U-601382, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1988
| ML20235S189 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/31/1988 |
| From: | Holtzscher D ILLINOIS POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| U-601382, NUDOCS 8903060197 | |
| Download: ML20235S189 (119) | |
Text
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0 CLINTON POWER STATION SEM/ ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT July 1,1988 - December 31,1988 6
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1A.120 ALLIN0/8 POWER 00MPANY l
IP ' CLINTON PONER STATION. P.O. BOX 678. CLINTON. ILLINOIS 61727 February 24, 1989 Docket No. 50-461-U. S. Nuclear Regulatory Commission 1 Attention: Document Control Desk Washington, D.C. 20555'
Subject:
Clinton Power Station Semiannual Radioactive Effluent' Release Report
Dear Sir:
Attached is the Semiannual Radioactive Effluent Release Report for
-Clinton Power Station.(CPS) for the period'of July.1, 1988 - December 31, 1988. This submittal is provided in accordance with-the require-ments of section;6.9.1.7 of the CPS Technical Specifications.
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If you have any questions, please contact me.
Sincerely yours,
.h. l D. L. Holtzscher Acting Manager -
Licensing and Safety SFB/pgc Attachment cc: NRC Clinton Licensing Project Manager f NRC. Resident Office i Regional Administrator, Region III, USERC -
1 Illinois Department of Nuclear Safety gf[
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' _S 4 'M TABLE-OF CONTENTS SECTION PAGE <
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- 1. Summary . . . . . , . . . . .- . . . . . . . . . . . . 6
- 2. Introduction. . . . . . . . . . . . . . . . . . . 8
- 3. Supplemental Information. '
. . . . . . . . . . . . 18-
- 4. Effluent and Waste Disposal Data. . . . . . . . . 25
- 5. -Meteorological Data and Dispersion Estimates. . . 36
- 6. Dose' Measurements and Assessments . . . . . . . . 69
- 7. Changes to_the_Offsite Dose Calculation Manual and-the Solid Waste Process Control.
Program . . . . . . . . . . . . . . . . . . . . . 82
- 8. Limiting Condition for Operation Reports. . . . . 90
- 9. Major Changes to Radioactive Waste Tr'eatment Systems . . . .- . . . . . . . . . . . . . . . . . 95
- 10. New Locations for Dose Calculation and/or Environmental Monitoring. . . . . . . . . . . . . 97 ,
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l LIST OF TABLES PAGE {
Table 1: Airborne Effluents - Summation of All )
. Releases . . . .. . . . . . .- . . . . . . . 26 Table 2: Airborne Effluents . . . . . . . . . . . . . 27 Table 3: Waterborne Effluents - Summation of All Releases . . . . . . . . . . . . . . . . . .. 29 Table 4: Waterborne Effluents . . . . . . . . . . . . 30 Table 5: Solid Waste and Irradiated Fuel Shipments. . 33 Table 6: Estimated Total Errors Associated with.
Effluent' Measurements. . . . . . . . . . . . 35 Table 7: Meteorological Data Availability . . . . . . 38 Table 8: Classification of Atmospheric Stability. . . 42 Table,9: Joint Wind Frequency Distribution by Stability Class. . . . . . . . . . . . . . . 43 Table 10: Average Annual Relative Concentrations . . . 57 Table 11: Maximum Off-Site Doses and Dose <
Commitments to Members of the Public . . . . 70 !
I Table 12: Calculated Doses to Members of the Public l During Use of the Road in the Southeast -
Sector within the CPS Site Boundary. . . . . 75 l Table 13: Calculated Doses to Members of the Public ;
During Use of the Agricultural Acreage in the South-Southwest Sector within the CPS Site Boundary. . . . . . . . . . . . . . . . 76 Table 14: Calculated Doses to Members of the Public During Use of Clinton Lake in the Northwest i Sector within the CPS Site Boundary. . . . . 77 Table 15: 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 . . . . . . . . . . . . . . . . . . 78 2
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t' PAGE Table 16: Calculated Doses for the Residence in the :
Southwest Sector within the CPS Site Boundary . . . . . . . . . . . . . . . . . . . 79 {
Table 17: Calculated Doses for'the Residence in the West-Southwest' Sector'within the CPS Site Boundary . . .. . .. . . . . . . . . . . . 80 Table 18: Calculated Doses for the Residence in the '
South-Southeast Sector within the CPS Site Boundary . . . . . . . . . . . . . .. . . . 81 r
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LIST OF FIGURES PAGE Figure 1: CPS Airborne Effluent Release Points. . . . . 10 Figure 2: CPS Waterborne Effluents Release Pathway. . . 11 Figure 3: Effluent Exposure Pathways. . . . . . . . . . 16 Figure 4: Clinton Power Station Monthly Liquid Radwaste Discharge Total. . . . . . . . . . . 31 Figure 5: CPS Wind Rose: 10-meter. . . . . . . . . . . 39 Figure 6: CPS Wind Rose: 60-meter. . . . . . . . . . . 40 Figure 7: Pasquill Stability Class Prevalences. . . . . 41 Figure 8: Areas Within the CPS Site Boundary Open to Members of the Public. . . . . . . . . . . 74 4
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LIST OF ATTACHMENTS
.i ATTACHMENT A: ODCM Revision 4, Affected'Fages !
ATTACHMENT B: Solidification-Vendor Procedure / Document Approval Cover Sheet e
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e SECTION 1
SUMMARY
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SUMMARY
l The Semiannual Radioactive Effluent Releasa Report is a detailed listing of all radioactive releases (both gaseous and liquid) from the Clinton Power Station (CPS) and the ;
resulting radiation doses for the period from July 1 through j December 31, 1988. This report includes a detailed )
meteorological section which provides the weather history of the area during the time of the releases. This information is used to calculate the dose to the public. This report also includes a summary of the amounts of radioactive >
material contained in solid waste that is packaged and I shipped for offsite disposal'at federally approved burial )
facilities. In addition, this report serves as a medium for l notifying the US Nuclear Regulatory Commission (NRC) staff of changes to CPS's offsite Dose Calculation Manual (ODCM) and Solid Waste Process Control Program (PCP), and exceptions to the CPS effluent monitoring program which must be reported per Technical Specifications 3.3.7.11 and ,
3.3.7.12.
The NRC requires that nuclear power stations be designed, constructed, and operated in.such a way that the amount of radioactive material in effluent releases to unrestricted areas is kept As Low As Beasonably Achievable (ALARA). To assure these criteria are met, the NRC has established limits governing the release of radioactivity in effluents.
The maximum radiation dose delivered to the inhabitants of the area surrounding CPS, due to radioactivity released from the station, is very small. The radiation dose to people in the area is calculated for each release using the concentration of radioactive material and the weather conditions at the time of the release. These doses were only a small fraction of the limit for the most exposed member of the public.
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i SECTION 2 INTRODUCTION se m
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. 1 INTRODUCTION Clinton Power Station is located in Harp Township, DeWitt l County approximately six miles east of the city of Clinton j in east-central Illinois. Clinton Power Station consists of l a 985 MWe gross electrical power output boiling water !
I roactor. The reactor and generating units were supplied by l General Electric, Sargent and Lundy Engineers served as architect-engineer, and Baldwin Associates was the constructor.
Construction of CPS began in the mid 1970's. Fuel load began in September of 1986 with initial criticality achieved l on February 27, 1987. Commercial operation commenced in i
April 1987 and the reactor reached 100% power for the first time on September 15, 1987. l
' Airborne effluents are released from CPS via two gaseous effluent release points to the environment: the Common Station Heating, Ventilation, and Air Conditioning (HVAC)
Stack and the Standby Gas Treatment System (SGTS) Stack (see Figure 1) . Each release point is continuously monitored and a program of periodic sampling and analysis is conducted as.
specified in the plant Technical Specifications. Liquid ,
effluents from CPS are released in batch mode and are sampled and analyzed prior to release. Liquid effluents, i variable from 10-60 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 Seal-Well prior to entering the 3.4 mile discharge flume to Lake l Clinton (see Figure 2). j 9
- - - - - _ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ b
CPS AIRBORNE EFFLUENT RELEASE POINTS Figure 1 1
TURBANE BUR. DING RADWESTE AND
' ROOF EL 876'0* NACHDE SHOP BUILDING ROOF EL 781'0*
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170'0* / 206'0* y. ,
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SGTS VENT AIR TOP CONTAINMENT CONC. EL 927'0* -
, c0wrROL sus.osso /
,,,, I ,, ROOF EL 847'0*
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3, GASEOUS EFFLUENT RELEASE POINT CHARACTERISTICS 1 i
HVAC EXHAUST STACK SGTS EXHAUST STACK RELEASE POINT HEGHT (m) 61 61 BUILDING HEGHT(m) 58 58 !
RELEASE POINT GEOMETRY DUCT APE RELEASE point AREA (m8) 11.15 0.15
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RELEASE PolNT DIAMETER (m) 3.77* 0.44 ANNUAL AVERAGE FLOW RATE (fr8/ min) 237,000 4000 VERTICAL EXIT VELOCITY (m/sec) 10.02 12.49 10 i
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7 CPS WATERBORNE EFFLUENTS RELEASE PATHWAY Figure 2 PLANT SERVICE WATER
( \
RW BLDG. p (AT LEAST 5000 GPM)
(UP TO 25.000 RE GALLONS / BATCH)
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LIQUID RADWASTE DISCHARGE LINE -
(10-60 OR 50-300 GPM) h RADIATION MONITOR ALARWTRIP SETPOINT CALCULATED BASED ON EACH BATCH ISCTOPIC ANALYSIS AND ;
DiumON Flow l
>4 ISOLATION VALVE .
TERMINATES RELEASE ON HIGH RAOlATION, HiGH RELEASE Ftow ram. OR Low @ COMPOSITE SAMPLER R M N N RAM COU.ECTS APPROXIMATELY 20 ml EVERY 00 MINUTES FROM THE DISCHARGE FLUME FOR MONTHLY ANALYSIS SEALWELL 0 LAKE PLANT CIRCULATING CLINTON l WATER l (0-567,000 GPM) DISCHARGE FLUME 3.4 MILES l
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Reculatory Limits The NRC requires nuclear power plants to be designed, constructed and operated in such a way that the radioactivity in effluent releases to unrestricted areas is kept ALARA. To assure these criteria are met, each license authorizing nuclear reactor operation includes Radiological Effluent Technical Specifications (RETS) governing the release of radioactive effluents (Code of Federal Regulations, Title 10, Part 50, Appendix I). The RETS designate the limits for release of effluents, as well as the limits for doses to the general public from the release of radioactive liquids and gases. Keeping releases within these operating limits is a demonstration that the ALARA principle is being met.
The dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas e
is limited to:
Less than or equal to 3 mrem per year to the total
,, body.
-and-Less than or equal to 10 mrem per year to any
, organ.
The dose to air due to release of noble gases in gaseous
, effluents is limited to:
Less than or equal to 10 mrad per year for gamma radiation.
