a 985 megawatt gross electrical power output boiling water reactor. The reactor and generating units woro supplied by General Electric, Sargent and Lundy Engincors served as architect-engineer, and Baldwin Associates was the constructor.
Construction of CPS began in the mid 1970's. Puol load began in September of 1986 with initial criticality achieved on Pobruary 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 offluent release points to the environments the common Station Heating,
. Ventilating, and Air conditioning (HVAC) Stack and the Standby Gas Treatment System (SGTS) Vent (see Figure 1). Each roloase point is continuously monitored and a program of periodic j sampling and analysis is conducted as specified in the ODCM.
Liquid effluents from CPS are released in batch modo and are sampled and analyzed prior to release. Liquid offluents, variable from 10-60 gallons por minuto (GPM) or 50-300 GPM, combine with Plant Service Water flow (minimum of approximately .
5000 GPM) and Plant Circulating Water flow (0-567,000 GPM) in the Sealvell prior to entering the 3.4 mile discharge fiume to Lake Clinton (see Figure 2).
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CPS AIRBORNE EFFLUENT RELEASE POINTS I Figure 1 .
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L - -_ Y GASEOUS EFFLUENT RELEASE POINT CHARACTERISTICS HVAC EXHAUST STACK SGTS EXHAUST STACK f
RELEASE POINT HUGHT (m) 61 61 Bull. DING HUGHT(m) 58 58-HELEASE PotNT CEOMETRY DUCT. PIPE RELEASE POINT AREA (m8) 11.15 0.15 '
j- RELEASE PotNT DtAMETER (m) 3.77' O.44 ANNUAL AVERAGE FLOW RATE (fr 8/mln) 237,000 4000 VERTICAL EXIT VELOCITY (m/sec) 10.02 12.49 7
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CPS WATERBORNE EFFLUENTS RELEASE PATHWN/ l Figure 2 i I
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PLANT SERVICE WATER
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- h , RADIATION MONITOR ALARM /TRP SETPowf CALCULATED BASED ON EACH 8ATCHISOTOPIC ANALYSIS AND atunON ROW
>4 ISOLATION VALVE . i TERMNATE8 RELEASE CH >#GH RADIADON, FOOH RELEASE FtDW RATE. OR t0W @ COMPOSITE SAMPLER 4 COLLECTS APPROXIMATELY 20 ml -l EvtnY eo unufts rnou mE asCmnaE RUME FOR MONTHLY ANALYSIS
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C LAKE -i 3LANT CIRCULATING- CLINTON iWATER 4 (0-567,000 GPM) DISCHARGE FLUME 3.4 MILES .;
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l l Reaulatory Limits The NRC requires nuclear power plants to be designed, constructed and operated in such a way that the radioer.tivity in effluent j releases to unrestricted areas is kept ALAMA. To assure these criteria are met, each 11 cense authorizin's nuclear reactor operation includes Radiological Effluent Technical Specifications ~
i (RETS) governing the release of radioactive effluents (code of-Federal Regulations, Title 10, Part 50, Appendix I). The RETS, designate the limits for release of affluents, as well as the
- j. limits for doses to the general public from the release of i radioactive liquids and gases. Keeping releases within these operating limits demonstrates that the ALARA principle is being
- met. _j The dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas is limited tot t
Less than or equal to 3 mrem per year to the total I body. 1
-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-tot 4 -
Less than or equal to 10 mrad per year for gamma radiation.
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-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:
i Less than or equal to 15 mram per year toLany 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 por year to the total body. j Less than or equal to 75 mrem per year to the thyroid.
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-and-Less than or equal to 25 arem per year to any other organ.
See Section 3 for more information on regulatory limits. {
Processins and Monitorina ;
i 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 i environmental sampling and analysis programs. In-plant radiation. 3 monitoring systems are used to provide a continuous indication of 4 -radioactivity and are also used to. collect particulate and F radioiodine samples. . These samples are analyzed in a laboratory .
to identify the specifis concentration of radionuclides being released. Sampling knd 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 purpose is the regulatory >
requirement to' trend,and' assess radiation exposure rates and 7 radioactivity concentrations that may-contribute to human--
radiation exposure. The program consists of.two phases, preoperational and' operational. During the preoperational phase of theiprogram, the baseline for the local radiation environment >
wan established. The operational phase of the program includos ithe objective of making confirmatory measurements to verifyfthat. i
< the in-plant controls for the release-of radioactive material are functioning as designed. Assessment of the operational impact of L CPS'on the environment is based on data. collected since the j freactor started. l l
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Exoosure Pathwav_s 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 informa' tion 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 rad'7nuclides enter the body through inhalation and ingestion and seek different organs depending on the nuclide.
For example, radioactive iodine selectively concentrates in the thyroid, radioactive cesium collects in muscle and liver tissue, and radioactive strontium in mineralized bone.
The 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 of radioactive material and the weather conditions present at the time of the release. The dose is calculated in all sixteen.
. geographical sectors currounding CPS and takes into account the location of the nearest residents, vegetable gardens producing 11 i=
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broad leaf-vegetables, dairy and meat animals in all sectors. l 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 breathos in a year.
See Tabins 14-21 of Section 6 for more detailed information'on dose to the public.
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j RELEASES DILUTED BY ATMOSPHERE .
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/ SaOREUNe EXPOSURE 4
QPaeoui Effluents Gaseous effluent radioactivity released from CPS is classified into two categories, 1) noble gas, and 2) iodine-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.
Licuid Effluents 4
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 Waste Shloments 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 comply.ing 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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I I. REGULATORY LIMITS A. Gaseous Effluents
- 1. In accordance with Title 10 of the Codo of Fedoral Regulations (CFR), Part 20, the maximum permissible concentrations for gaseous offluents shall not execed the values given in 10CTR20, Appendix B, Tablo II, Column 1. To ensure thoco concentrations are not exceeded, doso rates due to radioactive materials released in gaseous effluents from the sito to araas at and beyond the site boundary shall be limited to the followings
- a. Hoble gases - Loss that: or equal to 500 mrem / year to the total body.
- Less than or equal to 3000 mrem / year to the skin.
- b. Iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than eight days:
- Loss than or equal to 1500 mrem / year to any organ.
- 2. In accordance with Title 10 of the Code of redoral Regulations, Part 50, Appendix I, air doso due to noble gases released in gaseous effluents to areas at and beyond the sito boundary shall be limited to the following
- n. Loss than or equal to 5 mrad for gamma radiation and loss than or equal to 10 mrad for beta radiation during any calendar quarter.
- b. Loss than or equal to 10 mrad for gamma radiation End 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, iodino-133, tritium and all radionuclidos in particulate form with half-lives greater than eight days) in 15
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gaseous effluents ruleased 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 concer,tcation of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Tjtle 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 liquid effluents released to unrestricted areas shall be limited tot
- a. Less than or equal to 1.5 mrem to the total body and loss 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 mrom to any organ during any calendar year.
II. MAXIMUM PERMISSIBLE CONCENTRATION A. Gaseous
- 1. The maximum permissible concentrations (MPC) for gaseous offluents 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 1?mit the release rate of effluents such that discharges of gaseous radioactive material will L
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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, iodino-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.
B. 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 4
as described in Regulatory Guide 1.21, " Measuring, 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 a rplicable.
IV. MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY A. Fission and Activation Gases
- 1. Gas samples are collected monthly and are counted on a high purity germanium detector (HPGe) for 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 domineralized water. The collected samples are distilled and analyzed by liquid scintillation. The tritium released was calculated for each release point from the measured triti.um concentration, the volusoe of the sample, the tritium collection officiency, and the stack exhaust flow rates.
B. Iodines Iodine is continuously collected on a charcoal cartridge filter via an isokinetic sampling 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 reletse point are averaged for the duration of the sampling period and these results, along with isotopic concentrations, are used to determine tot.il. activity released during the time period in question.
C. particulates Particulates are continuously collected on.a filter paper via an isokinetic sampling assembly on ecch 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 r , ---s
1 l
D. Liquid Effluento Each tank of liquid radwaste is sampled and analyzed for principal gamma emitters prior to release. Each sampic tank is recirculated for a sufficient amount of tjmo 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-55, 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 th" sc. val activity released for these isotopes.
V. BATCH RELEASES A. Liquid 3rd Otr 90 .itlL91r 90
- 1. Number of batch releases: 31 4
- 2. Total time period for batch releases: 2,794 372 min.
- 3. Maximum time period for batch retoase: 116 95 min.
- 4. Average time period for batch release: 90.1 93 min.
- 5. Minimura time period for batch release: 79 90 min.
- 6. Average stream flow during periodo r*
releass 8.55E+04 5.62E+04 liters per minute
- 7. Total waste volume: 2.78E+06 3.47E+05 liters
- 8. Total dilution volume: 2.39E+08 2.09E+07 liters 19 .
l
. - _ . - .. - . - - .. . ,,~ .. .~ - - - . .
x ^'
i.v t, ,
B.- . Gaseous 3rd Otr 9,Q 4th Otr 90
- 1. - Number of-batch releases: 0 0 -
- 2. Total 1 time period for
-batch re'. eases: N/A N/A
- 3. Maximem time period for s -batch--release: N/A N/A
- 4. Avoraga time i period tor-batch release: N/A N/A
- 5. Minimum time
$ period for-katch release: N/A N/A l VI. DESCRIPTI0tf OF-ERROR ESTIMATES A. Gasocus arrd LiTuid Effluents'
-Estimates of measurement and analytical error.for gaseoua:and liquid effluents are calculated as follows:
E T = ((E1 )2 + (E2) + ..(En) 3 where, ET = total percent error, E 1 ....En'" percent error due to eclibration standards,Llaboratory analysis,
- . instruments, sample flow, etc.
7II.---CHANGE ~IN EXCESS. WATER TANK VOLUME
.; 'On January 28, 199i the.CPSTNuclear Station Engineering .
P -Department-(NSED) revisedsthe volumeVcalculations for the, Excess;WatersTanks,-OWE 01TA and-OWE 0lT3,0 based on CPS- 1 Vf ' operating exp'rience.- :These-tanks;are1 utilized when CPS--.
/; dischargeslliquid ' effluents to Clinton Lake.; The corrected q~
lf 100% volumes for_each. tank are-26,103Lgallons.- The. volume h}D
- -utilized in calculations reported inithis document was
- 25,670 gallons.-. This= change in tankLvolume reprerents anL a
]F ,
sp approximate 1.6%; differential in:valucar(1.o. total liquid- J f', -volume.and curies-discharged and thebdosetto the maximum-h . receptor): . reported. Since'the errorJassociated with.the ,
y calibration of. tank level. instrumentation 11s' estimated to?be' a f aboutc5.5%,Jit is believed that the= volume calculated
$< Jdifferential of 1.6% is well within the bounds of error for:
- he instrument. Therefore, the impact ?of:this circumstance ~ t 10 lj- :is thought to-be insignificant and,does;not warrant-any-y, =
changes to reported values.
l, h
1 4
/
20 m . .- . ._ _ __ ______ _ _ _ ,_ _ ._
FIGURE 4 -
CLI.NTON- POWER STATION j 1990 MONTHLY:.LlQUID RADWASTE DISCHARGE TOTAL 1000-847280-800 -
g 600 -
Z 4 U '
gi 400 -
307140 200 -
.0 0. G 0 0
8'8U1240 0 91840 0
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC TOTAL
.I I
N S -
_ N L
_ U -
s s .
m J S 30SA_ JATA i I
"j
,s-t- i v_, .
.. _ . m . _ _ . _ . . - .. _ . . . - - .__. _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ . _ _ . . . -
'k t
i
. TABLE 1 i
AIRBORNE EFFLUENTS - SUMMATION OF ALL.TTLEASES
' Data-Period: ; July 1, 1990 - December '; 2, 1990 Est Continuous Mode Totall 3 Nuclide-Category Unit 3rd Quarter 4th Quarter Error, %.
A. Fission & Activation
- Gases-
- 1. Total = Release 2 Ci 0.00E+00 0.00E+00 28 ;
- 2.' Average-Release Rate for. Period uCi/sec 0.00E+00 0.00E+00
- 3. Percent of-Applicable Limit % 0.00E+00 0~00E+00 B'. Iodine-131' *
- 1. Total Release Ci 4.13E-05 1.18E 33 !~
2.-Average: Release'
- Rate.for Period uCi/sec 5.24E-06 1.50E-06
-3. Percent =of-
- Applicable Limit % 7.40E-02 2.12E-02 ,
C. Particulates: '
1.~Particulates Released 27 with Half-lives >B Days Ci- 4.50E-03 9.16E-04*-
'2.. Average Releasm ~
Rate.for Period uCi/sec 5.71E-04 1.16E-04* (
- 3. Percent of
. Applicable Limit % 1.13E-03. 1.63E-03* q
- 4. . Gross' Alpha-Activity 1 Released Ci~ 3.68E-06 1.51E-06 D. Tritium' --
I
- 1.-TotalTRelease - Ci 4.12E-01 4.05E-01 105
- 2. Average Release
' Rate-for' Period 'uC1/sec 5.22E-02 5.14E-02
- 3. Percent"of' Applicable Limiti % '2.60E-05 2.56E-05
- 1. It1should be.noted that the-lower the actual-sample activityL H -is:withfrespect to background activity, the greater the p- l counting error. Large errorsJare reported for.the various componentslof CPS gaseous effluents-because of consistentlyf
~
low sample activity. i e
2 . Notation .An entry'of 0.00E+00'does;noterepresent the 1 absence'of a radionuclide but indicates that the concentration . of: the nuclide. was below the Lower Limit of 00t;0 Lion ' (LLD) value listed in Table 3. ,
- Reported-values include Sr-89 values based on third quarter 1990. samples analyses.and fourth qucrter 1990 ventilation exhaust rates.
22
- ,g 75 p -r +- . , . . 9 s
TABLE 2 AIRBORNE EFFLUENTS (Curies)3 Data Period: July 1, 1990 - December 31, 1990 Continuous Mode Nuclide Third Quarter Fourth Quarter A. Gases Kr-85 Kr*85m '
Kr 87 Kr-88 Xo-133 Xe-135 Xe-135m Xe-138 others:
Ar-41 Total 0.00E+00 0.00E+00 B.= Iodines I-131 4.'7E-05 1.18E-05 I-132 0.J0E+00 0.00E+00 I-133 4.80E-05 4.88E-06 I-134 0.00E+00 0.00E&OO I-135 0.00E+00 0.00E+00 Total 8.93E-05 1.66E-05 C.'Particulates
-w/ Half-lives
>8 Days Sr-89 2.12E-05 1.93E-05*
Sr-90 0.00E+00 0.00E+00*
Cs-134 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 Ba-140 0.00E+00 -0.00E+00 3 Notation: An entry of 0.00E+00 dces not represent the absence of a radionuclide but in'licates that.the concentration of the nuclide was below the LLD value listed in Table 3.
- Reported values are estimated based on third quarter 1990 composite analyses and fourth quarter 1990 ventilation exhaust rates.
1 i
23 l ~
~
. d
, f 4: ./
t TABLE 2 (Cont'd) ,
. . 1 AIRBORNE EFFLUENTS _(Curies)3 Data Period:- July.1, 1990 - December 31,:193 -
ci Continuous-Mode.- 2 Nuclide- Third Quarter Fourth Quarter !
~
Others:-
~
Cr-51' 4.46E-03 - 8'. 5 4 E-04 -
-Mn-54 0;00E+00 6.13E-06 Co-58 3.04E-06 ~2.18E-06 Fe-59. O.00E+00 0.00E+00
- Co-60 2.34E-05 3.44E-05 Zn-65 0.00E+00 0.00E+00 '
1Ag-110m? 0.00E+00 0.00E+00 Ce-141- 0.00E+00 0.00E+00 Ce-144 -0.00E+00 0.00E+00- ]
Totall 4.50E-03 9.16E-04
.:. g;
~
1 N
J V
ii ,
t
- Notation: LAn entry _of-0.00E+00 does not-represent the L.. 23 l~ absence'ofia radionuclide'but indicates that.the . .
l- . concentration of the;nuclide was below the'LLDLvalue listed l
-in Tablef3.
24 L
w-+we'- ++ c er*, 3 + p r -s . ,a.r g - , e ,-. w a ,- w .,-.--,--n w.. .-w<.. . 4,-w v. - - -. + **
(. ;, ; ~ ~ -- - - - ~ - -- - - +- -. > -
)
1 r.
TABLE 3 ,
j t RADIOACTIVE GASEOUS WASTE LLD VALUES LOWER LIMIT OF '
TYPE OF
~
DETECTION - (LLD)"
ACTIVITY ANALYSIS (uCi/mli- i Principal Gamma Emittersb ,c 1
1x10~4' 1x1p-& f
-H-3c ah:
. 1-131 0 1x10-12 j I-133 d 1x10-10 Principal Gamma Emittersb ,e 1x10~11' .
.)
(I-131,,others) i i
f 1x10~11
' Gross Alpha - f' Sr-89, Sr-909 '1x10~11 4
, ..j i
Table 3' Notations '!
ahheLLD!is: defined,Jforpurposes.ofthese. specifications,7 as the .
> smallest concentration'of radioactive material in-a sample that >
twillLy'ield a:.~neticount,:above system background; that will;bo1 :
f'
~detectediwith 95%' probability with only 5% probability of Lfalsely concluding that:alblank' observation represents af"real"~
ii signal =.f ;;
p # Forra'particular. measurement system, which may include-lradiochemicalyseparation:
L. <
. 4.66 sb "[
.LLD =
Eix V x 2.22 x 10 _6 x. y x _ exp (-Ag).
L I: ,
25 I
q - s -
.e e v w - , - , -
Table 3 Notations (Cont'd)
Where:
LLD is 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 or of the counting rate of a blank sample as appropriato, as counts per minute, E is the counting efficiency, 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 per minute por microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactlye decay constant for the particular '
radionuclide (sec~ ) and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec).
It should be recognized that the LLD is defined as an a oriori (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 specification applies include the following radionuclidos: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Cc-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported-in the Semiannual Radioactive Effluent Release' Report.
cMonthly grab sample and analysis d
Continuout charcoal sample analyzed weekly
- Continuous particulate sample analyzed weekly f
Composite particulate sample analyzed monthly 9Composite particulate sample analyzed quarterly i
i t
26
.: ; +
r TABLE 4 ,
WATERBORNE EFFLUENTS - SUMMATION OF ALL RELEASES
-Data Period: July _1, 1990 - December 31, 1990 BATCH MODE Est. Total Nuclide Category Unit 3rd Quarter 4th Quarter Error, %
A.oFission & Activation Products
- 1. Total Release- Ci 2.08E-02 8.24E-04* 14
- 2. Average" Diluted t Concentration uC1/ml 8.70E-08 '3.94E-08*
- 3. Percent of Applicable-Limit % '1.66E+00' 6.59E-02*
B.. Tritium
- 1. Total Release Ci 2.35Er00 1.77E 5 o2. Average Diluted' Concentration uC1/ml 9.83E-06 8.46E-06
- 3. Percent of Applicable Limit. %= ~3.28E-31. 2.82E-03 ,
L C.' Dissolved-and
~ Entrained ~Gasgs. I
- 1. Total Release 'Ci 0.00E+00 0.00E+00 '11+
2.-Average Diluted h Concentration -uC1/ml 0.00E+00 0.00E+00
- 3. Percent of 4
. Applicable Limit '% 0.00E+00 0.00E+00 D.1 Gross Alpha- ,
Radioactivity
-Released -Ci 0.00E+00 0.00E+00 56
'E.; Volume of Waste gal. 7.36E+05 9.18E+04 5.5L Released liters ~2.78E+06 3.48E+05
, , s F. Volume of; Dilution < gal. 6.30E+07- 5.52E+06 3
, Water.Used- liters 12.39E+08- 2.09E+07 ,,
- - Reported; values include'Fe-55' values based on third quarter. '
-1990: sample analysesLand fourth quarter discharge volumes.
4^ Notation:1An 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-systen, even though noble gas activity is <LLD.
27 i
i i
_. _ m _ _ - _ - . _ _ _ . . _ _ . -
TABLE 5 WATERBORNE EFFLUENTS-(Curies)5 ,
Data Period: July 1, 1990 - December 31, 1990
_2 Batch Mode '
Nuclide Third Quarter Fourth Quarter A. Tritium 2.35E+00 1.77E-01 B. Fission & Acti- 1
.vation Products Cr-51' 2.41E 8.80E-05 Mn-54 4.35E '1.85E-04 Co-58 3.01E-04 7.21E-06 Co-60 1.37E-02 5.44E-04 '
Fe 0.00E+00 0.00E+00*
Fe-59 0.00E+00 0.00E+00 Zn-65 0.00E+00 - 0.00E+00 Sr-89 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
- l. Cs-134 0.00E+00- 0.00E+00
=Cs-137 0.00E+00 0.00E+00 Ba-140 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 Ag-110m 1.34E-04 0.00E+00 Total 2.08E-02 . 8.24E-04 C. Dissolved and Entrained Gases Kr-85 Kr-85m ;
,Kr-87 Kr Xe-133
- . Xe-133m
! .Xe-135 Xe-135m Xe-138-- '
Total 0.00E+00- O 00E+00 -
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 in Table 6.-
- Reported.value is estimated. based on third quarter 1990 sample analyses and fourth quarter 1990 discharge volumes.
28 Yb-+p-mW --- , + - v-- p4 yen p 47q<g -w -
y (g"gp* -fW--M-1T-y'g'r 4- t- m -
F --4--
t h TABLE 6 *
- RADIOACTIVE. LIQUID WASTE LLD VALUES LOWER LIMIT OF
-TYPE OF DETECTION (LLD)a ACTIVITY ~ ANALYSIS (uci/ml)
Principal Gamma Emitters b '5x10~7
-I-131- 1x10-6 Dissolved and Entrained Gases 1x10-5 (Gamma Emitters)
, H-3 1x10-5 Gross Alpha 1x10-7 Sr-89,'Sr-90 5x10~8 -
'(
Table 6'Notationg= .a n
aThe LLD is defined, for-purposes of these requirements,'as the d smallest-concentration ofsradioactive material in a; sample that L will yield a-net-count, above system background,-thatswill be 11 detected;with 95% probability with only 5% probability of. .
.i
= falsely; concluding 1that a blank observation-. represents a."real" ;r signal.
--For a particular. measurement system,fwhich may include i
L c radiochemical: separation:: =!
i-
~4.'66 ab L-l LLD =
E=x.V x,2.22 x 10 6 x'Y x exp (~MD) .
l: 1 p-J p
29
. . . - - . , , - . , , ..,,,4
,..-.m y... ,. ..- -,.,_c , 4.n., , . - , . . ----.e g- y9 s
Table 6 Notations (Cont'd)
Where:-
LLD is 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 or of the counting rate of a blank sample as appropriate, as counts per minute, E is'the counting efficiency, 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 per minute per microcurie, Y is the fractional radiochemical yield, when applicable, ;
y A'is the radioacti}e decry constant for the particular radionuclide (sec- ) and
.at-for plant effluents.ls 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.
It chould be recognized that the LLD is defined as an a nriori
.(before the' fact)-limit representing the capability of a
- measurecent system and not an an a costeriori- (after the fact) limit for a particular measurement.
b The principal' gamma emitters for which the LLD requiremont-applies include the following radionuclides: . Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,fCs-134, Cs-137,'and Ce Co-144 shall also.be measured, but'with an LLD of 5 x lo-gl41.
. -This list- .
l does not mean that only thone nuclides are to be detected and . 4
-reported. Other gamma' peaks that are measurable,=together with-those of the above nuclidos,-shall-also be analyzed and reported inithe Semiannual Radioactive Effluent Release Report. ,
+
30
.~ _ _ ... -- . -
. 4 SOLID WASTE AND IRPyhDI ATED FUEL BHIPMENTS During this reporting period there were twenty-three (23) radioactive waste shipments and no irradiated fuel shipments from CPS as reported in Table 7. All vaste shipped in this reporting period wac classified as class A. In addition, the CPS OCDM requires reporting of the following information for solid waste shipped offsite during the report period
- 1. Total curie quantity: 425.6 curies as determined by dose-to-curie and sample concentration methodology estimates.
- 2. Principal radionuclides: See Table 7, A.2 for listing of measured radionuclides.
- 3. . Source of waste and processing employed: Resins, filter sludges and evaporator bottoms dewatered or solidified in cement. Compacted and non-compacted dry active waste.
- 4. Type of container: LSA, Type I, and Strong Tight Container.
- 5. Solidification agent or absorbent: Cement, Ditumen (ATI),
Aquaset I and II, and Petroset I and II (no absorbents used).
l l
31 4
TABLE 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS July 1, 1990 - December 31, 1990 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-MONTH EST. TOTAL
- 1. TYPE OF WASTE UNIT PERIOD ERROR, %
- a. Resins, m3 1.24E+02 filter sludges, Ci 4.25E+02 25 evaporator bottoms, etc.
- b. Dry compactible m3 4.03E+01 waste, contaminated Ci 6.05E-01 25 equipment, etc.
- c. Irradiated components m3 0.00E+00 control rods, etc. Ci 0.00E+00 0
- d. Other m3 0.00E+00 Ci 0.00E+00 0
- 2. ESTIMATE OF tr70R NUCLIDE COMPOSITION NUCLIDE PERCENT NAME ABUNDANCE CURIES
- a. Fe-55 51.50% 2.19E+02 Co-60 34.69% 1.47E+02 Mn-54 9.57% 4.06E+01 Cr-51 1.86% 7.89E+00 Co-58 1.30% 5.55E+00 OTHER 1.07% 4.52E+00
- b. Fe-55 54.29% 3.28E-01 Co-60 24.40% 1.48E-01 Cr-51 11.20% 6.80E-02 Mn-54 8.54% 5.20E-02 Co-58 1.74% 1.00E-02 OTHER 0.006% 3.60E-05
- c. NOME N/A N/A
- d. HONE N/A N/A 32 )
.. _ . _ . . .. . . . . _ . . _ . . - ~ . . _ .- . ._. ._ . . . , . _ _ _ . _ .-
' .[
- x. e =
_' g ; > <J L _
v
- TABLE - 7 = (Cont'd) -
SOLID WASTE AND-IRRADIATED FUEL SHIPMENTS July.1, 1990 - December-31,: 1990
._3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE 0F TRANSPORTATION DESTINATION ,
-18 Truck Richland,:WA-Si Truck' Barnwell, SC ,j
'B. IRRADIATED _ FUEL SHIPMENTS (Disposition')
NUMBER OF SHIPMENTS- MODE OF TRANSPORTATION ' DESTINATION-NONE N/A N/A
$' [ -
. _ -r -- i
~l
, e . - i -. ,
t 1
l k
- - r
-3
( r}- 1j
- t-i s
5 v
k l
1 33
- g. m. .q
TABLE B CORRECTIONS TO DATA REPORTED IN PREVIOUS DEMIANNUAL REPORTS I. CORRECTION TO PERCENT OF APPLICABLE LIMIT A. Parameter of Concern: Second quarter 1990 percent of applicable limit for tritium in waterborne effluents, Table 4, Item B.3.
- 1. Reported Value: 5.55E+00%
Corrected Value: 3.40E-01%
II. CORRECTION OF OMITTED TRITIUM ACTIVITY A. Parameter of Concern: Third quarter 1989 tritium in waterborne effluents, Table 4, Item A.
- 3. Reported Value: None reported Corrected Value: 1.12E+00 Curies III. DELETION OF 16.5 CURIES Kr-85 A. Parameter of Concern: First quarter 1990 Kr-85 in airborne effluents, Table 1, Section A, Items 1 and 2.