-and-Less than or equal to 20 mrad per year for beta radiation.-
The dose to a member of the general public from iodine-131, tritium and all particulate radionuclides with a half-life greater than eight days in gaseous effluents is limited to:
Less than or equal to 15 mrem-per year to any organ.
These ALARA limits are a fraction of the dose limits a established by the Environmental Protection Agency (EPA).
In its Environmental Dose Standard of 40CFR190, the EPA established dose limits in the vicinity of a nuclear power ~
plant. These dose limits are:
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.Less-than or equal to 25 mremiper yearJtofthe J
, total body.
Less;than~or' equal to175 mrem per. year.to.the
-thyroid.
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!' -and-Less'than or equalcto-25 mrem per year'to any other. organ. J!
See Section 3.for more information on regulatory limits.
Processina and Monitorina-Effluents are. strictly controlled'at CPS to ensure radioactivity released to.the environment is minimaliand' !
does'not' exceed release limits. . Effluent controls include the. operation of radiation monitoring systems in the' plant i and offsite. environmental sampling.and-analysis programs.
In-plant radiation monitoring systems'are used.to provide a
. continuous indication of radioactivity and are.also used~to.
z collect particulate and'radiciodine samples. These samples
-are analyzed in aLlaboratory-to identify,the specific .
- l concentration of-radionuclides being released.- ' Sampling and y' 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 radioactivity concentrations that may contribute to human radiation exposure. The program consists of two. phases, preoperational.and operational. During the preoperational phase of the .;
program, the baseline'for the local' radiation environment l was established. The operational phase of'the program '
includes the objective of making confirmatory measurements ,
to verify that the in-plant controls for the release of radioactive material are functioning as designed.
Assessment of the operational impact of CPS on the environment is based on data collected'since the reactor started.
EXDosure Pathways Radiological exposure pathways are the means by which people may become exposed to radioactivity released from nuclear facilities. The major pathways of concern are those which 13
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^ could:cause the highest calculated radiation dose. .These- '
pathwaysiare' 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 1which will be defined by wind speedLand wind direction at.the time of the release. This- i information is used.to evaluate how the radionuclides will be, distributed'in the' area. .The.most important factor in evaluating the exposure pathway is the use of the environment by the people living around CPS. Factors.such as location.of homes in the area, use of cattle'for milk and.
Lmeat, and the growing,of gardens for vegetable consumption are very important considerations in evaluating exposure . ;
pathways. Figure 3 illustrates the various. environmental '
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.
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- Dose Assessment !
Whole body radiation involves the exposure of all organs in the human body. Most background exposures are of this form.
Radionuclides enter the body by. 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, j The total dose to organs from a given radionuclides also dependsLon the amount of activity in the organ and the amount of time that the radionuclides remains in the body.- ;
Some radionuclides remain for very short periods of time due to'their rapid radioactive decay and/or elimination rate 3 from the body, while'others may remain longer. f 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 surrounding CPS and takes into account'the location of the nearest residents, vegetable gardens producing broad leaf vegetables, and milk and meat I animals in all sectors. The calculated dose also uses the l
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concept of a_" maximum' exposed individual"'and " standard 1 man", and;the-maximum use' factors for'the environment, such as how much. milk a person drinks and how much air a person breaths-in.a y. ear. I m I See Tables 11-18 of Section 6 for more detailed information I
on dose to the public.
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Gaseous 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 and 2 of Section 4 for more detailed I information on gaseous effluents.
Licuid Effluents Radioactivity in liquid effluents consists of radioactive fission and activation products, tritium and entrained noble gases.
See Tables 3 and 4 of Section 4 for more detailed information on liquid effluents.
Solid Waste Shioments In order to reduce the radiation exposure to personnel and ,
1 maintain the ALARA concept, the NRC and the Department of Transportation (DOT) have established limits on the types of l radioactive waste and the amount of radioactivity that may be packaged and shipped offsite for burial or disposal ~. To ensure that CPS is complying with these regulations, the types of waste and the radioactivity present are reported to the NRC.
See Table 5 of Section 4 for more detailed.information on solid waste shipments.
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SECTION 3 SUPPLEMENTAL INFORMATION M
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. g I. . REGULATOR LIMITS w
i A. ; Gaseous Effluents L 1
- 1. In accordance.with. Title ~10 of the, Code of; Federal Regulations,,Part 20, the maximum; *;
permissible concentration's for gaseous i effluents: shall not exceedo theLvalues given in 10CFR20, AppendixEB,f Table II, Column 1..
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To ensure.these concentrations are~not exceeded, dose l rates due to. radioactive 3 materials released in gaseousteffluents'from j the site tofareas at and beyond the site boundary shall be. limited to the following:-
.a. Noble gases - Less than or equal'to1500: i mrem / year to:the total body.
Iass than or equal to.
3000 mrem / year to thel skin.
- b. Iodine-131, iodine-133,. tritium and all-radionuclides in particulate' form with half-lives greater than eight days: ,
Less than or equal to 1500 mrem / year to any organ.
- 2. In accordance with Title 10 of the Code of Federal Regulations, Part 50,. Appendix I,. air ,
dose due to noble gases released in gaseous !
effluents to. areas at.and beyond the. site-boundary shall ium limited to'the'following: ;
a '
a .' Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for' beta radiation during any calendar quarter.
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- b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.
- 3. In accordance with 10CFR50, Appendix I, dose 1 to a member of the public (from iodine-131, iodine-133, tritium and all ~
radionuclides in particulate form with half-lives greater than eight days) in gaseous effluents released to areas at and beyond the 19
4 site boundary shall be limited to the following:
- a. Less than or equal to 7.5 mrem to any organ, during any calendar quarter.
- b. Less than or equal to 15 mrem to any organ, during any calendar year.
B. Liquid Effluents
- 1. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulations, Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries per milliliter total activity.
- 2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be timited to:
- a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.
- b. Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ during any calendar year.
II. MAXIMUM PERMISSIBLE CONCENTRATION A. Gaseous .
- 1. The maximum permissible concentrations (MPC) for. gaseous effluents are specified in Title 10 of the Code of Federal Regulations, Part 20, Appendix B, Table II, Column 1. However, the MPC's of 10CFR20 are not utilized directly for limiting gaseous effluents. CPS Technical Specifications establish requirements to limit the release rate of effluents such that discharges of gaseous ~
radioactive material will not result in the dose rates, to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA either within or outside the SITE BOUNDARY, higher than those which 20
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[06 Lwould occur?if average' annual concentrations exceeded MPS~ limits. 'The maximum permissible E.
, dose' rates for gaseous releases are ,
- .\
'J a.- Technical: Specification ; 3.11'. 2.1. a (Dose I
>v rate'at and beyond the site boundary i from gaseous effluents inLthe form of l noble _ gases). ,
14ss.than or equal to 500 mrem / year to the total body.- .l; Less than or_ equal to 3000 -
mrem / year to.the skin.
1 y b. Technica1' Specification 3.11.2.1.b (Dose [
. rate at and beyond the site-boundary :l' t from gaseous effluents':in the-form of iodine-131, iodine-133, tritium and all radionuclides in' particulate form with_
( half-lives greater than eight' days).
Less than or equal to 1500 l 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 c all cases. -For l dissolved and entra'ined noble gases the MPC e of 2.0E-04 microcuries per milliliter is
_. applied. This'MPC iszbased'on the Xe-135 MPC fr. air (submersion dose) converted to an equivalent concentration in water as
' discussed in the International Commission on Radiological Protection (ICRP) , Publication 2.
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III. AVERAGE ENERGY The CPS Technical Specifications' limit the dose equivalent rates due to the release of fission and activation products 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 as described ~in Regulatory Guide 1.21, " Measuring,1 Evaluating, and Reporting Radioactivity in Solid Wastes -
and Releases of Radioactive Materials in Liquid and l' Gaseous Effluents from Light-Water-Cooled Nuclear Power' Plants", is not applicable.
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IV. MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY A. Fission and Activation Gases i 1. Gas samples are routinely collected monthly ,
and as required by CPS Technical l Specification Table 4.11.2-1 and 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 demineralized water. The collected samples are distilled and analyzed by liquid scintillation. The tritium release was calculated for each release point from the measured' tritium concentration, the volume of sample, the tritium collection efficiency, and the stack exhaust flow rates.
B. Iodines Iodine is~ continuously collected on a charcoal cartridge filter via an isokinetic 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 release point are averaged for the duration of the sampling period and these results along with isotopic concentrations are used to determine total activity released during the time period in question.
C. Particulate Particulate are continuously collected on a filter paper via an isokinetic sampling assembly on each release point. Filters are normally exchanged once per week and analyzed on an HPGe system. Flow rates and total activity are determined in the same manner as for iodines.
D. Waterborne Effluents Each tank of liquid radwaste is sampled and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative sample is obtained.
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Samples are'analyzedtonian HPGe system and" release permits'are generated-basedJon the values obtained-from the isotopicfanalysis and the most recent ,
values foritritium, grossialpha, iron-55, strontium-89.and strontium-90.- An aliquot: based-on' release; volume is saved and'added tofcomposite containers..The. concentrations _of composited-isotopes..and Lthe: volumes of the releases -
associated.with these composites establish.the proportional relationships that are then utilized for calculatingLthe total ~ activity released.for. !
these isotopes.-
V. ' BATCH RELEASES A. Liquid .
3rd otr 88 4th otr 88 )
- 1. Number of batch 1 releases: 26 1
- 2. . Total 1 time period-for ._ 1
- batch releases: 2.314E+03 8.5E+01 min.'
min. !
'3. Maximum time period for batch release: '1'.52E+02 min. 8.5E+01 min.
- 4. Average time .;
period for ;
- batch release: 8.9E+01 min' . 8.5E+01 min. '
- 5. Minimum. time-period for batch release: 5.1E+01 min. ~8.5E+01 min'.
- 6. ' Average stream
. flow during '
periods'of i
' release: 1.147E+05 1pm 7.571E+04' lpm
- 7. Total waste volume: 2.247E+6 8.406E+04
liters liters
- 8. Total dilution -
volume: 2.65E+8 6.44E+06 liters liters 1
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'1. .- Number'of.
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. period for .
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batch: releases: .N/A N/A 1
- 3. , Maximum time period for.
batch release:- N/A N/A 4.- - Average' time period.for.
L - batch release: ,N/A N/A.
'5. . Minimum' time period-for ,
h t;
- batch release:- N/A. N/A. j l
'VI. ABNORMAL RELEASES a .
There have been no abnormal releases of radioactive material to the environment during this-reporting period.
t 6
l l
- I
)
24 l
1 e
d BECTION 4 EFFLUENT AND WASTE DISPOSAL DATA l
t l
i i
s e
25
w . . .
<~
n);*: '
1 c
l TABLE 1-1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
' AIRBORNE EFFLUENTS --SUMMATION OF ALL RELEASES Data Period: July 1, 1988 - December 31, 1988
'Nuclide Catecorv Unit Third Quarter Fou'rth Quarter A. Fission & Activation Gases 1.-Total Releasel Ci <1.35E+03 <1.97E+03
- 2. Average Release !
Rate'for Period- uCi/sec <1.70E+02 . <2.48E+02
- 3. Percent of .
Applicable Limit. .c % <7.72E-02 -<1.02E-01 B. Iodine-131
- 1. Total Release Ci .27.99E-05 <9.90E-05 28.82E-05 <1.28E <
- 2. Average Release t -
j u . Rate for Period uCi/sec- 21.01E-05 <1.24E-05 21.11E-05 <1.61E-05 .
- 3. Percent of-
> Applicable Limit % 24.13E-05 <5.12E-05 24.56E-05 <6.64E-05. 1 i
C.~ Particulate. 1!
- 1. Particulate Released -l with' Half-lives >8 .
, Days Ci 21.96E-03 <7.87E-03. 25.27E-02 <1.59E-02* l 2.. Average Release o D
- Rate for Period uCi/sec 22.47E-04 <9.90E-04 26.63E-03 <2.00E-03* .!
I
- 3. Percent of-Applicable. Limit % 18.05E-06 <1.12E-02 25.73E-04.<1.13E-02*
-4.JGross Alpha-Activity Released Ci 22.30E-05 <3.09E-05 28.05E-07 <8.78E-06
.D. Tritium
- 1. Total Release Ci 23.32E+00 <4.71E+00 22.41E+0'O <3.35E+00
- 2. Average Release
. Rate for Period uCi/sec 24.18E-01 <5.93E-01 23.03E-01 <4.22E-01'
- 3. Percentlof Applicable Limit % 21.19E-04 <1.69E-04 28,64E-05 <1.20E-05 l
1 l Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level (CL). The second value (<) includes detected activity plus the Lower Li'mit of Detection !
values of any samples in which activity was not detected at the 95% .
CL. _
- -Reported values include Sr-89 and Sr-90 values based on third quarter j 1988 sample _ analyses and fourth quarter 1988 ventilation exhaust j
. rates.
26 i
.i.
\
l TABLE 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
( AIRBORNE EFFLUZNTS (Curies)2 Data Period: July 1, 1988 - December 31, 1988 Nuclide Third Quarter Fourth Ouarter
'A. Gases Kr-85 <1.23E+03 <1.82E+03 Kr-85m <5.95E+00 <5.42E+00 Kr-87 <1.38E+01 <1.37E+01 Kr-88 <1.71E+01 <1.76E+01 Xe-133 <1.67E+01 <1.42E+01 Xe-135 <5.42E+00 <5.82E+00 Xe-135m <1.36E+01 <2.70E+01 Xe-138 <3.45E+01 <5.61E+01 Others:
Ar-41 <9.28E+00 <1.02E+01 Total <1.3SE+03 <1.97E+03 '
B. Iodines I-131 27.99E-05 <9.90E-05 28.82E-05 <1.28E-04 I-133 21.38E-04 <1.65E-04 22.04E-04 <2.26E-04 16.93E-05
. I-134 <2.98E-04 <4.89E-02 Total 22.18E-04 <5.62E-04 23.62E-04 <4.93E-02 C. Particulate with Half-liv ~es >8 Days Sr-89 <3.44E-03 <3.38E-03*
Sr-90 <3.44E-03 <3.38E-03*
Cs-134 <3.35E-05 <1.72E-04 Cs-137 <4.25E-05 <1.98E-04 Ba-140 <1.41E-04 <6.06E-04 2 Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level. The second value (<)
includes detected activity plus the Lower Limit of Detection values of any samples in which activity was not detected at the 95% confidence _
level.
- Reported values are estimated based on third quarter 1988 composite analyses and fourth quarter 1988 ventilation exhaust rates.
27
i
'o TABLE 2 (Cont'd) :
SEMIANNUALRADIOACTIVEEFFLUENTRELEgSEREPORT AIRBORNE EFFLUENTS (Curies)
Data Period: July 1, 1988 - December 31, 1988 Nuclide Third Ouarter Fourth Ouarter Others:
1 Cr-51 1.83E-03 4.75E-02 Mn-54 29.22E-05 <1.44E-04 21.80E-03 <1.83E-03 Fe-59 <9.42E-05 22.45E-04 <7.33E-04 Co-58 23.20E-05 <8.33E-05 21.38E-03 <1.41E-03 Co-60 25.48E-06' <8.16E-05 21.76E-03 <2.30E-03 Zn-65 <1.08E-04 <6.18E-04 Ce-141 <4.45E-05 <1.63E-04 Ce-144 <2.19E-04 <1.08E-03
. Total. 21.96E-03 <7.87E-03 25.27E-02 <1.59E-02 t
i l
2- Notation: Thefirst value presented (2) includes only activity positively detected at the 95% confidence level. The second value (<) '
includes detec ted activity plus the Lower Limit of Detection values of
.any samples la which activity was not detected at the 95% confidence _
level.
O Reported values are estimated based on third quarter 1988 composito analyses and fourth quarter 1988 ventilation exhaust rates.
28
l 4 h TABLE 3 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i WATERBO'NE EFFLUENTS - SUMMATION OF ALL RELEASES Data Period: July 1, 1988 -' December 31, 1988 Ep_q).ide Cateaorv Unit- Third Ouarter Fourth Ouarter A. Fission & Activation
' Products
- 1. Total Release 3 -
Ci' 28.58E-02 <1.11E-02 25.54E-04 <1.19E-04
- 2. . Average Diluted Concentration uCi/ml 23.24E-07 <4.19E-08 28.60E-08 <1.85E-08 3.' Percent of Applicable Limit % 22.50E-01 <3.13E-01 23.87E-01 <3.00E-01 B. Tritium
- 1. Total Release Ci 1.89E+00 9.17E-02 :
- 2. Average Diluted ]
Concentration uCi/ml 7.13E-06 1.42E-05
- 3. Percent-of-Applicable Limit ! 2.38E-01 4.75E-01 l
C. Dissolved and i Entrained Gases \
- 1. Total. Release Ci '
22.82E-06 <3.52E-02 <9.31E-04
- 2. Average Diluted N Concentration uCi/mls 21.06E-11 <1.33E-07 <1.44E-07 !
- 3. Percent of Applicable Limit % 25.32E-06 <6.65E-02 <7.22E-02
- D. Gross Alpha Radioactivity Released Ci <5.73E-06 8.75E-07 E. Volume of Waste gal. 5.94E+05 2.22E+04 Released liters 2.25E+06 8.41E+04 F. Volume o'f Dilution gal. 7.01E+07 1.70E+06 l l
Water Used liters 2.65E+08 6.44E+06
~
3 Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level. 'The second value (<)
includes' detected activity plus the Lower Limit of Detection values of' any samples in which activity was not detected at the 95% CL.
29
- _ - _ _ _ _ _ _ _ _ - _ _ _ = _ _ _ _ _ _
p ,
i e TABLE 14
- i 'SEMIANNUALRADIOACTIVE'EFFLUENTRELEAgE
- REPORT '
WATERBORNE EFFLUENTS (Curies)
L ~ Data Period:' July 1~, 1988.-' December. 31,-1988
- i. ,
.Nuclide Third Ouarter ' Fourth Ouarter A. Tritium. .. 1.89E+00 9.17E-02 B. Fission &iA'cti- .
.vation Products
.Na-24 7.43E-04 Cr-51 -7.54E-02 1.54E-04 Mn-54 23.58E-03 <3.60E-03 21.19E-04 Co-58 ~21.54E-03 <1.57E-03 '21.80E-05 Co-60 22.02E-03_ <2.08E-03' 21.91E-04 l '
Fe-55 -8.99E 3.36E-05*
Fe-59 <3114E-04 ,
<1.29E-05 Zn-65 <2.99E-04 <
'1.61E-05
.As-76 6.98E Sr-89-- 9.88E-04 3.69E-05*
.Sr 3.82E-05 1.43E-06*
Mo-99 11.54E-04 <9 80E-04. <3. 2 8E- 05 Tc-99m 3.56E-04 Sb-122 2.41E-05
'Sb-124 3.60E-05 I-131 <1.04E-04 <2.68E-06 I-133 <1.21E-04' s3.22E-06 I-135 <3.03E-04 <1.26E-05 Cs-134 <1.46E-04 <4.88E-06 Cs-137 <1.39E-04 <6.07E-06 .
Ba-140 <4.25E-04 <1.14E-05 La-140 <9.88E-05 <1.84E-06 Ce-141 <1.88E-04 <2.89E-06 Ce-144 <7.62E-04 <1.19E-05 Total - >8.58E-02 -<1.11E-02 25.54E-04 <1.19E-04 C.-Dissolved and-Entrained Gases Kr-85' <2.83E-02 <8.44E-04 ,
Kr-85m <1.35E-04 <1.75E-06 Kr-87 <2.62E-04 <7.72E-06 Kr-88 <3.78E-04 <8.84E-06 Xe-133 <3.10E-04 <4.47E-06 Xe-133m <8.16E-04 <2.25E-05
'Xe-135 22~.82E-06 <1.00E-04 <2.64E-06 'l Xe-135m <1.30E-03 <1.14E-05 !
.Xe-138- <3.62E-03 <2.72E-05 l Total' >2.82E-06 <3.52E-02 <9.31E-04
.4 Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level. The second value (<) l includes detected activity plus'the Lower Limit of Detection values of. l any samples in which activity was not detected at the 95% CL.
- Reported. values are ostimated based on third quarter 1988 sample analyses and fourth quarter 1988 discharge volumes.
30
4 FIGURE 4 CLINTON POWER STATION i MONTHLY-LIQUID RADWASTE DISCHARGE TOTAL Data Period: 1988 300,000 4
260,000 -
E 220,000 - / j
/
/
g
- ?; 6.~t /
g180,000 - WI g : =:' ' ((
o l
- I I
140,000 - f
- I \
100,000 - ;,: 9 e E
/ I f
~
l 60,000 -
\
\
m.rl 20,000 -
. . m x. .
l N'
1 I I I T T I I I I T t l JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC -
1988 31 l
_ _ _ _ _ _ . l
..- i
.y ,
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS During this. reporting. period there were~ nineteen-(19) radioactive waste shipments and no; irradiated fuel shipments from. CPS as reported in Table-5. Ailfwaste shipped in this
, reporting period was classified.asLClass A. In addition, CPS Technical Specifications,-section 6.9.1.7 requires-reporting of the-following information for solid waste- j shipped;offsite during the report period.
- 1. Container volume: -7.50 cubic feet, i
- 2. -Total curie quantity: 57.5 curies as determined by dose-to-curie methodology land sample concentration methodology estimates. 3 u
- 3. Principal radionuclides: See Table 5, A.2 for' listing l' of measured radionuclides.
- 4. Source of waste and processing-employed:. Spent resins, filter sludges and evaporator concentrates, solidified ;
in bitumen. Compacted and non-compacted dry active waste.
- 5. Type of. container:- 17E 55-gallon drums and'17H 55-
. gallon drums.