- 1. Reported Value: 2.74E+01 Curies Corrected Value: 1.09E+01 Curies
- 2. Reported Value: 3.48E+00 uC1/sec.
Corrected Value: 1.38E+00 uCi/sec B. Parameter of Concern: First quarter 1990 Kr-85 in airborne effluents, Table 2, Section A, Kr-85 value and total gases.
- 2. Reported Value: 2.74E+01 Total Curies Corrected Value: 1.09E+01 Total Curies C. Parameter of Concern: First half of 1990, doses to receptors located within the cite boundary, plume exposure pathway, Tables 14 through 20.
- 1. Table 14 Reported Value: total body = 4.54E-06 mrom skin = 2.94E-05 mrem Corrected Value: total body = 4.50E-06 mrem skin = 2.43E-05 mrom 34 )
h -.
jf i -
p
$yry; ht t =2.- Tabic 15
-4p
, Reported:Value total body = 3.00E-07 mrem he skin =-2.42E-05 mrem fi' -
Corrected Values total body = 2.63E-07 mrem-skin = 1.97E-05 mrem ,
. 1
-3.- Table 16 and Table 17: -No= changes
[
f 4 . -- Table 18 ] .
/ Reported-Values -total body =___3.55E-07= mrem- Js skin-= 1'.37E-04 mrem' f Corrected Value , total-body:= 2.97E-06 mrem U skin = 6.76E-05 mrem I "
. Table 19.__
l
~ Reported Value:- total body = 5.74E-06 mrem skin =-5.59E-05 mrem Corrected Values" total bodyLa_ 5.60E-06-mrem' skin = 3.97E-05 mrem 62 Table 20--
Reported-Value: Ltotal= body ~..= 4.78E-05 mrem skin-=--2.13E-04Lmram Corrected Values. total body =g4.76E-05 mrem skin = 1.85E-04 mrem h .i lc w
..( m.
i
,a.z,
)[l 5
- I$
w a -
y
-4
-f
- ?
I
!% ' ~
} l
%,i-j
-- i l~
35
.. l R , > . . .. . . . -
. , . y -
- y , . . ;'
i f ;ii ru I
+
TABLE 9
EFFLUENT DATA NOT AVAILABLE FOR '!
PREVIOUS SEMIANNUAL REPORT D
-Data Period: April;1,- 1990 - June 30,-1990.
.n-o -NuclideiCategory Unitc Second Quarter 1990 i
A.TAirborne Effluents
- 1. - Sr-89= Ci 2.01E-05' 2.-Sr Ci 0.00E+00
, B. Waterborne Effluents -
1.:Fe Ci 4.82E-04 !
);p . -
S. ,
9
.! 4
.}
- r
'4-.
-) !6
,,9 3
i;
,, ]
x4 .
- Ytm Nii 4 '.'
+
d 1
.?
1 P i1-
.-s
.f i ,
ih i
'6' ; Notation: An entry of 0.00E+00 does not represent the absence of a radionuclide butiindicates that the z concentration was.below the LLD value listed in Table 3.- !
.t t- 36
- 1. .
i y
, ,,;,-_--, .. , _.,, - _ , _ ~ , , , - - - -
. , . + , ,----_-.---__,,.m., -
y A,i 7
- T
, ., ; F !
i
.) .
f+
f
. t ,1 t
f a= =
S,_9 MB85 ,,
i
. :1 y
4 ANJ .,
i pl -
.(
SO -
_ S AO S_
l'
?
y t
s b
.g
't i
f i
(. i.
- r. I j
t l-f :..
I l'-
i METEOROLOGICAL DATA AND DISDERSION_ ESTIMATES r
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 instrumentation, at the 10-meter and 60-meter levels. Wind directions and speeds at the 10-meter and'60-meter levels are i 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 temperature between the 10- ati 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 C'inton-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 individdally to a microprocesror and chart recorders.
The microprocessor-la parc of the Clinton Power Station Radiation Monitoring System. Muteorological data is available via the microprc essors 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.- Sco Tables-10-13 and Figures 5-7 for more-detailed information on-meteorologyLand dispersion' data.
P i 37
TABLE 10 METEOROLOGICAL DATA AVAILABILITY Data Period: January 1, 1990 - December 31, 1990 Percent of Valid Parameter Hours Durina Period
- 1. Wind Speed
- a. 10-meter Sensor 98%
- b. 60-meter Sensor 97%
- 2. Wind Direction
- a. 10-meter Sensor 98%
- b. 60-meter Sensor 97%
- 3. Temperature
- a. 10-meter 98%
- b. Temperature Difference (10m-60m) 96%
- 4. Percent of hours for which valid 96.1%
10-meter Wind Speed, Wind Direction,
& Delta Temperature were available
- 5. Percent of hours for which valid 95.1%
60-meter Wind Speed, Wind Direction,
&' Delta Temperature were available 38 I
1 FIGURE 5 -i f
CPB WIND ROSE: 10-METER .
4 Data Period:- January 1, 1990 - December 31, 1990 N
NNW NNE ,
50% 6.1%
NW NE 6.1% 3.8% ,
- re WNW ENE 6.0% / ' 2.6%
E
=
s E
E N
- 6. b% -- EIIIIIb 2 E 3.0%
b E
=
)
5 WSW E ESE
.5.1% - .-3 7%- ,
1
[
SW SF 5.6%-
5.3%-
'" S WIND SPEED KEY l
11.8% -
I >24 MPH
}ij 19-24 MPH E 13-18 MPH-8-12 MPH 4-7 MPH i-3 MPH 39 I
w e, -----e -w w ---s w m E ,- er
t.. ...
FIGURE 6-CPS WIND ROSE 60-METER ~
Data'Periodt- January 1, 1990 - December 31, 1990 N
NNW NNE 4.9% 5.7%
NW- NE' 5.6%- 4.3%
E WNW ENE 4.9% 3.0%
5 5.3% I OE 24 - bD 3.3%
.[ m ,
WSW ..
y j M
4 ESE 4.5% '
3.3%
4.7% i
- t SSW-. SSE
!' 13.4% 7.2%.
l S WIND SPEED KEY 12.5% -
L >24 MPH I 19-24 MPH E 13-18 MPH 8-l2 MPH 4-7 MPH I-3 MPH 40
FIGURE 7 CLINTON POWER STATION DISTRIBUTION OF ATMOSPHERIC STABILITY CLASS I
Data Period: January - December 1990 x
] .2666 EXTREMELY UNSTABLE Hours /32.3%
^
x 7 y MODERATELY UNSTABLE
\ E 188 Hours /2.3%
NNy
\ ..
' ] SLIGHTLY UNSTABLE 230 Hours /2.8%
NEUTRAL S(N x-
\ ))N\
bq'
\\ '
vN Q _ j 1644 Hours /20.0%
SLIGHTLY STABLE
'/k%,($d{,([" . /
,N 2147 Hours /26.1%
,y,K MODERATELY STABLE
- '* gy'Nv) , g 9*2 Hours /11.1%
s
-/
)
EXTREMELY STABLE j X) se*gg g 448 Hours /5.4% j Based on Joint Wind Frequency Distribution at 10 Meters (8235 Hourly Values)
TABLE 11 CLASSIFICATION OF ATMOSPHERIC STABILITY Stability Pasquill Defining r-Classification Categories Conditions Extremely unstable A -0.900<ATS-0.019 Moderately up" table B -0.019<ATS-0.017 SIightly unstable C -0.017<aTS-0.015 y
Neutral D -0.015<aTS-0.005
-Slightly stable E -0.005<ATs 0.015 Moderately stable F 0.015<ATS 0.040 Extremely _ stable G 0.040<ATS 0.900 Invalid ATS-0.900 or AT>0.900 AT = temperature difference in Celsius deirees per meter c
1
,1~
42
y, ~ .. y_.-- ,
. . . . . . . _ __. m-. . _. - _ , - . .. - __.. - . .
, i<-
_ ~1
) (
)
TABLE 12, Page 1 of 7 i LJOINT WIND FREQDENCY DISTRIBUTION BY STABILITY CLASS Data Periodt January 1, 1990
- December 31,11990
-i
-STABILITY CLASS A-WIND. SPEED (MOH) AT 10 METER LEVEL DIRECTION ^13= '4 7 8 12 13 18' 19 24 >24 -TOTAL .
'N-
- 1.40E 01 - 4.40E 01 8.60E 01 4.90E 01 3.00E 00 0.00E 01 1.96E 02 j NNE- 1.00E 01 - 5.00E 01 5.70E 01 9.00E 00 2.00E 00.- 0.00E 01 1.28E 02 NE 6.00E'00- 3.40E 01 - 3.10E 01 6.00E 00 1.00E 00 . i0.00E 01 7.80E 01
-ENE 6.00E 00 1.70E 01- 1.70E 01. 1.90E-01 0.00E 01 0.00E 01 5.90E.01 [
L ;E 1.00E 01 3.50E 01 4.40E 01 - 1.10! 01' 1.00E 00 1.00E 00 1.02E 02
[ESE 1.10E 01 l1.40E 01 -3.60E 01 1.10E 01! 3.00E LO 0.00E 01 1.15E 02'
~ SE 4.00E 00 9.10E 01 4.00E 01.. 1.30E 01 . 2.00E 00 0.00E 01 1.50F, 02 SSE- 6.00E 00- -9.20E 01 8.40E 01 3.00E 01 2.00E 00 'O.00E 01 2.14E 02
-S. .1.00E 01 -9.40E 01 1.32E 02- 8.00E 01. 1.30E 01'- 7.00E 00 3.36E 02'
- SSW-
- 1.10E 01 5.40E 01 1.27E 02 9.90E 01 -- 1.90E 01, 3.00E 00 3.13E 02
' SW " - 8.00E 00: 3.00E 01 9.10E 01 4.80E 01 6.00E 00 0.00E 01. 1.83E 02 WSW - 4.00E 00 3.4CE 01 . 5.20E 01 2.60E 01- 8.00E 00 3.00E 00 1.27E 02 WL - 8.00E 00 3.10E 01- 6.70E 01- 3.20E 01 s.70E 01 2.40E 01 1.79E 02 WNW t 9.00E 00 4.00E 01 4.60E 01- 3.50E 01- -2.10E 01 9.00E 00 1.60E 02 j
, q- NW 1.00E 01; '3.50E 01' 5.70E-01 5.40E 01 1.50E 01 ,1.90E 01 ..).90E 02 j NNW i '6.00E 00 3.70E 01 5.80E 01 2.70E 01' 3.00E 00 5.00E 00 - 1.36E_QJ sTOTALL .1.33E 62 - 7.72E 02' 1.03E 03 5.49E 02 1.16E 02 7.10E 01- 2.67E 03 LPERICOS OF CALM (HOURS): 8.800E 01 W!ND SPEED (MPH) AT 60 METER LEVEL .
. i M
~I3 ' : DIRECTION 13 47 8 12 13 18 19 24 324' TOTAL'-
(N =5.00E'00 2.70E 01 7.40! 01 6.30E 01 - 2.00E 00 0.00E 01' 1.71E 02 Y NNE L :6.00E 00 '1.90E 01 6.60E'01- '1.80E 01 ~ -
- 9. DOE 00 * -2.00E 00 . 1.20E 02
- NE . 5.00E 00 2.10E 01 3.60E 01 2.20E 01 7.00E 00 2,00f 00 9.30E 01 ENE .-1.00E 00 1.50E 01 2.60E 01 1.90E 01. 6.00E 00. 2.00E t1. 8.70E 01 l E 3.00E 00- 1.50E 01 2.60E.01 '2,00E 01 3.50E 01-- ' t.30E 1,1
- 1.12E 02
- ESE- n5.00E 00 ~2.60E 01, 3.10E 01 2.t02 .01 6.00E 00. .0.00F 01 8.80E 01
'SE{ B.00E;00 6.20E - Cl i '5.20E 01 I Z E 01 0.00E-01v 'O.00E 00 1.35E 02- <
ASSE: .1.10F D1 '3.80E 01 5.90E 01 (.30E 01 2.10E 01 3.001 00 1.75E 02 8; 5.00EIO 5.40E 01 9.00E 01 6.JE 01 - 4.50E 01 4.20E 01 3.22E 02 rlJ-- , . Ssw " 5.00E 60 3.20E 01- V.02E 01 9.30E 01 5,00E 01 4.10E 01 3.13E 02
. CV .3.00E 00- 2.00E 01 8.7CE 01 - 9.40E 01 4.50E 01 1.80E 41 2.67E 02
% VSW- 6.00E 00 -
~
2.80E 01 3.90E 01- 3.20E Of '1.20E 01 2.50E 01 .42E 02 -
WM '.
' ~
.W 4.00E 00 2.50E 01- 4.20E 01 4.10E 0% ' 1.3U2 01 3.40E 01: 1.59E 02-
^
- WW 5.00E OD. '2.00E 01 -4.10E 01 3.50E 01 1.70E 01 2.70E 01 1.45E 02
- NW 1.10E 01 2.90E 01 3.40E 01 5.60E 01 2.20E 01 2.70E 01 1J2E 02 NW 7.00E 00 2.90E 01 4.70E 01 5.20E 01 1.00E 01 7.00E 00 1.52E 02 g TOTAL ~ 9.00E 01 4.60E 02 8.42E 02 - /.07E 02 3.00E 02 2.54E 02 2.65E 03 l.
PERICC10F CALM (Holmt): 7.70E 01 43 L
L ,
. 21, . a- .n . - - . - - - -
, - - , - . . ~ . - . . _ . - . . . --, -- ~ . . ~ . . . . - --~ .. . . -
)
- p. ; .-
4 y
. TABLE 12, Page 2 of 7
-JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS beta Period: January 1, 1990 December 31, 1990-STAstlttY CLASS BL 1.
WIND SPEED (MPN) At 10 METER LEVEL
. DIRECTION 1*3 47 8 12 13 18 19 24 m24 TOTAL N 0.00E 01: 1.00E 00 9.00E 00 7.00E 00 3.00E 00 0.00E 01 2.00E 01 lost 1.00E 00- 2.00E 00 0.00E 01 1.00E 00 1.00E 00 0.006 01 5.00E 00-NE - 0.00E 01 4.00E 00 2.00E 00 1.20E 01 1.00E 00 0.00E 01 1.90E 01 "
t ENE 0.00E*01- - 0.00E 01 2.00E 00 2.00E 00 0.00E 01 0.00E 01 4.00E 00 E 0.00E 01- 1.00E 00 1.00E 00 0.00E 01 0.00E 01- 0.00E 01 2.00E 00 LSE 0.00E 5.00E 00 3.00E 00 0.00E 01 0.00E 01 0.00E 01 8.00E 00 SE - 1.00E 00~ 3.00E 00 2.00E 00 0.00E 01 0.00E 01 0.00E 01 6.00E 00 SSE 0.00E 01 5.00E 00 6.005 00 0.00E 01 1.00E 00 0.00E 01 1.20E 01 :
s' O.00E 01- 5.00E 00 8.00E 00 5.00E 00 0.00E 01 1.00E 00 1.90E 01 t
-SSW- 0.00E 01 ,3.00E 00 3.00E 00 -- 6.00E 00- 3.00Z 00 -1.00E 00- 1.60E 01 SW - 2.00E 00 2.00E 00 1.00E'00 1 00E 00 'O.00E 01 0.00E 01- 6.00E 00 >;
. WSW 0.00E 01 0.00E 01 3.00E 00 1.00E 00 2.00E 00 0.006401 6.00E 00 W ' O.00E 01 3.00E 00 4.00E 00 4.006 00 2.00E 00 4.00E 00 1.70E 01 WNW 1.00E 00= 1.00E 00 3.00E 00 5.00E 00 0.00E 01 1.00E 00 1.10E 01 y : NW 0.00E 01- 0.00E*01 4.00E 00 9.00E 00 8.00E 00 1.00E 00 2.20E 01 ,
NNW 0.00E 01 3.00E 00 5.00E 00 4.00E 00 1.00E 00 2.00E 00 1.50E 01 TOTAL- 5.00E 00 3.80E 01 5.60E 01 5.70E 01- 2.2ft 01 1.00E 01 1.88E 02
-. PERIODS OF CALM (HOURS): 1.00E 01 0 8 e-WIND SPEED (MPH) At 60 METER' LEVEL . ;
e DIRECTION *13 47 8 12 13-18 19 24 324 TOTAL N . 0.00E 01- 0.00E 01 4.00E 00 5.00E 00 2.00E-00 0.00E 01 1,IDE 01 NNE l1,00E 00 1.00E 00- 5.00E 00 2.00E 00 2.00E 00 3.00E 00- 1.40E 01 NE 0.00E 01 0.00E 01 3.00E 00 3.00E 00 5.00E 00 5.00E 00- 1.60E Di ENE 0.00E 01 1.00E 00 1.00E 00 2.00E 00 3.00E 00 0.00E 01 7.00E 00 M E 0.30E 01 1.00E 00 0.00E 01 1.00E 00 0.00E 01- 0.00E 01 2.00E 00 ESE -0.00E 01 1.00f 00 -6.00E 00 . 3.00E 00 0.00E 01 0.00E 01 1.00E 01 SE . - 0.00E 01. :2.00E 00 2.00E 00, 1.00E 00 -0.00E*01 0.00E 01 5.00E 00
$$f - 0.00E 01 .0.00E 01 1.00E 00 3.00E 00 1.00k 00 1.00E 00 6.00E 00 *
?$ - 0.00E 01 1.00E 00 ' ,.00E 00 6.00E 00 3.00E 00 7.00E 00. 2.20E 01 SSW .0.00E 01 1.00E 00 5.00E 00 6.00E 00 : 2.00E 00 9.00E 00' 2.30E 01
- SW - . 0.00E 01- 2.00E 00 3.00E 00 1.00E 00 - 1.00E 00 0.00E 01 7.00E 00 WSW 0.00E 01' s 00E-01 4.00E 00 0.00E 01 1.00E 00 3.00E 00- 8.00E 00 W 0.00E 01- 1.0M 00 3.00E 00 1.00E 00 4.00E 00. 6.00E 00 1.50E 01-WNW . 0.00E 01 2.00s 00 2.00E 00-- 3.00E 00 3.00E 00 6.00E 00 1.60E 01 NW -0.00E 01- 1.00E TO 2.00E 00 6.00E 00- '$.00E 00 1.00E 00 1.50E 01 i NNV 0.00E 01 1.00E 0 ' 2.00E 00 3.00E 00 1.00E 00 4.00E 00 1.10E 01 i ,- T0fAL; 1.00E 00 1.50E 01 4.80E 01 4.60E 01 3.30E 01 4.50i 01 1.88E 02 PERICOS OF CALM (MCURS): 8.00E 00 44 .
R.
E _,u, ,. . , . - - ~ . - - , _
l 1 ABLE 12. Pepe 3 of ~
4 J(., INT WIND ThLgUENCY DISTRIBUTIM AY STABILITY CLASS Date PeH om Jewy 1, iWO Dece.w 11. Ino stanttitt etest t ug, lettD (Mow) At 10 MittGE titittt> 13 ,_47 e 12 13 18 19 24 >24 totAt b 2.00t 00 0. Cot 01 1.001 01 5.00E 00 7.00t 00 1.00t 00 2.50t 01 Wht 1.001 00 1.00t 00 7.00t 00 3.001 00 0.00E 01 0.00t 01 1.201 01 NE 1.00f 00 3.006 00 6.00t 00 2.005 00 0.00E 01 0.00t 01 1.20t 01 tut 0.00t e1 1.00t 00 8.00t 00 3.00t 00 0.00t 01 0.00t 01 1.20t 01 E 0.00E 01 3.00t 00 2.00t 00 0.00E 01 0.00t 01 1.001 00 6.00t 00 Ett 1.000 00 4.00t 00 1.00t 00 0.00t 01 0.00t 01 0.00E 01 6.00" 00
$t J.00t 01 4.00t 00 7.001 00 0.00t 01 0.00t 01 0.00t*01 1.10t 01 EEE 1.006 00 3.00t 00 5.00t 00 4.00t 00 0.00E 01 0.00E 01 1.30E 01 8 0.00t 01 2.00t 00 5.005 00 7,00t 00 1.00t 00 0.00E 01 1.501 01 ttV 0.00E 01 2.00t 00 4.tiot 00 9.00t 00 3.00t 00 0.00t 01 2.00t 01 SW v.00t 01 4.00t 00 4.00t 00 2.00t 00 i.00t 00 0.00t 01 1.iOE 01 Vtw 1.00t 00 1.00t 00 3.001 00 6.00t 00 1.00t 00 0 00E 01 1.20C 01 W 0.00E 01 2.00f 00 - 3.00t 00 6.001 00 2.00t 00 3.00t 00 1.60t 01 WWW 0.00E 01 3.00t 00 3.00t 00 6.00t 00 2.00t 00 1.00t 00 1.50t 01 NV 0.00E 01 S.00t 00 6.00t 00 1.20t 01 4.00t 00 2.00t 00 2.901 01 Wwv D.00t 01 0.00t 01 1.00t 01 4.00t 00 0.00t 01 1.00t 00 1.50! 01 TOTAL 7.00E 00 3.80E 01 8.40t 01 c.90E 01 2.30t 01 9.00t 00 2.30t 02 Pitt0D$ OF CALM (WOutt): 7.00t 00 WIND $Ptt0 (M,fy) AY 60 METE U M plPitt104 13 47 6 12 13 16 19 24 324 TOTAL N (n 00t 01 0.00t 01 5.00t 00 1.00t 01 2.00t 00 0.00f 01 1.70t 01 Wht 0.00t 01 0.00t 01 3.00t 00 6.00t 00 1.00t 00 1.000 00 1.10t 01 kt 1.00t 00 0.00t 01 4.00t 00 7 ?! 00 1.00t 00 0.00t 01 1.30t 01 ENE 0.00E 01 1.00t 00 2.00t 00 5.00t 00 3.00t 00 0.00E 01 1.10E 01 t 0.00t 01 1.00t 00 2.00t 00 2.00f 00 1.00t 00 0.00t 01 6.00t 00
($t 1.005 00 4.00! 00 3.000 00 1.00E 00 0.00t 01 0.00E 01 9.001 00 St 0.00t 01 2.00t 00 2.00E 00 4.005 00 0.00t bl 0.00E 01 6.00t 00 558 0.00t 01 1.00t 00 2.00t 00 2.00t 00 2.00t 00 2.00t 00 9.00f 00 8 0.00E 01 0.00t 01 6.00t 00 3.00t 00 5.00t 00 6.00t 00 2.00t 01
$$W 0.00E 01 0.00t 01 5.00t 00 6.00t 00 4.00t 00 1.10E 01 2.60E 01
&V 0.00t 01 1.001 00 3.001 00 3.00t 00 3.00t 00 0.00E 01 1.00t 01 WSW 0.00E 01 2.00t 00 2.00t 00 1.00t 00 2.00E 00 2.00t 00 9.00t 00 V 1.00t ce 1.00t 00 2.000 00 5.00t 00 1.00t 00 7.00t 00 1.70t 01 WWV 0.00E 01 1.00t 00 2.00t 00 4.00E 00 5.00t 00 7.00t 00 1.900 01 NV 0.00t 01 2.00t 00 4,00t 00 1.10t 01 5.00t 00 2.00E 00 2.40t 01 WNV 0.00t 01 3.00t 00 6.00t 00 5.001,fp 3.00t 00 2.00t 00 1.90E 01 TOTAL 3.005 00 1.90t 01 5.30E 01 7.50t 01 3.60E 01 4.00t 01 2.28t 02 PERICOS OF CALM (HOUR $): 6.00t 00 45
I
. e 1ASLI 12, Page 4 of 7 JOINT WIND FREQUENCY DISTRIDUTION DY DTADILITY CLAllD Data Peric& Jewtiry 1,1990 Decent >er 31, 1990 51A91tlVY CLAll 0 uND tett0 (MPN) 41 10 WEf((,1[y1(
glPIC110eL 11 47 8 12 _ 13 12 i t;,h,,,,, *24 TOTAL W 4.00t 00 4.406 01 9.40t 01 4.90t 01 8.008 00 1.00t 00 2.00t 02 WN! 9.00t 00 3.80t 01 9.20t 01 3.10t 01 $ 00t 00 0.0J 01 1.754 02 WE 3.00t 00 3.50t 01 3.001 01 1.201 01 2.00( 00 0.002 01 8.20t 01 (WE 3.006 00 1.64 01 1.10t 01 4.004 00 0.001 01 0.00t 01 3.40s 01 t 1.006 00 1.50L 01 7.00f 00 0.00t 01 0.00t 01 0.001 01 2.304 01 f tt 5.00t 00 2.10E 01 7.00t 00 0.00t 01 0.00t 01 0.00t 01 3.30t 01 51 0.00t 01 2.80t 01 2.40E 01 3.00t 00 0.00t 01 0.00t 01 5.50t 01
$$t 3.00t 00 4.10t 01 4.20t 01 1.70t 01 0.006 01 1.00t 00 1.041 02 5 2.00E 00 2.80t 01 6.50t 01 3.30t 01 F.00t 00 1.00t O(. 1.361 02 ssv 4.00t 00 2.30t 01 7.60s 01 5.r'Ot 01 9.00t 00 2.00t 00 1.64t 02 5V 4.00t 00 1.90t 01 3.30t 01 2.20t 01 5.00t 00 0.00t 01 8.30t 01 v5W 3.00E 00 1.60E 01 1.40t 01 2.30t 01 1.601 01 1.00t 00 7.30t 01 W 2.00t 00 9.00t 03 2.50t 01 3.70t 01 8.00t 00 1.30t 01 9.40t 01 WWW 3.00t 00 1.10t 01 3.20t 01 4.80t 01 1.90t 01 1.20t 01 1.25t 02 WV 1.00t 00 2.10t 01 4.00t 01 3.80t 01 1.40t 0 5.00t 00 1.19t 02 NWW i.00t 00 2.60f 01 7 60t 01 3.40t 9.1, 6.C't 00 1.00t 00 1.44t 01 101AL 4.806 01 3.911 02 6.68f 02 4.01t 02 9.90t 01 3.70t 01 1.64f 03 Pitt0DS Of CALM (Ha'.ms): 4.10E 01 WIND tPtte tweN) A160 mtitpd[yLL DIPittlDN 13 47 B 12 13 18 11.24 >24 121AL_,.
N 1.006 00 2.101 01 4.60t 01 8.80t 01 3.10t 01 7.00E 00 1.94E 02 kut 0.00f 01 2.10E 01 $.60E 01 8.20t 01 1.90t 01 1.60E 01 1.941 02 NE 1.00t DC 1.00t 01 2.80t 01 4.50t 01 1.00t 01 2.00t 00 9.60t 01 ENE 2.00t 00 7.00t 00 '.not 01 7.00t 00 6.00t 00 1.00t 00 4.10t 01 t 2.00t 00 4.00E 00 1.20t 01 1.40t 01 1.00t 00 0.00t 01 3.30t 01 Elf 0.00t 01 1.50t 01 2.10E 01 8.00t 00 0.00E 01 0.00t 01 4.40t 01 St 1.00t 00 1.30E 01 3.20t 01 8.00t 00 4.00t 00 3.00t 00 6.10t 01 S$t 1.00f 00 2.00t 00 3.40t 01 3.00f 01 1.10t 01 9.006 00 8.70E 01 .