- 6. Solidification agent or absorbent: Bitumen l
1 ii 32
TABLE 5 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Data Period: July 1, 1988 - December 31, 1988 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total
- 1. Tvoe of Waste Unit Eeriod Error, %
- a. Spent resins, filter m3 1.22E+02 sludges, evaporator Ci 5.52E+01 30.0 bottoms, etc.
- b. Dry compressible m3 1.05E+02 waste, contaminated Ci 2.32E+00 30.0 equip, etc.
- c. Irradiated components m 3 0.00E0 control rods, etc.
Ci 0.00E0 0.0
- d. Other (describe) m3 0.00E0 Ci 0.00E0 0.0
- 2. Estimate of major nuclide composition (by type of waste)
, (Curiesl
- a. Fe-55 66.883% 3.69E+01 Mn-54 12.572% 6.94E+00 C-14 9.858% 5.44E+00 Co-60 6.620% 3.65E+00 Co-58 1.303% 7.19E-01 Ni-63 1.297% 7.16E-01 Cr-51 1.121% 6.19E-01' Other 0.345% 1.90E-01
- b. Cr-51 39.097% 9.08E-01 Fe-55 36.142% 8.39E-01 Mn-54 15.560% 3.61E-01 Co-60 5.035% 1.17E-01 Co-58 3.328% 7.73E-02 Other 0.838% 1.95E-02 l c. None N/A N/A
- d. None N/A N/A -
i
'C' TABLE 5 (Cont'd)
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Data Period: July 1, 1988 - December 31,'1988
- 3. Solid Waste Disposal l Number of Shioments Mode of Transportation Destination 19 Truck Richland, WA B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shioments Mode of Transportation Destination None N/A N/A C. TECHNICAL SPECIFICATIONS CLASSIFICATION REQUIREMENTS -
N/A i
l i
.-=
34
______2__ __ _ - ._
)
TABLE 6 )
f .' SEMIANNUAL RAD'I:,1 ACTIVE EFFLUENT RELEASE REPORT ,
ESTIMAT7S TOTAL ERRORS ASSOCIATED l WITu EFFLUENT MEASUREMENTS Data Period: July 1, 1998 - December 31, 1988 Measurement Averace % Error Larcest % Error
, 1. Airborne Effluents A. Activation & Fission Gases Xe-135 i20.4 124.8 B. Iodine-131 31.1 146.9 i C. Particulate Na-24 24.9 125.5 Cr-51 126.5 132.9 Mn-54 30.5 38.2 Tc-99m 24.5 25.9 D. Gross Alpha 24.8 +34.6 E. Tritium i20.8 21.0 F.' Beta Emitters-Sr-89 i21.7 25.0 Sr-90 , 115.8 25.0
- 2. Waterborne Effluents i
-A. Activation & Fission Products Cr-51 i20.4 i33.8 Mn 54 12.6 17.2 Co-58 115.2 20.1 Co-60 il2.4 16.7 B. Tritium 1.1 1.2 C. Gross Alpha 135.5 148.3 i
D. Beta Emitters I Sr-89 i 2.3 i 6.1 Sr-90 1 3.8 114.7 Fe-55 i 6.2 12.6-I 35
SECTION 5 i
12 METEOROLOGICAL DATA AND DISPERSION ESTIMATES 1
dee 36
_ _ - - - _ _ _ _ _ - - _ - _ - _ _ _ _ _ . i
C 1
METEOROLOGY AND DISPERSION DATA l
The meteorological monitoring program began at the Clinton Power Station site on Apri' 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 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- and 60-meter levels. Dew-point is measured at the 10-meter level with an aspirated dew-point sensor.
Precipitation is measured at ground level by a tipping bucket rain gauge. 1 l
Meteorological monitoring instruments have been placed on the Clinton Power Station microwave tower at the 10-meter level to act as a backup to the existing meteorological tower.
Clinton Power Station meteorological data is transmitted to the Main Control Room via a dedicated telephone line. There the signals are received and converted to a 4 to 20 milliamp' signal and fed individually to a microprocessor and chart recorders. The microprocessor is part of the Clinton Power Station Radiation Monitoring System. Meteorological data is available via the microprocessor in the Main Control Room, Technichl 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 jbint 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.
37
TABLE 7 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT METEOROLOGICAL DATA AVAILABILITY Data' Period: 1988 1 I
l Percent of Vali' Parameter Hours Darina Fetlod
- 1. Wind Speed ;
- a. 10-meter Sensor 97%
- b. 60-meter Sensor 96% l
- 2. Wind Direction
- a. 10-meter Sensor 97%
- b. 60-meter Sensor 96%
- 3. Temperature
- a. 10-meter 97%
- b. 60-meter 96% '
- c. Temperature Difference (10m-60m) 97%
- 4. Percent of hours for which valid 96.9%
10-meter Wind Speed, Wind Direction,
& Delta Temperature were available
- 5. Percent of hours for which valid 95.6%
60-meter Wind Speed, Wind Direction,
& Delta Temperature were available i
1 l-
~
l l
l- '
38
o .i a '
?{. E . i; -l i
"'*y .-
- - 2 FIGURE 5 6
CPS WIND ROSE: 10-METER Data Period:: 1988 N
s- 4.8% -
-NNW NNE '
4.7% 5.5% :I NW' NE
-6.8%. 6.0%
I
=
- -l ENE )
4.4% .:
f WNW-8.3%
'x 'n i. ,
(
Z 7.5% N W N#'I '
WSW 6.9% -
"4 Nk7
- "# 4.6%-
I i
/ ,- / Y
/ ESE
- i-.
3.3%
WIND SPEED KEY SSW SSE 10.7% 5.8% >24 MPH 8.9% 19-24 MPH -
13-18 MPH h, 8-12 MPH 4-7 MPH 39 [7 i.3 MPH
- s -
t J .. 1 FIGURE 6 CPS WIND ROSE: 60-METER '
Data Period: 1988 i N '
5.4%
NNW NNE .
5.6% 6.4% '
NW NE )
6.8% 4.6% !
l M l
= !
E ENE ;
3.9%
WNW i 7:2% i f
's 's '
i l3ul j 7.1% I' EIIIIIIIV///M E/dIISI -
\ 3.1%
/
,s .
WSW 6.1%
ESE 2.8%
=
=
= '
=
=
4.8%
WIND SPEED KEY SSW SSE 9.9% ~-
5.9% >24 MPH j i I 9% h 19-24 MPH _
13-18 MPH h 8-12 MPH 4-7 MPH 40 h I-3 MPH
)l l ! :
i!U e l e
l b
b% a e % % e%
e%
l a2 t 3 9 b4 s%ba3% l l t
s8 n6 2 e02 ta2 b3 a n2 U 2 s 3 t 2 l S1/S1 t0 U/
yu s
r l y/ n/ s s
/ ba/s s
r t r l ysr ys
/
- l eo eru Ur u u Su o .o teu l
eur mH areHtH t
olyo l aH l yH aH r
o mo s
r _
r t e H e _
g7 d e0 e0 h t0 h0 _
tr9 d 2 g4 u9 5 t3 r t x3 o2 i8 l e8 i7 l o0 x7 e E2 M2 S2 N1 S1 M1 E8 M 1 ) l l
) 0 S
E ['
N ['
[
hMf/, // '
[
1 t
C a N n -
R i o -
t T
u A bre)s NV i OE I
t sl u TR ia D V A P 88 '
\
/
y y T S 9 cl N
n u r S S1 e
u o y
qH 7R LA:do \ e EE Ci s N ,
F7 r9 R
U W r e
4 G OYP ,
d n (8 FPTaIt I
- i W
La '
NID OB t
i n
o TA J '
NT n o
I S L d CL N e
L I
s a
, U B Q
S i A
P
/ -
. l TABLE'8 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CLASSIFICATION OF ATMOSPHERIC STABILITY
- 1 Stability Pasquill Temperature Change Classification Categories Std. Dev.5 (degrees) w/ height (OC/100m) iExtremely unstable. A 25.0' -1.9 i Moderately unstable B 20.0 -1.9 to -1.7
! .Slightly unstable C 15.0 -1.7 to -1.5 h-. Noutral 'D 10.0 -1.5 to -0.5-1 'Slightly stable E 5.0 -0.5 to 1.5 Moderately stable F 2.5 1.5 to 4.0
-Extremely stable G 1.7 4.0 i
.i l
L l
5 Standard deviation of horiziontal wind direction over a period of 15 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The values shown are the averages for each stability classification.
42
TABLE 9, Page 1 of 14 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Data Period: 1988 STABILITY CLASS :A ELEVATION : 10 METERS WIND SPEED (HPH) AT 10 METER LEVEL 13 : 47 : 8 12 : 13 18 : 19 24 : >24 : TOTAL :
N : 6.00E 00 : 3.70E 01 : 4.30E 01 : 2.00E 01 : 1.00E 00 ! 1.00E 00 : 1.08E 02:
NNE! 1.30E 01 : 5.50E 01 : 5.00E 01 : 5.40E 01 : 1.10E 01 : 5.00E 00 : 1.88E 02:
NE : 1.50E 01 5.50E 01 : 4.10E 01 : 4.50E 01 : 1.70E 01 : 1.00E 00 : 1.74E 02:
___ ._______________________________ ...... ____________________________________ i ENE! 1.10E 01 : 4.00E 01 3.80E 01 : 6.00E 00 : 2 00E 00 : 0.00E 01 9.70E 01: )
E : 5.00E 00 2.80E 01 : 1.30E 01 : 8.00E 00 : 0.00E-01 : 0.00E-01 : 5.40E 01:
ESf; 9.00E 00 3 60E 01 : 3.30E 01 : 7.00E 00 : 0.00E 01 : 0.00E-01 : 8.50E 01:
SE : 1.60E 01 : 6.80E 01 : 4.80E 01 : 1.20E 01 : 1.00E 00 : 0.00E-01 : 1.45E 02:
SSE: 2.10E 01 : 6.80E 01 : 5.10E 01 : 2.00E 01 : 5.00E 00 2.00E 00 : 1.67E 02:
_____.m... ______________. _____________________________ __ .. _________________
S : 1.90E 01 : 8.30E 01 : 8.10E 01 : 4.10E 01 3.00E 00 : 4 00E 00 : 2.31E 02:
SSW: 6.00E 00 : 6.30E 01 : 8.90E 01 : 5.50E 01 : 4.00E 00 : 1.00E 00 2.18E 02:
SW : 4.00E 00 : 1.90E 01 : 2.90E 01 : 4.50E 01 : 6.00E 00 : 1.00E 00 : 1.04E 02:
WCW: 9.00E 00 : 2.30E 01 : 1.70E 01 : 2.80E 01 : 2.00E 00 : 4.00E 00 : 8.30E 01:
W 5.00E 00 : 2.70E 01 : 3.60E 01 : 4.50E 01 : 1.80E 01 : 7.00E 00 1.38E 02:
WNW: 6.00E 00 : 2.30E 01 9.30E 01 : 9.60E 01 : 4.60E 01 : 2.20E 01 : 2.86E 02:
NW : 1.50E 01 ! 3.90E 01 : 6.70E 01 : 5.60E 01 : 9.00E 00 : 6.00E 00 : 1.92E 02:
NNW: 9.00E 00 : 3.30E 01 : 3.90E 01 : 3.50E 01 : 0.00E 01 : 0.00E 01 : 1.15E 02:
TOT: 1.68E 02 : 6.97E 02 : 7.68E 02 : 5.73E 02 : 1.25E 02 : 5.40E 01 : 2.39E 03:
PERIODS OF CALM (HOURS): 4.000E 00 HOURS OF INVALID DATA : 0.000E-01
- l l
l 1
43 1
1
TABLE 9, Page 2 of 14 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Data Period: 1988 STABILITY CLASS :B ELEVATION : 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 13 : 47 : 8-12 : 13 18 19-24 : >24 : TOTAL :
N : 0.00E 01 : 4.00E-00 : 6.00E 00.! 3.00E 00 ! 0.00E 01 : 0.00E 01 : 1.30E 01:
NNE: 2.00E 00 : 3.00E 00 : 1.00E 00 : 5.00E 00 ! 0.00E-01 ! 0.00E-01 : 1.10E 01:
NE : 1.00E 00 : 2.00E 00 7 00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 1.40E 01:
ENE: 1.00E 00 : 1.00E 00 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 8.00E 00:
E : 0.00E 01 : .1 00E 00 : 3.00E 00 :
. ..__________________.. . ______- --_1.00E 00 : 0.00E-01 : 0.00E 01 5.00E 00:
ESE: 0.00E-01 : 2.00E 00 : 2.00E 00 : 0.00E 01 : 0.00E 01 : 0.00E 01 : 4.00E 00:
SE : 0.00E-01 l'2.00E 00 : 5.00E 00 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 1.20E 01: J SSE: 0 00E 01 : 0 00E 01 6.00E 00 : 2.00E 00 : 0.00E 01 : 0.00E 01 8.00E 00:
S : 0.00E-01 : 3.00E 00 : 2.00E 00 : 9.00E 00 ! 2.00E 00 : 0.00E 01 : 1.60E 01:
SSW: 0.00E 01 : 4.00E 00 : 8.00E 00 : 9.00E 00 : 1.00E 00 : 4.00E 00 : 2.60E 01:
SW ! 1.00E 00 : 5.00E 00 : 8.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E 01 : 1.70E 01!
WSW: 1.00E 00 : 3.00E 00 : 4.00E 00 3.00E 00 : 1.00E 00 : 0.00E 01 : 1.20E 01:
W ! 0.00E-01 : 6.00E 00 : 1.00E 00 : 1.10E 01 4.00E 00 : 1.00E 00 1 2.30E 01:
WNW: 0.00E 01 : 2.00E 00 : 5.00E 00 : 8.00E 00 : 5.00E 00 ! 0.00E 01 : 2.00E 01:
NW 0.00E 01 : 2.00E 00 2.00E 00 : 8.00E 00 : 3.00E 00 2.00E 00 : 1.70E 01:
NNW: 0.00E-01 : 4.00E 00 : 7.00E 00 : 4 00E 00 : 1.00E 00 0.00E 01 : 1.60E 01:
TOT: 6.00E 00
- 4.40E 01 7.30E 01 : 7.50E 01 : 1.70E 01 : 7.00E 00 l 2.22E 02:
PERIODS OF CALM (HOURS)! 0.000E-01 HOURS OF INVALID DATA : 0.000E-01 l
1 44 i
i2 O
9*
TABLE 9, Page 3 of 14 SEMIANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Data Period: 1988 STABILITY CLASS :C ELEVATION : 10 METERS WIND SPEED (HPH) AT 10 METER LEVEL
- 13 : 47 : 8 12 : 13 18 : 19 24 : >24 : TOTAL !
N'__ 0.00E-01 : 2.00E 00 : 8.00E 00 : 8.00E 00 : 1 00E 00 0.00E 01 : 1.90E 01:
NNE: 0.00E 01 : 1.00E 00 3.00E 00 1 2.00E 00 : 1.00E 00 0 00E 01 : 7.00E 00: 1 NE ! 1.00E 00 2.00E 00 : 9.00E 00 : 2.00E 00 : 0.00E 01 : 0.00E 01 : 1.40E 01:
ENE: 1.00E 00 : 4.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 i'O.00E-01 : 5.00E 00!
E : 0.00E 01 : 0.00E 01 : 4.00E 00 : 1.00E 00 : 0.00E 01 : 0.00E 01 : 5.00E 00:
ESE: 1.00E 00 2.00E 60 : 4.00E 00 0.00E 01 : 0.00E 01 : 0.00E : 7.00E 00:
...____.___ .........____________________________________________-01 ... _..._..
SE : 0.00E-01 5.00E 00 : 4.00E 00 : 2.00E 00 ; 0.00E 01 : 0.00E-01 1.10E 01:
SSE: 1.00E 00 : 4.00E 00 : 0.00E-01 : 1.00E 00 : 0.00E-01 : 0.00E-01. : 6.00E 00: j S 2.00E 00 6.00E 00 6.00E 00 : 9.00E 00 .1.00E 00 : 1.00E 00 2.50E 01:
SSW: 1.00E 00 : 3.00E 00 : 7.00E 00 : 6.00E 00 : 3.00E 00 : 0.00E-01 : 2.00E 01:
SW 2 00E 00 : 8.00E 00 : 1.10E 01 l 9.00E 00 2.00E 00 : 0.00E 01 3.20E 01:
WSW: 2.00E 00 ! 7.00E 00 : 2.00E 00 : 8.00E 00 7.00E 00 : 1.00E 00 ! 2.70E 01:
W 0.00E 01 : 1.00E 00 : 7.00E 00 : 1.20E 01 : 1.10E 01 : 0.00E-01 : 3.10E 01:
WNW: 0.00E-01 : 1.00E 00 : 1.00E 01 : 1.70E 01 : 9.00E 00 : 4.00E 00 : 4.10E 01:
NW 0.00E-01 : 2.00E 00 : 8.00E 00 1.10E 01 : 1.00E 00 : 1.00E 00 2.30E 01:
NNW: 0.00E-01 : 2.00E 00 : 5.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 1.10E 01:
TOT: 1 10E 01 ! 5.00E 01 : 8.80E 01 ! 9.20E 01 : 3.60E 01 : 7.00E 00 : 2.84E 02!
PERIODS OF CALM (HOURS): 2.000E 00 HOURS OF INVALID DATA : 0.000E-01 45 !
1
+
TABLE 9, Page'4 of 14 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS l
I Data Period: 1988 '
L STABILITY CLASS :D .
ELEVATION : 10 METERS l WIND SPEED (MPH) AT 10 METER LEVEL i 1-3 ! 4-7 : 8-12 ! 13-18 : 10-24 : >24 : TOTAL :
N l'3.00E 00 : 4.40E 01 6.70E 01 : 2.00E 01 ! 3.00E.00 : 0.00E-01 : 1.37E 02:
NNE! 3.00E 00 : 3.90E 01 : 3.50E 01 ! 4.20E 01 : 7.00E 00 2.00E 00 : 1.28El02: l i
NE : 7.00E 00 2.40E 01 : 4.60E 01 : 2.50E 01 : 1.00E 00 : 0.00E-01 : 1.03E 02:
_____________________________________________ ________________ _ .__ ..________ i ENE! 1.00E 00 : 2.60E 01 : 1.80E 01 : 0.00E-01 : 0.00E 01 ! 0.00E 01 4.50E 011 i E : 2.00E 00 : 1.20E 01 ! 6.00E 00 :.1.00E 00 ! 0.00E-01 : 0.00E-01
- 2.10E 01:
........___.___a...__________.__. __. ____________....___..._-_________....______ .
ESE: 1.00E 01 : 1.40E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 0.00E-01 : 2.80E 01:
3.00E 00 l 00 0.00E-01 : 0.00E 01 : 6.00E 01: i SE'_:______. _____.._.._________.__
.__ 2.90E 01 ! 2.20E 01 : 6.00E SSE: 6.00E 00 3.30E 01 4.90E 01 : 1.30E 01 : 4 00E 00 : 1.00E 00 : 1.06E 02:
S : 2.00E 00 3.70E 01 : 7.70E 01 ! 5.30E 01 : 1.30E 01 : 1.00E 00 : 1.83E 02:
SSW: 2.00E 00 ! 4 10E 01 : 0.70E 01 : 7.40E 01 : 2.00E 01 : 1.00E 01 : 2.34E 02:
i SW : 5.00E 00 3.30E 01 : 7.60E 01 : 2.20E 01 : 7.00E 00 : 0.00E 01 ! 1.43E 02:
WSW: 5.00E 00 ! 2.50E 01 : 2.20E 01 ! 2.60E 01 : 9.00E 00 2.00E 00 : 8.90E 01:
W ! 2.00E 00 ! 2.30E 01 ! 5.30E 01 9.40E 01 2 3.00E 01 ! 3.00E 00 ! 2.05E 02:
WNW: 4.00E 00 ! 1.90E 01 : 5.80E 01 5.90E 01 1 80E 01 : 7.00E 00 1.65E 02:
NW ! 2.00E 00 ! 3.10E 01 ! 6.50E 01 : 3.80E 01 : 6.00E 00 : 6.00E 00 : 1 48E 02:
NNW: 1.00E 00 : 2.60E 01 ! 4.00E 01 : 1.90E 01 : 6.00E 00 : 2.00E 00 : 9.40E 01:
.......____._____.......________.__._____..______. ___..... _______________...___ ~
TOT: 5.80E 01 : 4.56E 02 : 7.25E 02 : 4.92E 02 : 1.24E 02 : 3.40E 01 : 1.89E 03!
PERIODS OF CALM (HOURS): 7.000E 00 HOURS OF INVALID DATA : 0.000E-01 46
<c ;
q: , .
,4,
, 1 s
'. TABLE 9, Page 5 of314
~
fSEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JOINT WIND FREQUENCY DISTRIBUTION BY. STABILITY CLASS
, Data Period:. 1988' t
i STABILITY CLASS .: E ELEVATION 1 10 METERS WIND SPEED (MPH) AT 10 HETER LEVEL 8-12
- - 47- ! t 13 18 ! 19 24 : >24 ..: TOTAL Lt-
.. . .._ _'_1_3 __.......__...........___ _______________. __. __....____...__.._______
N 7.00E 00 1 3.80E 01 : 2.80E 01 1 30E 01 : 1.00E 00 1.0.00E-01 !.8.70E.01 -
HNE .4.00E 00 1.2.30E 01 ! 7.00E 00 ! 1.20E 01 : 0.00E 01-! 0.00E 01 4.60E 012-NE : 6.00E'00:1-3.20E 01 ! 2.00E 01 6.00E 00 0.00E-01 !.0.00E-01:1'6.40E 01 . 1 ENE: 6.00E 00. 2.80E.01. 2.20E 01 1.00E 00 : 0.00E 01.! 0.00E-01 5.70E 01 t .