I S 1.001 00 6.00t 00 3.90t 01 4.60t 01 4.8X 01 3.90t 01 1.79t 02 S$W 2.00t 00 $ 00t 00 3.00t 01 6.30E 01 4.70t 01 2.60t 01 1.73t 02 SW 1.00E 00 9.00t 00 1.80t 01 2.60t 01 1.20t 01 4.00E 00 7.00t 01 VtV 1.00t 00 3.00f 00 1.20t 01 1.90E 01 1.40t Oi 5.00t 00 5.40E 01 W 2.00E 00 9.00t 00 1.90t 01 .70t 01 1.30t 01 2.10t 01 9.101 01 WWW 0.00t 01 5.00t 00 2.10E 01 a.30t 01 1.10E 01 2.70t 01 9.70E 01 l WV 0.00E 01 8.00t 00 1.60E 01 4.40t 01 1.30t 01 1.10E 01 9.20t 01 hvW 1.00t 00 1 &E 01 3.50f 01 3.40t 01 1.70t 01 7.00E 00 1.0M 02 l
TOTAL 1.60E 01 1.52t 02 4.37f 02 5.741 02 2.57E 02 1.78t 02 1.61t 03 I
PtFI ~) 0F CALM (HOURS): 4.30t 01 ,
46 ,
1
)' ,
e
(" 1ABLt it, Page 5 of 7 l d
JOINT WIND FREfgUENCY DISTRIBUTION BY STABILITY CLA88 Data Feriod: .lanuary 1. 1990
- Deceder 31, 1990 RfAtitiff tLAtt 1 i-WIND SPfl0 (MPW1 At 10 Mtitt Ltyrt Diktefl0W i.3 47 9 12 13 18 19 ?4 *2 L TOTAL _
N 8.00t 00 5.90t 01 4.5M 01 1.00t 00 0.00E 01 0.00t.nl 1.13t 02
- Nut . 1.$0t 01 5.40t 01 2.3M 01 1.00t 00 0.0M*01 1.00t 00 9.40E 01 ut . 8.00t 00 3.40t 01 1.90t 01 1.00t 00 0.00E 01 0.00t 01 6.!M 01
- INE 1.00t 01 2.808 01 3.00t 00 2.00t 00 0.00t 01 0.0M401 4.30t 01 !
t 1.60E 01 ' 2.50t 01 1.70E 01 0,00E 01 0.00t+01 0.00t 01 5.30t 01 ftt 1.90s 01 5.60t 01 3.00t 00 0.00t 01 0.00E 01 0.00t 01 7.80t 01
'St 1.90t 01 1.11t 02 1.60E 01 4.00t 00 0.00t 01 0.00t*01 1.50t 02
- 884 - 1.10E 01 1.28E 02 9.40F 01 9.00t 00' i.00t 00 0.00t 01 2.434 02 8- 1.60t 01 9.40t 01 2.04t 02 4.80E 01 3.00t 00 0.001 01 3.65t 02
$sW 1.40t 01- 7.7M 01 1.53t 02 6.90t 01 6.00t 00 0.00t*01 3.19t 02 SW 1.30t 01 3.30E 01 4.70t 01 1.00t 01 1.00t 00 0.00t*01 1.04t 02 W9W 9 CT 00 2.70t 01 5.80t 01 3.10t 01 5.00t 00 0.00t*01 1.30t 02 W !.00E 00 2.60E 01 4.90t 01 3.30t 01 1.00t 00 2.00t 00 1.16t 02 WWW 4.006 00 3.60t of 3.70E 01 1.80E 01 3.00t 00 2.001 00 1.02t 02 NW 4.M 30 -4.60E 01. 4.40t 21 2.00t 00 1.00t 00 0.00t+01 .9.70t 01
- uuW 1.for t'1_ 4.10t 01 1.aot 01 S.00t 00 0.00t 01 0.00E0) 7.aot 01 10?AL 1.858 02 8.77E 02 8.25t 02 2.34t 02 2.10E 01 5.00t 00 2.15t 03 Pttl0DS OF CALM (N0utth 2.50t 01
, WIND SPitD (MPM) At 60 METER ttVEL Diettflom 2 1 3- -
47' 8 12 -13 18 - 19 E4 *24 TOTAt-N 4.00t 00 1.90E 01 4.40E 01 3.80t 01 4.00t,01 0.00t 01 '1.09E 02
. Nut 1.00E 00 1.50t 01 3.50t 2.60E 01- 6.00W 01 0.00t 01 8.30E 01 i
NE L 0.00E*01- 6.00t 00 2.60t 01 3.70E 01 -7.00t 01 0.00t+01 7.60E 01 t ENE . 1.00t 00 - 4.00t 00 -2.90t 01 1.50t 01 ~ 4.00t 00 1.00t 00 5.00t 01 I- 3.00E.00 7.00t 00 8.00E 00 1.80t 01 c.00E 01 0.004 01 3.60t 01 FSt 6.00t 00- 1.40t 01 2.70E 01 6.00t 00 1.00E 01 0.00t 01 5.40E 01 ,
St . 5.00t 00 3.30t 01 5.10E 01 9.00t 00- 3.00t 01 0.00t 01 1.01t 02 888 '3.00t 00 1.80s 01- 8.50c 01 7.80t 01 2.30t 00 8.00t 00 2.15e 02 8 -5.00f 00 1.80t 01 7 60t 01 1.37E 02 9.30t 01 3.30t 01 3.62t 02
$$W 1 3.00t 00 1.60E 01 4.50t 01 1.988 02 =1.24t 01 3.306 01 4.19E 02 SW - 0.00E 01 -1.006 01 4.10E 01 8.00t 01 3.10k 00 8.00t 00 1.70t 02-
- WsW, 3.00t 00- 1.70E 01 2.10t 01 3.30t 01 1.20t 00 1.00t 00 8.70E 01-W: 3.00E 00 -1'00t
. 01 2.00t 01 2.906 01 1.10t 01 1.106 01 8.40t 01. I WW- 3.00t 00 8.00t 00 3.70t 01 2.70E 01 8.00t 00 1.00t 00 8.40E 01 l NW 1.00t 00- 1.20t 01- 3.30t 01 . 3.60t 01 1.306 01 0.00E.01 9.50E 01 tutW ' 1.00t 00 1.30t 01 4.10t 01 2.00t 01 0.00kg,1 0.00t 01 7.50t 01 I
. TOTALL .4.20t 01 2.20E 02 6.19E 02 7.87E 02 3.36C 01 9.60E 01 2.10t 03 Pit 100$ 07.. CALM (HOURS): 4.30E 01 47 t
, ,-m,-r, ...--m.r..,,-,,,,wy,.&,m.,,,,---,._,---g.-. .,,,. m . ,,. -..,.,,_, - ._ ,,4.. ,,,,., _,,. ,_ 4.~
1Allt 12, Fase 6 of 7 JOINT WIND FREQUENCY DISTRIBUTION DY STADILITY ': LASS Date Period: .laruary 1,1990 Decenter 31, 1990 rag,1 Q Q,,,(1A$$ P VlWD $Ptt0 (uPM) A1 10 Mitte Lfylt gj eg1]DN 13 47 8 12 13 18 19 24 >24 TOT AL _
h 4.00t 00 3.401 01 6.00t 00 0.00E 01 0.00E 01 0.00E 01 4.40t 01 WNt 1.10t 01 3.50t 01 2.00E 00 0.001 01 0.00t 01 1.00t 00 4.90t 01 NE 1.80E 0' 2.20t 01 0.00t 01 0.00t 01 0.00t 01 0.00E 01 4.001 01 tut 1.30E 01 2.20t 01 0.00t 01 0 ME 01 0.00t 01- 0.00E 01 3.50t 01 E 2.60t 01 2.20t 01 1.00t 00 0.00t 01 0.00E 01 0.00t 01 4.90t 01 ttt 2.10t 01 2.30E 01 2.00t N 1.00t 00 b.%E 01 0.00E 01 4.70t 01 st 1.80E 01 4.90E 01 1.00F 00 0.00t 01 0.00t 01 0.0::M1 6.801 01
$$1 1.60t 01 8.00t 01 7.00t 00 0.00t 01 0.00t 01 0.00t 01 1.03[ 02 8 1.20t 01 7.70E 01 1.70E 01 1.00E 00 0.00E 01 0.00E 01 1.0?! 02
$$W i.10t 01 4.50E 01 2.80t 01 0.00E 01 0.001 01 0.00t 01 c.40t 01
$W 4.00t 00 2.70t 01 1.90t 01 1.001 00 0.00t 01 0.00(-01 5. 00 01 Wsw 7.00t 00 2.80E 01 2.00t 01 0.00t 01 0.00E 01 0.00t 01 5.50t 01 W 9.00E 00 3.20t 01 2.10t 01 1.00t 00 0.00t 01 0.00E 01 6.30E 01 VWW 9.00t 00 4.200 01 1.50t 01 0.005 01 0.00t 01 0.00E 01 6.60E 01 NV 4.00t 00 2.50t 01 6.00t 00 0.00t-01 0.00t 01 0.00E 01 3.50t 01 pW 4.00t 00 9.00t 00 3.00E 00 0.00t 01 0.00t 01 0.00t 01 1.60t 01 101AL 1.871 02 5.72t 02 1.48E 02 4.00t 00 C.00t 01 1.00t 00 9.12E 02 PERIODE OF CALM (HOUR $): 3.00t UO WlWD SPtfD (MPN) At 60 Mfitt Livf'.
MR1,[A 13 47 B 12 13 18 19 24 *24 TOTAL N 4.00t 00 3.00t 00 2.60t 01 1.006 01 0.00E 01 0.00t 01 4.30t 01 Wht 0.00E 01 3.00t 00 1.40t 01 1.60E 01 0.00E 01 1.00E 00 3.40t 01 Nt 2.00t 00 8.00t 00 1.20t 01 1.20E 01 1.00t 00 0.00t 01 3.50t 01 ENE 2.00E 00 4.00E 00 1.20E 01 8.00t 00 0.00t 01 0.00E 01 2.60E 01 E 2.00t 00 4.00t 00 1.20t 01 9.00t 00 0.00E 01 0.00E 01 2.70E 01 (St 1.00t 00 1.10E 01 2.60E 01 3.00t 00 0.00E 01 0.00E 01 4.10t 01 st 3.00t 00 3.30E 01 2.10E 01 5.00t 00 1.00t 00 0.001 01 6.30E 01
$$t 1.00E 00 2.40t 01 2.70E 01 2.30E 01 2.00t 00 0.00t 01 7.70t 01 5 1.00E 00 1.20t 01 2.801 01 5.90t 01 1.10E 01 0.00E 01 1.11E 02 tsW 0.00E 01 7.00E 00 3.70t 01 7.40E 01 1.20E 01 0.00E 01 1.30t 02 3W 2.00t 00 6.00E 00 1.90t 01 5.00t 01 6.00E 00 0.00E 01 8.30E 01 WSW 1.004 00 5.00t 00 1.40E 01 2.70E 01 7.00E 00 0.00E 01 5.40t 01 W 1.00E 00 1.00t 00 2.00t 01 2.40t 01 3.00t 00 0.00E 01 4.90t 01 WWW 2.00t 00 4.00E 00 1.70E 01 2.20E 01 1.00C 00 0.00E 01 4.60E 01 kW 0.00E 01 6.00t 00 2.90E 01 1.70E 01 1.00t 00 0.00t 01 5.30t 01 NwW 4.00E 00 6.00t 00 9.10t 00 1.00t 01 0.00f 01 0.00f 01 2.90t 01 TOTAL 2.60t 01 1.37E 02 3.'38 02 3.69E 02 4.50t 01 1.00t 00 9.01t 02 PERICOS of CALM (HOURS): 1.40E 01 48
. o 1Aste 12. tape 7 of 7 JOINT WIND I'REQUENCY DISTRIllDTION DY STABILITY CLASS '
Data terlod: Ja%sry 1.1990 Deteatur 31, 1990 RTAlltitY CLAtt C VIND tof fD (M?M At 10 MittR ttytt D!tttflDN i3 47 8 12 13 18 19 24 *24 Y0tal W 1.1N 01 1.001 01 5.00t 00 0.00t 01 0.00t 01 0.00t 01 2.60t 01 kNt 3.20E 01 2.60f 01 1.00t 00 0.00t 01 0.001 01 0.00t 01 5.90t 01 ht 2.40t 01 1.40t 01 0.00t 01 1.00t 00 0.00t 01 0.00ta01 3.90t 0) thf 1.90t 01 1.001 01 0.00D01 0.00t 01 0.00t 01 0.00t 01 2.90t 01 E 1.30t 01 9.00t 00 1.00t 00 0.001 01 0.00E 01 0.00t 01 2.301 01 Elf 1.10E 01 1.50C 01 5.00E 00 0.00t.01 0.00t 01 0.004 01 2.10t 01 st 4.00t 00 1.508 01 1.00f 00 0.001 01 0.00E 01 0.00t 01 2.00f 01 !