_________............_________....__! _____....___..__.____.______..___.!___________ l E ~ ! 7.00E 00 1 60E 01 1.70E 01 : 1.00E 00;; 0 00E 01 0.00E_01'__! 4.10E 01:
ESE: 1.10E 01 ! 4'.10E
_ . _ _- 01 '_ _: 2.00E 00. 0.00E
______....___ __ .01 : 0.00E 01 : 0.00E 01 : 5.40E 01:
- SE : 1.10E 01 i 4.60E.01 ! 0.00E 01 : 0.00E 01 ! 9 00E 01:
...._____.....__ ...______ 3.20E'01.! _____________......
1.00E 00 :___________. __________'_.. _..__ .
SSE! 1.10E 01 l : 5.10E~01 : 6.00E 00 .0.00E 01 : 0.00E 01 : 1.33E 02:
.__..........__.'6.50E:01 ...____________________ ..____...____________________' .-_-______
S : 1.70E '6.90E 01 : 2.20E 01 !.5.00E 00 2.00E 00 ! 2.03E 02: !
__ .. _____011:'8.80E 01 SSW: 1 40E 01 !:8.60E 01 ! 1.17E 02 1 4.80E 01 : 8 00E 00 2 2.00E 00 : 2.75E 02: ';
SW 1.50E 01 1 6.20E 01 ! 8.30E 01 : 2.50E 01 : 5.00E 00 ! 1 00E 00 ! 1.91E 02:
WSW: 8.00E 00-! 3.70E 01 ! 6.40E 01' 00 ! 4.00E 00 l-3.00E 00 : 1.25E 02: ;
....... _________________._______...__9.00E ________ .......___ .._______________ _..
j W ! 8.00E 00 : 3.00E 01 : 6.30E 01 1.60E 01 ! 4.00E 00 t 7.00E 00 1.28E 02: j
-_-________.____... ____._____..___.____________. _______. .____________________ 4 WNW: 4.00E 00 : 4.10E 01 5.80E 01 : 4.00E 00 : 0.00E 01 0.00E 01 ! 1.07E 02:
NW ! 9.00E 00 : 3.80E 01 : 9.00E 00 : 1.00E 00 1.00E 00 : 9 10E 01:
..... _______ ..... ......_3.30E 01
__________.________________________________.. _______ 1 HNW:'6.00E 00 2.60E 01 : 2.50E 01 : 1.50E 01 : 1.00E 00 : 9 00E 00 : 8.20E 01: j
_______.___....__.______..__...________...__.__.________..____-...._____._______ \
TOT: 1.44E 02 : 6.97E 02 ! 6.91E 02 : 1.88E 02 ! 2.90E 01 : 2.50E 01 ! 1.77E 03:
. PERIODS OF CALM (HOURS): 1.000E 00 HOURS OF INVALID DATA : 0 000E-01 47
r I
c -. '
i- .
[
TABLE 9, Page 6 of 14 L . SEMIANNUAL. RADIOACTIVE. EFFLUENT RELEASE REPORT !
l ' JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS a Data Period: 1988 -
l i
i l
STABILITY CLASS :F !
ELEVATION : 10 NETERS :
WIND
...._______.__________ SPEED (MPH) AT 10 HETER
____. ...___________________________ LEVEL 1-3 : 4-7 .! 8-12 : 13-18 't 19-24 : >24 : TOTAL :
H ! 7.00E 00 1 2.10E 01 ! 3.00E 00 : 1.00E 00 ! 0.00E-01 :____________________-01 0.00E : 3.20E 01:
NNE: 1.40E 01.3 3.20E 01 !-3.00E 00 : 0.00E-01 0.00E-01 : 0.00E-01 : 4.90E 01:
NE : 1.00E 01 ! 3.50E 01 3.00E 00 0.00E 01 : 0.00E 01 : 0 00E 01 : 4.80E 01:
ENE: 1.40E 01 2.60E 01 : 1.00E 01 ::1.50E 01 : 0.00E-01 : 0.00E-01 : 6.50E 01: !
E : 1.50E 01-! 2.20E 01 :.2.70E 01 2 3.00E 00 : 0.00E-01 : 0.00E-01 : 6.70E 01:
ESE: 1.60E 01 : 1.80E 01 : 1.00E 00 0.00E 01 !_0.00E 01 0.00E 01,: 3.50E 01:
i SE : 1.30E 01. 2.80E 01 1.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.20E 01:
o SSE! 1.20E 01 4.00E 01.:.5.00E 00 : 1.00E 00 0.00E 01 : 0.00E 01 : 5.80E 01 l S !~1.10E 01 ! 6.10E 01 1.20E 01 3.00E 00 0 00E-01 : 0.00E-01 : 8.70E 01:
SSW! 1.00E 01 7.10E 01 : 3.10E-01 : 2.00E 00 0.00E-01 : 0.00E-01 : 1 14E 02:
SW ! 1.10E 01 ! 6 50E 01 : 3.20E 01 : 1.20E 01 : 5.00E 00 0.00E 01 !.1.25E 02:
...____. ______________________________________________,________________________ i WSW: 1.10E 01 3.90E 01 ! 4.40E 01 : 1.70E 01 : 1.30E 01 ! 2.00E 00 : 1.26E 02:
l W : 4.00E 00 : 2.10E 01 : 1.60E 01 1.40E 01. 3.00E 00 : 1.00E 00 : 5.90E 01:
WNW: 1.20E 01 2.70E 01 : 2.00E 00 : 0.00E 01 : 0.00E 01 : 1.00E 00 : 4.20E 01:
NW ! 1.20E 01 ! 3.50E 01 : 4.00E 00 0.00E-01 : 1.00E 00 : 1 00E 00 ! 5.30E 01:
NNW: _1.10E 01 : 1.90E 01 : 1.60E 01 : 1.00E 00 0.00E 01 : 0.00E-01 4.70E 01:
TOT: 1.83E 02 : 5.60E 02 : 2.10E 02 5.90E 01 : 2.20E 01 : 5.00E 00 : 1.05E 03:
PERIODS OF CALM (HOURS): 6.000E 00 HOURS OF INVALID DATA : 0.000E-01 48
i-
)
TABLE 9, Page 7 of 14 '
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS j Data Period: 1988 j STABILITY CLASS :G ELEVATION : 10 METERS WIND SPEED (HFH) AT 10 HETER LEVEL 13 : 47 : 8-12 : 13 18 : 19 24 : >24 : TOTAL N : 1.30E 01 : 1.00E 00 : 1.00E 00 0.00E 01 : 0.00E-01 : 1 50E 01:
_________________________________.== 0.00E _01 NNE: 1.40E 01 : 1.70E 01 : 0.00E 01 : 0.00E 01 : 0.00E 01 : 0.00E 01 : 3.10E 01:
NE : 3.10E 01 : 6.10E 01 : 0.00E 01 : 0.00E 01 : 0.00E-01 : 0.00E 01 : 9.20E 01:
ENE: 2.80E 01 5.20E 01 : 1.90E 01 : 2.00E 00 0.00E-01 : 0.00E-01 : 1.01E 02:
E : 2.30E 01 4.30E 01 : 2.30E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 8.90E 01: )
ECE: 3.00E 01 : 1.80E
___________. __ - . _ _01
_ _ :_ 0.00E-01
_ _ _ _ _ _ _ _ :_ 0.00E-01-! 0.00E 01 : 0.00E _01 : 4.80E 01:
_ ==_.....______________.- =_ _____________
SE : 1.30E 01 : 6.00E 00 : 1.00E 00 0.00E 01 : 0.00E 01 : 0.00E 01 : 2.00E 01:
SSE: 1s10E 01 :_ 1.40E,01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.50E 01:
S : 5.00E 00 : 1.50E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.10E 01:
55Ui"IIU3E 65"l~2553E'3I~I~2530E~03~l~0500E-di~l"3500E~-3I~I"UI665565"I~55765~5II SW 1.50E 01 ! 5.80E 01 : 1.10E 01 : 2.00E 00 0.00E 01 : 0.00E-01 : 8.60E 01:
WSW: 2.20E 01 : 3.60E 01 3.50E 01 : 2.20E 01 : 1.10E 01 : 0.00E-01 : 1.26E 02:
W : 2.30E 01 : 2 50E 01 : 2.00E 00 2.00E 00 : 0.00E-01 ! 0.00E-01 : 5.20E 01:
WNW: 2.50E 01 : 1.50E 01 : 0.00E 01 : 0.00E 01 : 2 00E 00 : 0.00E 01 : 4.20E 01:
NW : 1.50E 01 3.20E 01 ! 8.00E 00 : 1.00E 00 : 0.00E 01 : 0.00E 01 : 5.60E 01:
NNW: 2.20E 01 : 9.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E 01 : 0.00E 01 3.20E 01:
TOT: 3.00E 02 : 4.27E 02 : 1.04E 02 : 2.90E 01 : 1.30E 01 : 0.00E 01 : 8.73E 02:
PERIODS OF CALM (HOURS): 1.500E 01 HOURS OF INVALID DATA : 0.000E-01 g HOURS OF GOOD DATA : 8.511E 03 = 96.9% OF TOTAL HOURS 49
il .
L 9 Lm .l 3 .
.1 1
ar 1
-1 L ,
TABLE 9, Page 8 of 14 )
l l .
. SEMIANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT-1 1
JOINT WINT FREQUENCY DISTRIBUTION-BY STABILITY CLASS i Data Period: 1988 1 e 1.
I l
STABILITY CLASS :A ELEVATION : 60 METERS WIND SPEED (HPH) AT 60 METER LEVEL j
! 13 .: 8 12 : 13 18 ! 19-24 : >24 :
...__.._......____4_7 _ __________ .._____________...__..._________________ TOTAL __.__....
N : 6.00E 00 1 4.70E 01 5.70E 01 4.50E 01 : 1.00E 01 : 6.00E 00 ! 1.71E 02:
-NNE: 6.00E 00 : 5.20E 01 :
_____________..____________4.10E 01 : 4.00E 01 : 4.20E 01 : 2.00E 01 : 2.01E 02: ,
NE : 4.00E.00;! 2.40E 01 : 3.50E 01 2 60E 01 1.70E 01
- 2.60E 01 ! 1.32E 02!. i i
ENE: 5.00E-00' .1.60E 01 ! 3.40E 01 : 9.00E 00 1 2.00E 00 2.00E 00 ! 6.80E 01 - !
E 8.00E 00 ! 6.30E 01: i
_____ .....____.'1.90E 01'_: 1.60E 01 : 5.00E 00 : 9.00E 00 : 6.00E 00
______ ._ _______ ..._____________________._________..........__ i ESE! 1.20E 01.: 2.80E 01- 2.60E 01 : 1.60E 01 :
.____._____.____________.___________..._____'_________________._____.2.00E 00 ft2.i --- ___ ;
'SE : 1.70E 01~ 6.10E 01 : 4.90E 01 : 2.80E 01 : 6.00E:00 l 2.00E 00 1 63E 02: !