tst 9.00t 00 1.50f 01 0.00t 01 0.00E 01 0.00t 01 0.001 01 2.40t 01 6 1.000 01 1.30t 01 0.00( 01 0.00t 01 6.001-01 0.00E 01 2.30t 01 stW 6.006 00 1.60E 01 0.00E 01 0.00E 01 0.00t 01 0.00E 01 2.20t 01 EV v.20f 01 2.50t 01 1.001 00 0.00E 01 0.00E 01 0.00t 01 3.80E 01 vtw 1.60t 01 1.40E 01 3.00t 00 0.00t 01 0.00t 01 0 not 01 3.30t 01 W 1.(DC 01 2.00t 00 2.00t 00 0.00t 01 0.00t 01 0.005 01 2.30t 01 WNW 1.20t 01 7.00t 00 4.00t 00 0.001 01 0.00t 01 0.001 01 3.30t 01 WW 3.00t 00 8.00t 00 4.00t 00 0.00t 01 n.00E-01 0.00t 01 1.50E 01 Nwv f.00t 00 B.00t 00 3.06t CD 1.00t 00 0.00t C1 0.00E C
- _ .LML .Q1 TOTAL 2.04t 02 2.12t 02 3.00E 01 2.00t 00 0.00t 01 0.00t 01 4.48t 02 PERIODS Of CALM (HOLRS): 5.00t 00 Elgo $Ptf D MPH AT. 60 Mtitt Ltytt gjytTION 1-3 47 8 12 13 1B 19 24 >24 h W 3.00t 00 6.00t 00 1.00t 01 8.00t 00 0.00E 01 0.00E 01 2.70E 01 WNE 4.00t 00 8.00t 00 5.00t 00 7.00t 00 0.00t 01 0.00001 2.40t 01 NE 2.005 00 6.00t 00 1.500 01 9.00t 00 0.001 01 0.00t 01 3.20t 01 Ekt 4.00t 00 8.00E 00 1.40t 01 4.00t 00 0.00t 01 0.00t 01 3.00E 01 t J.00t 00 6.00t 00 2.90t 01 8.00t 00 1.00t 00 0.00t 01 4.90t 01 tst 2.00t 00 1.00t 01 1.201 01 4.00t 00 0.00t 01 0.00t 01 2.80f 01 SE 2.00t 00 1.20E 01 4.00t 00 1.00f 00 1.00E 00 0.00[ 01 2.00t 01
$tt 9.00t 00 5.00t 00 2.001 00 1.50t 01 0.00E-01 0.00f 01 3.60t 01 s 3.00t 00 6.00t 00 1.00t 00 1.10E 01 1.00t 00 0.00t 01 2.20t 01
$3W 1.00t 00 6.00t 00 1.10E 01 1.70E 01 2.00t 00 0.00t 01 3.70t 01 SV 3.00t 00 5.00E 00 1.30t 01 1.30t 01 0.00E 01 0.00E Of 3.40t 01 VSW 1.00t 00 6.00t 00 1.00t 01 1.70E 01 2.00t 00 0.00t 01 3.60E 01 W 0.00E 01 1.00t 01 8.00E 00 9.00t 00 1.00t 00 0.00t 01 2.80t 01 WWW 0.00E 01 5.00t 00 1.00t 00 2.00E 00 0.00E 01 0.00t 01 8.00t 00 NW 2.00E 00 2.00( 00 9.00t 00 1.00t 00 0.00E 01 0,00E 01 1.40E 01 l
l FWW 4.00t 00 4.00f 00 5.00t 00 1.00t 01 0.00E 01 0.00t 01 2,300 01 l TOTAL 4.50t 01 1.05E 02 1.54f 02 1.361 02 8.00t 00 0.00t 01 4.48E 02 PEtt005 Of CALM (HOURS): 5.00t 00 49
l 1ABLE 13, Pope 1 of 4 ANNUAL AVERAGE RELATIVr. CONCENTRATIOND FOR HVAC STACK Data Period: Jerwary 1,1990 Demter 31, 1990 LNottAtt0 aND LNotPLETED PAetitut Airs (sec/mI )
KILoutitR$ > 0.2 0.8 1.8 4.0 8.05 12.5 17.3 N 2.35t 06 4.231 07 1.80t 07 6.47t 08 3.03t 08 2.03t 08 1.35t 08 NNE 2.20E 06 3.97t 07 1.69E 07 6.25t 08 3.07E 08 2.111 08 1.45t 08 NE 1.158 06 1.90E 07 8.16E 06 3.17t 08 1.57t 08 1.0er 08 7.411 09 ENE 1.12E 06 1.988 07 8.15t 08 2.94t 08 1.41E 08 9.57t-09 6.50t 09 1 1.09t 06 2.23t 07 9.79E 08 3.78t 08 1.91t ^8 1.33t 08 9.171 09 tst 8.92t 07 1.57t 07 6.74t 08 2.53E-08 1.24t 08 8.4BE-09 5.79t 09
$t 7.80t*07 1.475 07 6.70t 08 2.63l 08 1.33t 08 9.27t 09 6.40t 09 tst 5,9M 07 1.34t 07 6.79t 08 5.05t 08 3.68t 08 2.89t 08 2.19t 08 8 1.14t 06 1.91t 07 8.72t 08 3.40t 08 1.66t-08 1.13t 08 7.6BE 09
$$W 1.C9t 06 2.05t 07 9.05t 08 3.37t 08 1.58t 08 1.06t 08 7.06t 09 SW 6.92t 07 1.25t 07 5.471 08 2.10E 08 1.03t 08 T.06t 09 4.84t 09 VSV 4.94E 07 8.31t 08 3.65t 08 1.471 08 7.49t-09 5.26t 09 3.68t 09 W 5.75t-07 9.36E 08 3.98t 08 1.55t 08 8.00E 09 5.70E 09 4.06t 09 WWW 5.97t 07 1.00E 07 4.63t 08 2.021 08 1.06t 08 7.44t 09 5.19t 09 NV 9.99t*07 1.72t*07 7.79E 08 3.262 08 1.69t 08 1.191 08 8.28t 09 NNV 1.61t 06 2.88E 07 1.25t 07 4.71t 08 2.30E 08 1.57t M 1.088 08 K1t0Mtittl > 24.15 32.2 40.25 48.3 56.35 64.4 72.45 _
N 8.99t 09 6.64t 09 5.221 09 4.29t 09, 3.62E 09 3.13t 09 2.75t 09 NNE 9.83E 09 7.371 09 5.86E 09 4.85E 09 4.12t 09 3.58t 09 3.16t 09 NE 5.04E 09 3.78t 09 3.01t 09 2.49t 09 2.121 09 1.84t 09 1.63t 09 ENE 4.38E 09 3.27t 09 2.59t 09 2.14t 09 1.82t 09 1.58t 09 1.39t 09 E 6.30t 09 4.78E 09 3.84t 09 3.21t 09 2.76t 09 2.42t 09 -2.15t 09 tSE 3.91E 09 2.92t 09 2.321 09 1.91t 09 1.62t 09 1.4it 09 1.24t 09 tt 4.37E 09 3.30E 09 2.64t 09 2.191 09 1.87t 09 1.63t 09 1.s5t 09 SSE 1.618 08 1.26E 08 1.04E 08 8.82t 09 7.65t 09 6.7%t 00 6.04t 09 s 5.18E 09 3.87t 09 3.071 09 2.531 09 2.15E 09 1.87t-09 1.24t 09 CSV 4.69t 09 3.47t 09 2.74t 09 2.25E 09 1.90E 09 1.658-09 1.45t 09 SW 3.30E*09 2.4BE 09 1.98t 09 1.64t 09 1.40E-09 1.21E 09 1.07E 09 Vsw 2.56t 09 1.95t 09 1.571 09 s 31E 09 1.12t 09 9.81t-10 8.70E 10 W 2.86t 09 2.19E 09 1.77t 09 1.s9f. 09 1.28E 09 1.12t-09 9.92t 10 WWW 3.57t 09 2.70E 09 2.16t 09 1.7k 09 1.53t-09 1.33t-09 1.18E 09 NV 5.69t*09 4.30E 09 3.43t 09 2.85t ')9 2.43t 09 2.11t 09 1.87t 09 NwV 7.31t 09 5.49t 09 4.37t 09 3.62t t9 3.981 09 2.69E 09 2.371 09
. 50
h ik2Lt 13, Page 2 cf 4' l
ANNUAL AVERAGE RELATIVE CONCENTRATION 6 ,
70t WV4C 514CK Date Period: Jeruary 1,1990 Deceseer 31, 1990 ptCAftD Noett DAtts (sec/m3 ) ,
ritaMETER$ > 0.2 0.9 1.8 4.0 8.05 12.5 17.3 N: 2.35t 06 4.23t 07 - 1.80E 07 6.43t 08 3 Ant 08 2.00t 08 1.33t 08 Nut - 2.20t 06 3.971 07 1.68E 07 6.20t 08 3.00t 08 2.C3( 08 1.37t 08 ,
NE 1.1H 06 : 1.90E 07 8.14t 08 - 3 151 08 1.55t 08 1.0H 08 7.24t 09 tut 11.128 06 1.98t 07 8.1M 08 2.92t 08 1.39t 08 9.41t 09 6.35t 09
-t 1.09t 06 2.234 07 -9.68t 08 3.66t 08 1.78t*08 1.20t 08 8.006 09 Elf - 8.91t 07 ' 1.57t 07 6.7M 08 2.52t 08 1.22t 08 8.29t 09 5.58t 09 9t '7.00E 07- '1.44t 37 6.64E 08 2.58E 08 1.28t 08 8.71t 09 5.86E 09 .e sSt 5.9M 07 - 1.3M 07 6.69t 08 4.70t 08 3.14t 08 2.30t 08 1.58E 08 9 8 1.14t 06 1.90t 07 8.69t 08 3.38t 08 1.63C 08 1.11t 08 . 7.45t 09
$5W 1.09t 06 2.04E 07 9.02t 08 3.35t 08 1.56t 08 1.04E 08 6.88E 09 i
. SW 6.92t 07 ' 1.24t 07 5.46t 08 2.08t 08 1.01t 08 6.93t 09 4.72t 09 WsW ' 4.9M 07' 8.30E 08- 3.63E 08 1.46E 08 7.36t 09 5.145 09 3.57t 09 W- 5.74t 07' - 9.33t 08 3.97t 08 1.55t 08 7.84t 09 5.54t 09 3.90t*09 WWW 5.96t 07 1.00E 07 4'.61t 08 2.00E 08 1.04t 08 '- 7.252 09 5.00E 00 -
W' 9 904 07 1.72E 07 7.77t 08 3.2M 08 1.67t 08 1.16t 08 8.01t 09 ,
NNW , 1.616 06- 2.88t 07. 1.24t 07 4.68E 08 - 2.27t 08 1.55t 08 1.0*E 08
- g,LaMETras o 24.15 -32.2 40.25 48.3 $6.35 64 5 72.45
- N' i 8.76E 09 6.40E 09 -4.99t*09 4.06t 09 3.40E 09 2.91t+09 2.54t 09 NME i 9.028 09 6.59t 09 5.12t 09 4.14t 09 3.44t 09 2.94t09L 2.54t 09 j NE . '4.88t 09 3.62t 09 - 2.86t 09 2.34t 09' 1.97t 09 1.70E 09 1.49t+09 I ENE?' 14.23t 09= 3.13t C9 '2.46t Gv 2.00( 09 1.68E 09 1.45E+09 1.26E+09 !
t: .5.21E 09.; 3.75E 09- 2.87t 09 2.29t 09 1.88t 09 1.58t 09- 1.36E 09 tlE ; :3.70E 09 -2.72t 09 2.12t 09 1.72E 09 1.44t 09 1.23t 09 ' 1.07t 09
-st- '
'3.87t 09 2.83E 09 2.20E 09 1.78t 09- 1.48t 09 1.26t 09 1.09t 09 SSt i 1.02t 08 7.07E 08 15.15t 08 - 3.898 09-3.02t 09 2.40E 09- 1.94E 09i
$. 4.95t 09 3.65t 09 2.85t 09 2.32t 09. 1.95t 09 1.664 09 1.45E 09 '
$$W L ' :- 4.52t 09 3.31t 09 2.58E 09 2.10E 09 = 1.75t 09 1.50t 09- 1.30E 09
' SV L -3.18E 09 2.366 09 1.86t 09 1.52t 09 1.28t 09 1.10E 09 9.64E 10 - ,!
WlW e 2.45t 09. 1.84t =09 - 1.47r. vi 1.21t 09 1.02t 09 8.81t 10 7.72t 10
'W , 3: L2.706 09 2.05t 09 1.63t 09 ti35t OP :1.14t*09 9.85t 09- 8.62t*10 .i W .
4 04E 09 09 1. t 09 -
E NNW - 7.04t 09 .5.23E+09 4.11t 09 3.36t 09 3.83E 09 2.43t 09 2.121 09-s 51 -
1 A- i --
.,n.,- , m - - _ ,
. e TABLE 13, Page 3 of 4 s
ANNUAL AVERAGE Ri:LATIVE CONCENTRATIONS FOR NVAC $1FI Data Pericd Jaruary 1,1990 Dece@r 31,1990 OttAtto AND DEPLtito PaeticVlatts AND R AD10lMND (Sec/m3 )
[lLCNtitRS > 0.2 0.8 1.8 4.0 8.05 12 3 t Q, ,..