SSE: 1.90E 4.50E : 2.20E 01 : 1.60E 01 : 9.00E 00 : 1.61E 02:
..__________'01 1.5.00E 01 :__________ ______-01 ______________'________________________________
__ 1 S ! 6.00E 00 : 7.10E 01 : 1.10E 02 : 5.30E 01 : 2.20E 01 ! 1.70E 01 : 2.79E 02:
~
SSW: 7.00E 00 l 01 ! 4.10E 01-! 3.10E 01 ; 3 40E 01 : 1.50E 01 : 1.42E 02: l
____.___________'1'_.40E _ __ ...._____________..._______________. ________....._________ ,
SW 2.00E 00 ! 2.50E 01 : 1.60E 01 : 4.00E 01 : 1 60E 01 :.4.00E 00 : 1.03E 02!
WSW: 7.00E 00 ! 1.00E 01 : 1.30E 01 : 1.70E 01 : 2.20E 01
_________._________________________...__........._________'_________ 6.00E 00 : 7.50E 01:
W ! 2.00E 00' 2.10E 01 : 4.20E 01. 4.70E 01 ! 4.30E 01 : 2.90E 01 : 1.84E 02:
WNW:'_4.00E 00 : 1.40E 01 : 5.80E 01 : 5.80E 01 5.90E 01 : 4.60E 01 : 2.39E 02!
NW 5.00E 00 : 3.90E 01
- 6.10E 01 : 4.10E 01 : 2.80E 01 : 6.00E 00 : 1.80E 02:
NNW: 9.00E 1
..____.__ _'00 : 3.20E________
______..._________ 01 ! ___________..__________.._______________.
3.10E 01 : 3.40E 01 : 6.00E 00 : 0.00E 01 l 1.12E 02: 1 '
TOT: 1.19E 02 : 5.23E 02 : 6.75E 02 : 5.12E 02 : 3.34E 02 : 1.96E 02 : 2.36E 03:
PERIODS OF CALM (HOURS): 3.000E 00 i HOURS OF INVALID DATA : 2.700E 01 50
2 i l
TABLE'9, Page 9 of 14 SEMIANNUAL RADIOACTIVE EFFLUENT. RELEASE REPORT JOINT WIND FREQUENCY: DISTRIBUTION BY STABILITY CLASS L Data Period: 1988 i-L ..
. STABILITY CLASS B .
ELEVATION : 60 METERS -1 1
. t
. WIND SPEED (HPH) AT 60 . METER LEVEL !
c :
- 1-3 : 4-7 : 8-12 : 13-18 ! 19-24 : >24 : TOTAL : !
N : 0.00E 01 t 2.00E 00
._______________'______'_____. 3.00E 00 ! 7.00E 00 3.00E 00 ! 0.00E 01 1.50E 01:
____________________________________ l
- NNE:.1.00E 00 l'1.00E 00 1 5.00E 00 : 3.00E 00 5.00E 00 : 1.00E 00 1.60E Oi!
]!
1 NE ! 1.00E 00 : 1'.00E 00-! 1.00E 00 l 4.00E 00 : 3.00E 00 0.00E-01 t'1.00E 01:
l ENE: 0.00E-01 : 0.00E-01 : 0.00E-01 3.00E 00.: 1.00E 00.: 0.00E-01': 4.00E 00; i 1
E .: 0.00E 01 : 1.00E 00 : ________________.____________________________________.
-._________.__._________ __'3.00E 00. 0.00E 01 : 1.00E 00 : 1.00E 00 : 6.00E 00:
R q
ESE: 0.00E-01 : 1.00E 00 : 1.00E 00 t,0.00E-01 : 0.00E-01 1 0.00E-01 : 2.00E 00! ~ l
~
SE : 0.00E-01 : 1.00E l>0 : 2.00E 00 5.00E 00 : 0.00E-01 :~0.00E-01 : 8.00E 00 -
SSE: Og00E-01 :.1.00E 00 : 0.00E : 0.00E : 8.00E 00 : 0.00E 01 t 9.00E 00:
________....________.____'________-01 ___________-01 __...._______________ _ _____'________. ,
S : 0.00E 01 : 2.00E 00 : 7.00E 00 : 4.00E 00 : 6.00E 00 : 8.00E 00 : 2.70E 01:
SSW:
_____________ 0.00E 01' 2.00E 00 : 6.00E 00 : 3.00E 00 : 2.00E 00 : 7.00E 00 2.00E
_'_________________________________ 01:
2.00E 00 : 0.00E-01 : 1.80E 01:
SW ! 0.00E_01
__________ 1 4.00E 00 : 6.00E 00 : 6.00E
__________________________________..____.___ 00
. WSW: 0.00E-01 3.00E 00 : 1.00E 00 : 3.00E 00 4.00E 00 2.00E 00 : 1.30E Oli i
W O.00E-01 2 3.00E 00 2.00E 00 : 3.00E 00.! 7.00E 00 l 2.00E 00 :
____'__..._____________________________.._______...____________.._________...____1.70E 01:
WNW: 0.00E-01 : 1.00E 00 : 3.00E 00 ! 5.00E 00 : 8.00E 00 1.00E 01 : 2.70E 01:
2.00E 00 : 8.00E 00 : 3.00E 00 : 0.00E 01 : 1.40E 01:
NW'_: 0.00E 01 !.1.00E 00 NNW:.0.00E 01 : 1.00E 00 : 4.00E 00 : 4.00E 00 ! 3.00E 00 0.00E-01 : 1.20E 01:
TOT: 2.00E 00 2.50E 01 : 4.60E 01 : 5.80E 01 5.60E 01 : 3.10E 01 : 2.18E 02:
PERIODS OF CALM (HOURS): 1.000E 00 i HOURS OF INVALID DATA : 3.000E 00 l
}
1 I .I 51 j
,, Y h;( f _ . ,
. 7~ c 3 gr 30 -
_l w m,s ,a i
M $ 36 iI 4 ,. j m
- g. , m~- ,
,,W "i
- ,- p
- p. --
,s
. TABLE . 9, : Page 10 = of ,14
.,r C ' ~
SEMIANNUAL RADIOACTIVE' EFFLUENT RELEASE' REPORT :l JOINT WIND FREQUENCY DISTRIBUTION'BY STABILITY CLASS l
. Data Period: 1988 ;
- 1 L ,
l-I.
l t .;-, .
ni l'
i 4 h . STABILITY. CLASS. ! C. I
!: ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 NETER LEVEL.
H'
,- : 1 ! 47 !- 8-12 !. 13-18' ! 19-24 : >24 2. TOTAL-(N. !.0 00E-01 : 1.00E 00 2.00E 00 ! 1.00E.01 : 2.00E.00 : 0.00E-01 : 1'.50E/01: :l NNE! 0 00E-01': 0.00E-01 !.3.00E 00 2.00E 00 : 1.00E 00 : 1.00E 00': 7.00E 00 '
NE-! 1.00E 00 : 1.00E 00 ! 3.00E 00 : 6.00E 00 ! 1.00E 00 .2.00E 00 : 1.40E Oli i! 'ENE:.0.00E-01 : 1.00E 00 ! 1.00E.00 :.2.00E 00 0.00E-01 : 0.00E-01.!:4.00E 00!' .s
.E !.0.00E 01 l O.00E 01 : 0.00E-01 : 0.00E 01 : 1.00E 00 0.00E 01 : 1.00E 00:c
,ESE 1.'00E 00
_________'________________.... ______________ ______ -l 1.00E '00 ! 6.00E 00 2.00E 00 : 2.00E 00 1 0 00E-01 : 1 20E 01:
.SE :-0.00E_01 ~1.00E 00 : 4.00E.00 : 2.00E 00 : 0.00E 01 : 0.00E ! 7.00E 00:-
_____..___ __________.._______________________... ______.________-01 _____ _________ 1 e SSE: 0.00E-011: '0.00E-01 l' 3.00E 00 !! 3.00E 00 : . 4.00E 00 0 00E-01 : 1.00E 01:
S !1 2.00E 00 : 2.60E 01:
___..._'.00E 00 :_ ___..4.00E 00 00 2 3.00E 00 l'_8.00E ._.__________._____________-00
__.._____ 8.00E SSW:.1.00E.00 ! 2.00E 00 1 7.~00E 00 ! 6.00E 00 : 6.00E 00 l'6.00E 00-! 2.80E 01
- 0. 6.00E-00 7 00E 00 : 4.00E 00 : 4.00E 00 : 2.00E 00 ! 2.30E 01:
___ ___'00E_01' SW'_: ___ __. __...__.___________ ____________________...._. __________________
WSW: 0.00E 01 3.00E 00 : 1 00E 00 1 2.00E 00 ! 9.00E 00 : 7.00E 00 1 2.20E 01: q W -: 1.00E 00 : 0.00E 01 4 00E 00 ! 1.20E 01 : 9.00E : 1.40E 01 ! 4.00E 01: ' -
l
..__....._____'..__________...____.....____...._________'00 ___.._______..______ .____
WNW! 0.00E-01 : 1.00E 00 : 4.00E 00 : 6.00E 00 : 1.10E 01 9.00E 00 : 3.10E 01:
NW ! 0.00E-01 ! 0.00E-01 4.00E 00 : 1.20E 01 : 5.00E 00 : 3 00E 00 1 2.40E 01:
NNW:
....._ 0.00E_01 : 2.00E 00 6.00E 00 : 8.00E 00 : 3.00E 00 0.00E 01 : 1 90E 01:
TOT: 5.00E 00 2.20E 01 : 6.30E 01 8 10E 01 : 6.60E 01 ..___________.-____02:
- 4.60E 01 : 2.83E PERIODS OF CALM (HOURS)! 0.000E-01 HOURS OF INV/, LID DATA : 3.000E 00
~
i 52
t.
... 1 g
'1 .
l.
TABLE-9, Page'll of 14.
1
- SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT r
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS q
Data Period: 1988 1
1 l
i i
I] 1 STABILITY CLASS :D ELEVATION : 60 NETERS l WIND SPEED (MPH) AT 60 HETER LEVEL :W
________________________________. _______....._______________________________ q
! 13 : 47 .: . 8 12 :
____________._____________________'_____________________________________ 13 18 : 19 24 : >24- TOTAL : 1 N :'0.00E_01
._.....___ : 1 70E 01 5.80E 01 ! 6 10E 01 ! 1 10E 01 ! 2.00E 00 : 1.49E 02:
NNE: 1.00E 00 : 1.80E 01 ! 3.10E 01 ! 3.50E 01 ! 4.10E 01 : 2.70E 01 : 1.53E 02:
NE 1.00E 00 : 4.00E 00 1 2.70E 01.: 2.40E 01 ! 1.10E 01
.__________________1.00E 00 6.80E 01:
ENE: 0.00E-01 : 4.00E 00 : 2.10E 01 : 6.00E 00 : 1.00E 00 : 0.00E-01 3.20E 01: j
- .i E fil.00E 00 : 5.00E 00 .7.00E 00 : 0 00E-01 0.00E-01 : 1.00E 00
- 1.40E 01: !