N 2.231 06 3.79t 07 1.56t 07 5.361 08 2.43t 08 1.59t 08 1.04t - %
NNE 2.0ft 06 3.55t 07 1.468 07 5.22t 08 2.49t 08 1.69t 08 1.131 08 NE 1.09t 06 1.71t 07 7.10E 08 2.671 08 1.2M 08 8.69t 09 5.s5t 09
[NE 1.Mt
- 06 1.771 07 7.02t 08 2.43t 08 1.12t 08 7.48t 09 4.97E M t 1.04t -06 2.021 07 8.581 08 3.18t 08 1.54t 08 1.04t 08 6.92t 09 Est 8.46t 07 1.41E 07 5.86t 08 2.93t 08 1.01t 08 6.83t 09 4.571 09 st 7.t1E 07 1.33t 07 $.92E 08 2.26t 08 1.10E 08 7.50t 09 5.03t 09 st! 5.691 07 1.231 07 6.13t-08 4.63t 06 3.33t 08 2.56t 08 1.88t 08 9.28t 09 6.19t 09 '
S 1.08t 04 1.T't*07 7.69t 08 2.92t 08 1.381 08 stW 1.04t 06 1.84t 07 7.94t 08 2.85t-08 1.28t 08 8.36t 09 5.44t 09 CW 6.57t 07 1.121 07 4.80E 08 1.7BE 08 8.47t 09 5.73t 09 3.86t 09 WsV 4.68t 07 7.471 08 3.19t 08 1.25t 08 6.22t 09 4.31t 09 2.98t 09 W 5.45t 07 8.39t 08 3.45t 08 1.30E 08 6.54E 09 4.60E 09 3.231 09 WW 5.67t 07 9.02E 08 4.07t 08 1.74t 08 8.98t 09 6.24t 09 4.29t 09 NV 9.49t 07 1.54t 07 6.82t 08 2.80E 08 1.43t 08 9.94t 09 6.82E 09 NW 1.53t 06 2.581 07 1.08t 07 3.95E 08 1.88t 08 1.27t 08 8.50t 09 QLCNtitR$-** 24.15 32.2 40.25 48.3 _,
56.35 64.4 72.45 W 6.68t 09 4.81tr09 3.70E 09 2.98t 09 2.471 09 2.09t 09 1.81t 09 NNE 7.48t 09 5.47E 09 4.24t 09 3.43E 09 2.85t 09 2.421 09 2.09t 09 NE 3.89E 09 2.86t 09 2.24t 09 1.821 09 1.53t 09 1.31E 09 1.13t 09 ENE 3.26t 09 2.38t 09 1.85t 09 1.50E 09 1.25t 09 1.06t 09 9.20E 10 t 4.52t 09 3.271 09 2.52t 09 2.01t 09 1.66t 09 1.40t 09 1.19t 09 Est 3.01E 09 2.20E 09 1.71E 09 1.38t-09 1.15E 09 9.77t 10 8.45t 10 st 3.31t 09 2.41t 09 1.871 09 1.51E 09 1.25t 09 1.06E 09 9.15t 10 SSE 1.32E 08 9.91t 09 7.79t 09 6.31t 09 5.23E-09 4.41t 09 3.771 09 - i S 6.08E 09 2.98t 09 2.32t 09 1.89t 09 1.57t 09 1.34t 09 1.17E 09
$$W A 511 09 2.53t 09 1.95t 09 1.56t 09 1.31t 09 1.11t 09 9.59t 10 SW l.57t 09 1.90E 09 1.49t 09 1.21t 09 1.021 09 8.73t 10 7.60t 10 WW 2.C4t 09 1.53t 09 1.22t 09 1.00E 09 8.49t 10 7.32t 10 6.41t 10 W 2.24t 09 1.706 09 1.36t 09 1.12t 09 9.51C 10 8.21t-10 7.20t 10 WNV 2.90E 09 2.16t 09 1.701 09 1.39E 09 1.17E w 1.00t 09 8.76E 10 NW 4.61E 09 3.43E ')9 2.70t 09 2.20E 09 1.85t 09 1.59t 09 1.39E 09 NNW 5.661 09 4.17E 09 3.27t 09 2.67E 09 2.24t 09 1.92C 09 1.671 09
- 52
l.
1 ABLE 13, Pope 4 of 4 ANNUAL AVERAGE RELATIVE CONCENTRATIONS FOR NVAC STAtt Data Period: Jamary 1,1970 Decenter 31, 1990 bttAYt0 AhD ttPLEttD PAttttUt Atts AND P AD10ttelWtt (DEPeslilDW)
(m*2)
QLtutifts > 0.2 0.8 1.8 4.0 8.05 12.5 17.3 N 2.94t 08 6.3BE-09 2.20t 09 5.358 10 1.87t 10 1.0't 10 6.18t 11 WWE 2.99t 08 6.44t 09 2.21t 09 5.36t 10 1.87t 10 1.07t 10 6.15t 11 NE 1.34t 06 3.21t 09 1.11t 09 2.71t 10 9.60E 11 5.621 11 3.30t 11 EWE 1. M 08 2.84t 09 9.73t 10 2.36t 10 8.23t 11 4.74t 11 2.73t 11 E 1.61t M 3.64E 09 1.27t 09 3.12t 10 1.09t 10 6.31t 11 3.64t 11 Elf 1.321 06 2.89t 09 1.00t 09 2.471 10 8.62t 11 4.97t 11 2.86t 11
$t 1.42E 08 1.31t 09 1.15t 09 2.8bt*10 9.85t 11 5.71t 11 3.32t 11 stt 9.93E 09 2.4t*09 9.571 10 2.47t 10 8.81E 11 5.15t 11 3.021 11 8 1.564 08 3.71t 09 1.35t 09 3.41t 10 1.20t 10 6.97t 11 4.03t 11
$$W 9.721 09 2.46t 09 9.38t 10 2.47t 10 B.75t 11 5.07t 11 2.94t 11 SW 6.76t 09 1.70E 09 5.26t 10 1.60t 10 5.69t 11 3.31t 11 1.935 11 WSW 4.58t 09 1.121 09 4.b2D10 1.02t 10 3.63t 11 2.12t 11 1.25t 11 W 5.222 09 1.24t 09 4.38t O 1.09t 10 3.84t 11 2.24t 11 1.31t 11 WW 4.90E 09 1.29009 4.72E 10 1.21t 10 4.3!3 11 2.55t 11 1.51t 11 NW 8.02t 09 2.06t 09 7.46D 10 1.88t 10 6.74t*11 3.96t*11 2.34t 11 PWW 1.54t 06 3.45t 09 1.20E 09 2.908 10 1.04t 10 6.00t 11 3.47t 11 ritoMtites > 24.15 31 2 40.25 48.3 56.35 64,4 72.45 W 3. Sit 11 2.32t 11 1.67t 11 1.275 11 1. Cit 11 8.26t 12 6.90t 12 kWE 3.49D11 2.30D11 1.65t*11 1.26t 11 1.00t 11 8.24t 12 6.92t 12 NE 1.94t 11 1.31t 11 9.571 12 7.41E 12 5.97t 12 4.94t 12 4.16t 12 tut 1.56t 11 1.03t 11 7.39D12 5.63D 12 4.48t 12 3.66t 12 3.06t 12 L k.088 11 1.371 11 9.83t 12 7.46E 12 5.88E 12 0 78D 12 3.96D12
($t 1.63C 11 1.08D11 7.721 12 5.871 12 4.64E 12 3.7C9 12 3.14t 12 St i.918 11 1.27E 11 9.19E 12 7.02F 12 5.5Bt 12 4.55t 't 3.79E 12 CSE 1.76t*11 1.18t 11 8.53t 12 6.53D12 5.16t 12 4.22E 12 3.50E 12 1 2.32t 11 1.54E 11 1.118 11 8.48t 12 6.73D 12 5.49t 12 4.57t 12 tsW 1.69f 11 1.1?t 11 8.1tt 12 6.19E*12 4.92t 12 4.01t 12 L34t 12 SW 1.12t 11 7.475 12 5.43E 12 4.19D 12 3.35E 12 2.76E 12 2.3M 12 vsw 7.28t 12 4.90t*12 3.58D12 2.TTD12 2.22D12 1.84E 12 1.55t ?2 W 7.59t 12 5.081 12 3.71E 12 2.87t 12 2.31E 12 1.92t*12 1.62t 12 WNW 8.90E 12 6.03t 12 4.43t 12 3.41D12 2.75t 12 2.27t*12 1.90t 12 WW 1.37t 11 9.29t 12 6.8M 12 5.35t il 4.19t 12 3.44t 12 2.87t 12 NNV 1.99t 11 1.32t 11 9.54t 12 7.30D12 5.82D12 4.77t 12 4.00D12 53 ,
1 1
SEC ON 6 JOS E M EASU livi E N"S Ab J ASS ESS vie N ~S e
TADLE 14 MAXIMUM
- OFFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUDLIC Data Period: January 1, 1990 - December 31, 1990 DOSE **
Source 1st Otr 2nd Otr 3rd Otr 4th Otr A. Waterborne Effluents (mrem) Organ 0.00E+00 3.58E-03 1 2.41E-02 1 1.53-03 1 2
Total Body 0.00E+00 3.28E-04 2 2.29E-03 2 1.50E-04 B. Airborne Effluents
- 1. Iodines and 2.11E-03 3 5.90E-04 4 6.43E-04 5 3.50E-04 4
Particulates organ 6
Total Body 7.55E-05 6 4.96E-06 6 8.65E-06 6 2.14E-05
- 2. Noble Gases: Gamma 6.BBE-04 0 0.00E400 0.00E+00 0.00E+00 Beta 1.30E-03 8 0.00E+00 0.00E+00 0.00E+00 C. Direct Radiation (mrem) _0.00 7 0.00 7 0.00 7 0.00 7 THERE ARE NO OTHER URANIUM FUEL CYCLE FACILITIES WITHIN 8 KM OF CPS
- " Maximum" means the largest fraction of the corresponding Appendix I doso design objectivo.
- The numbered footnotes on the following page briefly explain how each maximum dose was calculated, including the organ and predominant pathway (s).
l t
! 54 l
l
Eqp.1Aptes_for Table 14
- 1. Dose to the adult 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 thyroid via the inhalation, cow milk, and ground-plane pathways. Calculated at 4.5 miles North using methtdology contained in the CPS ODCM.
- 4. Dose to the infant thyroid via the inhalation, cow milk and ground-plane pathways. Calculated at 4.5 miles North-Northeast using methodology contained in the CPS ODCM.
- 5. Lose to the infant thyroid via the inhalation, cow milk and ground-plane pathways. Calculated at 4.5 miles South-Southwest 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-Northeast using methodology contained in the CPS ODCM.
- 7. Ditect radiation dose component from reactor plant operations in Jor.formance with 40CFR190.
- 8. Dose is independent of age group. Calculated at 0.87 miles North using methodology contained in the CPS ODCM.
55 ,
l DOBE8 TO MEMDERfi OF TJ1E_f_qDLIC WITHIN THE_ SITE DOUNDARY CPS Technical Specification 6.9.1.7 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 gareous effluents shall be used for determining the gaseous pathway doses. Within the CPC site boundary there are seven areas which are open to members of IIl the public as identified by CPS ODCM Table 3.4-4 (soo rigure 8):
A road at 0.495 kilometers (0.3 miles) in the SE sector
- Agricultural acreage 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 kilomotors (1.5 miles) in the WSW sector A residence at 2.736 kilometers (1.7 miles) in 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.
56
I e .
l FIGURE 8 l '
AREAS WITHIN THE CPS SITE BOUNDARY OPEN TO MEMDERS OF THE PUBLIC 2P l
1
)
CLINTON
/ g e - -
a m-
%~ , ,.--
,,,,, WAPELLA i MAROA , ..., .. .. ,,,.... ... ......
. ......i.... ...... 1. m .. .. . .
a
.......t....m....................
, ......... .. m ., .. ... .......... .... ...,..
+
1
- 6' b ~I 8
1 E1
" e
- G -
p N C .P.S.
nicON en WELDONBR %, ,
{PIATTCD.
';CISCO >
7?
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o
.: e FARMER
~
c5" CITY 3%
DELAND f 1, 4 TO '
- CHAMPAIGN 74 57
i
.. . 4 r
t 1'
TABLE 15 CALCULATED DOSES TO MEMBERS OF THE PUSLIC DURING USE OF THE ROAD IN THE SOUTHEAST SECTOR WITHIN TME CPS SITE BOUNDARY Data Period: January 1, 1990 - December 31, 1990 ,
Egggsure Pathway Qrgans Dose (arem) plume
- total body 4.50E-06 skin 2.42E-05 ground plane
- total body 6.01E-05 skin 7.06E inhalation; four highest organ domest child thyroid 3.60E-06 teen thyroid 3.46E-06 adult thyroid 3.05E-06 infant thyroid 2.88E-06 i
- Doses via these pathways are not dependent upon
+
age-group..
L h
1 w
I l;
58
_ _ , ,.-,4_._.,_...- ~ _ . _ . _ _ . - . . _ . _ _ .. . . . . . . _ . . . . , _ _ _ _ _-- _ _ u._ _... .._ . _._._.J
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TABLE 16 i CALCULATED DO8ES TO MEMBERS OF THE PUBLIC DURING USE OF THE AGRICULTURAL ACREAGE i IN-THE SOUTM-SOUTHWEST SECTOR WITHIN [
THE CPS SITE BOUNDARY i Data Period: January 1, 1990 - December 31, 1990 i
Ernosure Pathway QIgang Dose farem) ,
plume
- total body 2.63E-07 skin 1.97E-05 ground plane
- total body 5.50E-05 i skin 6.46E-05 inhalation; four highest organ doses: ,
child thyroid 4.52E-05 ,
teen thyroid 4.25E-05 infant thyroid 3.79E-05 ,
adult thyroid 3.63E-05 l
- ! Doses-via these pathways are not dependent upon age-group.
l l"
59
- l. . . . , . . . . _ - . _ . ...,..-_._,m-_.,--,_...-._. . - . - . . , ..
TADLE 17 CALCULATED DODES TO MEMDERS OF THE PUDLIC DURING USE OF CLINTON LAKE IN THE NORTHWEST SECTOR WITHIN THE CPD SITE BOUNDARY Data Period: January 1, 1990 - December 31, 1990 EXD2 Dure Pathway Orcans Dose (mromi plume
- total body 0 skin 0 ground plane
- total body 1.50E-05 skin 1.77E-05 inhalation; four highest organ dosest child thyroid 6.00E-05 toen thyroid 5.61E-05 adult thyroid 4.01E-05 infant thyroid 3.75E-05
- Dosos via theno pathways are not dependent upon age-group.
60
TABLE 18 CALCULATED DOSES TO MEMDERS OF THE PUDLIC DURING USE OF THE DEPARTRENT OF CONDERVATION RECREATION AREA IN THE EAST-SOUTHEAST DECTOR WITHIN THE CPD SITE DOUNDARY Data Period: January 1, 1990 - December 31, 1990 Exposure Pathway QIgang Dose (mrem) plume
- total body 0 skin 0 ground plane
- total body 1.43E-06 skin 1.69E-06 inhalation; four highest organ doses:
child thyroid 5.53E-06 teen thyroid 5.05E-06 infant thyroid 4.87E-06 adult thyroid 4.19E-06
- Doses via these pathways are not dependent upon age-group.
61
$ ;.e,., , .,. .
TABLE 19 CALCULATED DOSES FOR THE RESIDENTS IN THE SOUTMWEST SECTOR WITRIN TME CPS SITE BOUNDARY Data Period: January 1, 1990 - December '31, 1990
~
4 Ernosure Pathway Organs Dome faren) plume
- total body 2.97E-06 skin 6.76E-05 1
ground plane *' total body 3.34E-04 I
skin 3.94E-04
' inhalation; four. highest organ dosest child thyroid 2.39E-05 ;
teen thyroid 2.24E-05 infant thyroid 2.00E-05 adult thyroid . 1.92E-05
- Domes via these pathways are not dependent upon age-group..
I 62 i 4
i
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m 1.- ;
)
i
)
a i
TABLE 20 g i
CALCULATED DORES FOR THE RESIDENTS 1
-IN THE WEST-80UTNWEST SECTOR WITMIN THE CPS SITE BOUNDARY Data Periodt- January 1, 1990 - December 31, 1990 ,
y L
, t Exposure Pathway graans Dgga faren) ,
e p3ume* total body 5.60E-06 -t skin 3.97E .
- ground plane
- total body 9.23E-05 }
skin 1.09E-04 j inhalation; four highest organ dosest-
'l ^
child thyrvid 7.63E-06 taan thyroid 7.19E-06 -)
infant thyroid 6.34E-06 ;
adult thyroid 6.20E-06 j i
'L i
- Doses via these pathways are-not' dependent upon age-group.
I h 5
?
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i 3
l l-I 63 s
._,,-,-..-.,-...~...J._.-._,,..___._,._.-__.,_,.,,,--.._-...,_...,...,_..,,..-
TABLE 21 CALCULATED DOSES FOR Tl!E RESIDENTS IN TIIE 80UTit-800Tl! EAST SECTOR WITIIIN TIIE CPS SITE DOUNDARY Data Period: January 1, 1990 - December 31, 1990 Exoosure Pathway Organg Dose (mromt plume
- total body 4.76E+05
- skin 1.85E-04 ground plane
- total body 1.56E-04
. skin 1.83E-04 inhalation; four highest organ doses child thyroid 1.85E-05 teen thyroid 1.79E-05 adult thyroid 1.51E-05 infant thyroid 1.46E-05
- Doses via these pathways are not dependent upon age-group.
d 64
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t S EC~ Os 7 C.
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CA_CU_A~0s V AN UA_ AN J
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C11ANGEB TO Ti!E OFFSITE DOSE CALCULATION MANUAL hND.,_TilC_BOLID WADTE PROCESS CONTROL PAOGRAM In accordance with CPS Technical Specification 6.14, changes to the CPS ODCM shall be reported in or concurrent with the Somiannual Radioactive Effluent Release Report. No changes were mado during this reporting period.
In accordance with CPS Technical Specification 6.13, changen to the Solid Wasto Process Control Program are no longer required to bo reported in the Semiannual Radioactivo Effluent Releaso Report. This Technical Specification change was implemented on October 16,1990.
65
I S EC~ O N 8
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NG CON J ~ O s 70R 0 3lE RAT ON R E 3O R~S A sl]
OJCV 0 3 E R A~ O N A _
R EQU R EiV E f~S
a
. e . I LIMITING CONDITION FOR OPERATION REPORTS &
3 ODCN OPERATION REQJIREMENTS Prior to October 16, 1990, the liquid and gaseous effluent j monitoring instrumentation channels that were inoperable for I greater than 30 days were reported in the Semiannual l Radioactive Effluent Release Report in accordance with Clinton Power Station Technical Specification 3.3.7.11 and 3.3.7,12. Inoperative conditions for effluent .
instrumentation channels entered after October 16, 1990 are !
now referred to as offsite Dose calculation Manual operation !
Requirements'(00R), in accordance with CPS ODCM operation Requirements 2.7.1 and 3.9.2.
October 16, 1990 was the effective date'for implementation of programmatic controls for Radiological Effluent Technical
. Specifications in the administrative controls section of the
- Technical Specifications-and the relocation of procedural details'of Radiological Effluent Technical Specifications to the CPS ODCM, per Nuclear Regulatory Cormission (NRC)
During this reporting period, four inoperability conditions occurred which require reporting, and one previously '
reported inoperable condition was r'estored. The following
-is a dar.tiption of these conditions: 4 Case 1 L Information:
Operability Requirements. Technical Specification
-Table 3.3.7.11-1.2.a .
Date Entered:
5-29-90 at 1230 Date Restoreda 9-14-90 at 2336 ;
4 Explanation:
On May 21,.1990, the calibration of the plant service water process radiati.on monitor, IRIX -
PR036, was initiated. During the performance of this calibration, problems involving acceptance criteria and procedural deficiencies were encountered. An action plan was. initiated on July 16,- 1990 to troubleshoot the monitor as well as .
~ develop new or verify old acceptance criteria.
This1 condition was reported-in the last Semiannual .
Radioactive Effluent Release Report. .
Acceptance criteria and procedural deficiencies were corrected, the calibration was completed,'and the monitor was returned to service on September
- 14, 1990 at 2336 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.88848e-4 months <br />.
P 66
- -en.,-, ...~.n-- -
.-c--- -,ew.. ,,~+-<-n.m .nn~n-,.,~ n r ,-, ~ , w en w e + n -.o r , n n-w-,,.c,,,,--sm-~, ,, ,- y ,--
I Case 2 Information:
Operability Requirementt Technical specification Table 3.3.7.11-1.1.a Date Entered: 7-5-90 at 1130 Date Restored: As of 12-31-90, the instrument had not been reatored to an operable condition Explanation -. -
The Liquid Radwaste Discharge Process Radiation Monitor, ORIXPR040, was declared inoperable on July 5, 1990 at 1130 when it failed the source check just prior to a liquid discharge. The cause of this failure was due to high background counts in the sanple chamber and adjacent system piping.
Efforts were made to lower the background radiation bl'uecontar::nating portions of the monitor communicating with the waste stream.
Efforts were also made to shield the detector from adjacent system piping which contributes to the overall background counts. During the effort to lower background radiation, the calibration for the instrument expired.
During early October, an in vitro calibration (i.e., detector alignment and some troubleshooting), was initiated to eliminate interference from the high background condicions that still existed. The remainder of the calibration is to be completed upon the arrival of a standard detector shield housing in which the detector will be placed. Roceipt of the shield is expected in February 1991, Appropriate connections will bo made at the monitor's microprocessor with sufficieht lengths of cable to locate the assembly an adequate distance from the high background area to facilitate the completion of the calibration.
Upon completion of the calibraticn, the high background radiation readings will have to be reduced to acceptable levels prior to restoring the monitor to service.
It should be noted that two independent samples are analyzed and independent verifications of release rate calculations and discharge line valving are performed prior to initiating any radioactive liquid discharge, when ORIXpR040 is inoperable. These actions are in accordanco with the Remedial Requirements list'ed in Table 2.7-1 of the ODCM.
67 ,
. 4 Jhe monitor is expected to be rencored oy March 31, 1991. The information pertaining to the restoration.of this Limiting Condition for Operation (LCO), that is ODCM Operatfon Requirement, will be reported in the next Semiannual Radioactivo Effluent Release Roport.
Case 3 Informationt Operability Requirement: Technical Specification Tablo 3.3.7'.12-1.3.a Date Entered: 8-5-90 at 1345 Date Restored: 9-14-90 nt 1300 Explanation The main condensor off-gas hydrogen analyzer "A" was declared inoperablo on August 5, 19 'J O at 13 4 5 due to a flow obstruction at the discharge valve, IN66-F005A. Approximately one veck was spent evaluating whether a permanent or temporary fix
.was in order. Temporary Modification 90-36 van initiated to run tubing to the "B" ane.lyzer di,1 charge line. The cafety evaluation for the modification took approximately two weeks to complete. The, modification was 1.nstalled on August 27, 1990. On Augdst 29, *990 1 a calibration was attempted but no sample flow could be obtainud. Troubleshooting showed inlet valve, IN66-F083A, ta be obstructed. On August 21, 1990 the surveillance was resstarted using an alternato suctior, flowpath, but this attempt failed due to electronic prob 1 cms. These problems were corrected on Septembar 5, 1990, and the calibration was completed on September 6, 1990.
The 30-dai LCO action tino limit was exceedoC on September 4, 1990 at 1345. Temporary Modification 90~41 was installed to bypass "A" Analyr.or inlet valve on September 13, 1990 and the monitor was declared operable to September 14, 1990.
Thore were two primary reasons for excuoding the 30-day LCO action time limit. First, a significant amount of time, at loost one week, was spent evaluating whether to pursue a temporary or a pernanent fix. Only after this was decided could the maintenance work order be written nad parts be ordered. The requirement for a second te.mporary modification, 90-41, wan the action that ultimately forced CPS to exceed the 30-day LCO action time limit.
68
_ _ _ _ _ _ - ____ __ ___._m___________s-- _ _____mm____ _ _ _ _ _ ____
Case 4 Information: '
Operability Requirement. Technical Specification Table 3.3.7.12-1.!!.g Date Entered 8-11-89 st 1004 Dato Rostorodt 12-29-50 rf. 2205 e Explanation:
On August 3, 1989, OUIX-PR051 Chr.nnel 1, the Ettndby Gas Treatment System stecA flow monitor, vn s declared inoperable due to the instrument c/ cling in and out of alarm statuo during porlods
.I no flow. This condition was repertod in the ,
1 tst lemiannusi Radioactive Effluent FSlonso RF ort.
Sin m the last taport, extensivo engineering evT Temporary acs,'Jations ficqtion 90-61 have been was worked conducted. during November and -
Dh* mber 1990 to install the necessary electrical gloands. Prior to rostoring the moniu:Or to service, a problem with the low flow hisem associated with the flew transmitter hac *.e be corrected. The problem occurs during 131 r ow conditions, causing the monitor to cycl 6 $o and mit of low flow annunciations. This probinu was eGErncted, and the monitor was restored to barvice on b.womber 29, 1990 at 220b.
Cave S Informations OperabJ 11ty Requiremontt ODCM Table 2.7-1.2.c Date Entored: 11-10-90 at 0000 Date'Restorad As of ,'.2-31-90, the instrument .'aad not boon restored to an operable condition.
Explanations
.%e Fuol Pool llant Exchanger "A" Service Water Ws untion Monitor, IRIX-PR004, was declared Anop rable on 11-10-90 at 0000 because the eight Tn month slibration had not boon perfoamed.
The ca.tbratio, did not take placo because the task wau -onsidered a lower priority than the ongoing ente,311ng outagefuork.
Upon initiatit1-calibration of the monitor during December 1990, the bachground radiation levels l were found tv be elevated due to contributions from surrounding system components. This cordition has e,*, onded the timo required to calibrato the norttor. The background readings 69 v-- ' - -f T pr P . 4 y--- gw pw -y -.m-- p y e w - * -
t will have to be reduced to .cceptable levels prior to restoring the monitor to service.
' The calibration is scheduled for completion by February 28, 1991. The information pertaining to the restoration cf this LCO will be reported in the next Semiannual Radioactive Effluent Release Report.
9 4
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'1 1
MAJOR CHANGES TO RADIOA9TIVE WASTB TREATM:NT BYSTfdia In accordance with the CPS ODCM, licensee-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 chang'es to the Waste Treatment Systems were reviewed and ap1, roved during this reporting period.
l l
1 71
i S EC~~ O s 10 s EW _OCA~~ O s S OR JOS E CALCU _A" Ob Ah J/O R ENV RO s k E CA_ v O N ~~O R NG p
i i
A 1
- g NEW LOCATIONS FOR DOSE CALCULATION AND/OR ENVIRONMENTAL MONITORING In accordance with CPS ODCM, new locations for dose calculations and/or environmental monitoring identified by i the Annual Land Use Census shall be reported in the Semiannual Radioactive Effluent Release Report. No new environmental monitoring locations were identified in the latest Annual Land Use census completed on September 26, 1990. However, indicator sample-location CL-17 was installed and ultimately implemented on October 22, 1990.
Clinton Lake bottom- sediments are collected at this location. CL-17'is location in the southwest sector at a distance of 3.5 miles from the HVAC stack at CPS.
The following is a summary-of the changes identified by the (
1990 Annual Land Use Census.
1.0 Nearest Residence
- a. Replace K. Scott residence with=K. Dittman at 0.9 mile in NNE sector,
- b. No response from C. Groves residence at 2.5 miles .
in ENE sector. {
c.- -Replace R. Evans-residence with Larry Jarosch and '
4 John Punk at 1.7 miles in SSE sector.
- d. Replace C. Webb residence with Riaz_& Farida Baber at 3.0 miles in SSW sector.
- e. Replace J. Brias residence with Beth Burns at 1.6 mile-in WNW sector.
2.0 Garden Census s
- a. Identified 60-gardens in the 16 sector within a 5 mile-radius, of which 39 produced broad leaf vegetation!(spinach,. lettuce, cabbage and chard).
Specifically broad leaf vegetation was identified
-for this surveillance. -In most cases tomatoes, sweet corn and beans were grown in_all sectors.
- b. Changes in census locations for the nearest garden
. identified in 9'of the 16 sectors are shown in the following table.
1989 Census Location 1990 Census Location NNE 0.9 mile (K. Scc' " 2.0 miles (J. Spencer)
NE 1.2 miles-(H. P_rsimus) 2.0 miles (T. Spencer)
EL 1.1 miles (F. L. Reynolds) 1.5 miles (G. Defebaugh)
SE 14.6 miles (J. Weaver) NONE IDENTIFIED SSE 2.7 miles (M. West) NONE IDENTIFIED S 3.0 miles (L. Disney) NONE IDENTIFIED SSW 3.0 miles (C. Webb)- 3.2 miles (L. Sugg)
WSW 2.3 miles (J. Holland) 3.4 miles (S. Best)
NNW 1.6 miles-(S. Stapleton) 2.3 miles (G. R. Cope) 72
I s
RAJ O _OG CA _
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7 s ILLI L 5 ,
ER 5
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_ _ - _ _ _ _ _ _ _ __ _ _ _ _ - _ _ __--