ESE: 2.00E 00l: 4.00E 00, 1.20E 01 : 2.00E 00 : 0.00E 01 ! 2.00E 01:
____________.... ________...______________ ..____-0.00E_01 _____ _________________________ ;
SE : 2.00E 00.! 2,80E 01 : 2.00E 01 !L1.10E 01 : 0.00E 01 : 7.00E 01: 1
____-9.00E 00 3 SSE: 4 00E 00 ; 6.00E 00 1.90E 01 : 4.20E 01 : 1.30E 01 : 1.20E 01 : 9.60E 01:
LS : 1.00E 00 : 1.00E 01 4.90E 01 : 7.80E 01 : 4.60E 01 ! 6.30E 01 ! 2.47E 02:
___________ _________________________________________ ____.__...________________ 1 SSW! 1.00E 00 : 1.10E 01 : 5.30E 01 : 8.80E 01 : 4.30E 01 3.00E 01 : 2.26E 02: 1 SW : 3.00E 00 ::1.90E.01 : 2.80E 01 ! 2.40E 01 : 1 40E 01 : 5.00E 00 : 9.30E 01: i WSW: 1.00E 00 : 1.00E 01 : 2.30E 01 : 2.20E 01 : 2.20E 01 : 1.10E 01 : 8.90E 01:
W ! 3.00E 00 ! 5.00E 00 : 2.40E 01 : 5.60E 01 6.50E 01 : 2.70E 01 : 1.80E 02:
WNW! 2.00E 00 3.00E 00.! 2.60E 01 : 5.90E 01 1 3.80E 01 1.3.00E 01 ! 1.58E 02: !
NW ! 2.00E 00 : 8.00E 00 : 5.70E 01 l Ct i 2.40E 01 : 1.60E 01 ! 1.61E 02:
._......._____________________________'5.40E ______..._______________ _________________ o
.NNW: 0.00E-01 : 1.20E 01 l 4.70E 01 : 4.80E 01 : 2.00E 01 : 0.00E 01 : 1.27E 02:
TOT: 2.40E 01 ! 1.45E 02 : 5.10E 02 : 6.19E 02 : 3.60E 02 : 2.25E 02 : 1.88E 03:
1 PERIODS OF CALM (HOURS): 3.000E 00 j ll0URS OF INVALID DATA : 1.000E 01 l I
i 1
1 1
)
53 x _ _ - - - _ - _ _ -
TABLE 9, Page 12 of 14 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Data Period: 1988 STABILITY CLASS :E ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL
- 1 : 4-7 : 8-12 : 13-18 : 19-24 : >24 ! TOTAL :
.... ___-3________________________ ...____ .______________________________________
N : 3.00E 00 : 5.00E 00 ! 3.00E 01 : 2 20E 01 : 2.00E 00 : 1.00E 00 6.30E 01!
NNE: 3.00E 00 : 4.00E 00 : 1.60E 01 : 2.10E 01 : 1 90E 01 : 8.00E 00 : 7.10E 01:
NE : 1.00E 00 : 4.00E 00 : 1.00E 01 : 4.40E 01 : 6.00E 00 : 0.00E-01 6.50E 01:
.._-____ ____..... __-_=- ===
ENE: 1.00E 00 8.00E 00 : 1.40E 01 : 1.70E 01 0.00E 01 : 0.00E-01 4.00E 01:
== __ _______
E : 0.00E-01 : 5.00E 00 : 1.40E 01 : 5.00E 00 3.00E 00 : 0.00E 01 : 2.70E 01:
~__..__.__.-- ._=-- ==__ ____...._____..____... ________.__________ = .__.._
ESE: 0.00E-01 6.00E 00 : 2.60E 01 : 8.00E 00 : 0 00E-01 : 0.00E-01 ; 4.00E 01:
SE : 1.00E 00 : 1.10E 01 : 3.80E 01 : 1.50E 01 : 1.40E 01 0.00E-01 : 7.90E 01:
.______.______________._________.___.-__________.==----- -_______.-- -____
SSE: 3.00E 00 : 8.00E 00 5.20E 01 4.90E 01 : 1.70E 01 : 1.00E 01 : 1.39E 02:
S : 2.00E 00 : 1.50E 01 5.60E 01 : 1.30E 02 : 3.10E 01 : 3.60E 01 : 2.70E 02:
__..__..______________.______.__.____.______________._____.______ -_-- ===
SSW: 1.00E 00
- 1.30E 01 : 7.20E 01 : 1.01E 02 : 5.50E 01 : 1.50E 01 : 2.57E 02:
SW ! 0.00E-01 : 1 60E 01 : 4.70E 01 : 7 00E 01 : 2.70E 01 : 1.80E 01 : 1 78E 02:
WSW: 3.00E 00 : 9.00E 00 : 5.00E 01 : 3.70E 01 : 1.00E 01 : 1.20E 01 : 1 21E 02:
W : 1.00E 00 : 5.00E 00 2.50E 01 3.40E 01 : 1 00E 01 : 5.00E 00 : 8.00E 01:
WNW: 5.00E 00 : 4.00E 00 1 2.30E 01 : 5.10E 01 : 5.00E 00 0.00E 01 : 8.80E 01:
NW : 1.00E 00 : 1.00E 01 : 4.40E 01 : 4.80E 01 7.00E 00 : 1.30E 01 : 1.23E 02: -
NNW: 2.00E 00 : 8.00E 00 : 3.70E 01 : 5.10E 01 : 1.00E 01 ! 0.00E-01 : 1.08E 02:
____...___.-__._______.___ .__________.___..__ ___==______. ____..__--- ...__
TOT: 2.70E 01 : 1.31E 02 : 5.54E 02 : 7 03E 02 : 2.16E 02 : 1.18E 02 : 1.75E 03:
PERIODS OF CALM (HOURS): 1.000E 00 HOURS OF INVALID DATA : 2.500E 01 54
I TABLE 9, Page 13 cf 14 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Data Period: 1988 STABILITY CLASS :F ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 HETER LEVEL
---.--------...........--..= .----...........--..--..........--........--..
- 1-3 : 4-7 : 8-12 : 13-18 : 19-24 : >24 : TOTAL :
........--..................... -- _.---- ...-- =--....--.......---
N : 0.00E-01 : 9.00E 00 : 1.90E 01 : 7.00E 00 : 1.00E 00 ! 0.00E-01 : 3.60E 01:
........----...........------- -- =_- _------------- .--. =.--------..
NNE: 6.00E 00 1 2.00E 00 : 1.40E 01 : 3.60E 01 : 3.00E 00 : 0.00E-01--: --------- 6.10E 01:
NE : 4.00E 00 : 4.00E 00 : 9.00E 00 : 2.50E 01 5.00E 00 1 0.00E-01 4.70E 01:
ENE: 1.00E 00 : 1.20E 01 : 1.80E 01 : 2.60E 01 : 1.60E 01 : 1.00E 00 : 7 40E 01:
E : 1.00E 00 0 9.00E 00 : 1.30E 01 : 1.40E
- - . . . . . . . - - - - - - - . . . - - - - - - . . . . . = -
01 : 4.00E 00 : 5.00E 00 f 4.60E 01:
ESE: 3.00E 00 : 6.00E 00 : 2.00E 01 : 4 00E 00 : 0.00E-01 : 0.00E-01 : 5.30E 01:
SE : 5.00E 00 6.00E 00 2.10E 01 : 7 00E 00 : 0 00E-01 : 0.00E-01 : 3 90E 01:
..............--------------------- ---- __ _= ._------..--...--.. --
SSE: 2.00E 00 : 7.00E 00 2.30E 01 : 1 50E 01 : 0.00E-01 : 0.00E-01 : 4.70E 01: --------._ _ _ .=- --------
S : 3 00E 00 : 1.20E 01 3.60E 01 : 670EOi:3.00E0010.00E-01: 1.21E 02:
SSW: 1.00E 00 : 3.00E 00 2.30E 01 6.70E 01 : 1.30E 01 : 2.00E 00 : 1 09E 02:
SW ! 1.00E 00 : 5.00E 00 3.30E 01 : 6.90E 01 : 8.00E 00 : 1.30E 01 : 1 29E 02:
_........... _ =- ------.--------- .............
WSW: 2.00E 00 : 5.00E 00 : 3.00E 01 : 4.20E 01 : 2.20E 01 : 8.00E 00 : 1 09E 02:
W 2.00E 00 : 4.00E 00 : 1.90E 01
=.-------------....-- .
- 1.30E 01 : 3 00E 00 2.00E 00 : 4.30E 01:
....=- _...... ..--.......--.....-------
WNW: 0.00E-01 4.00E 00 2.20E 01 : 1 10E 01 : 2.00E 00 : 2 00E 00 : 4 10E 01:
NW : 2.00E 00 : 6.00E 00 2.80E 01 : 8 00E 00 : 2.00E 00 ; 0.00E-01 : 4.60E 01:
. . . . - - - - - - - - - - - - - - - - - _ __ - _ _ = _ . . . - - - - - - . . . . . . . . . - - = = = = _ = _ _ _ . . . . . . . . . . . . . - - - - - - -
NNW: 2.00E 00 : 4.00E 00 : 1.90E 01 : 2.50E 01 : 0.00E-01 : 0 00E-01 : 5 00E 01:
TOT: 3.50E 01 : 9.80E 01 : 3.47E 02 : 4.36E 02 : 8 20E 01 3.30E 01 : 1.03E 03:
PERIODS OF CALH(HOURS): 1.000E 00 HOURS OF INVALID DATA : 2.300E 01 55
[h r -
Sa . , -
,z' o
a J . .
7 TABLE 9,:Page 14 of 14 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT >
' JOINT. WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS-
- Data Periodt 198P .3 1
a 4
l 3
.i
'-- STABILITY CLASS :G ELEVATION ! 60 METERS' WIND SPEED (MPH) AT 60 METER LEVEL
!- 1-3 4-7 : 8-12 : 13-18 : 19-24 : >24 -: TOTAL : .
1
_01 -7 00E 00 : 1 80E 01 5.00E 00 0.00E 01 : 0.00E 01 ! 3.00E 01; N
__ _'_t.0.00E q
NNE: 3.00E 00 1.50E 01 : 9.00E 00 : 4.00E 00 0.00E-01 : 0.00E-01 :'3.10E 01:
NE :.1.00E 00. 1.40E 01 !'1 70E 01 : 2 30E 01 : 2.00E 00 0 00E-01 : 5.70E 01 .
ENE: 3;00E 00 : 5.00E 00 : 2.90E.01 : 6.60E 01 : 5.00E 00 0.00E 01 1.08E 02 E : 1.00E 00 ! 1.20E'01 : 2.80E.01 : 4.70E 01 1.20E 01 : 2.00E 00 :-1.02E'02:
ESE: 5.00E 00 : 1.40E 01 .1.10E 01 : 1.00E 01 8.00E 00 : 1.00E 00 4.90E 01:
SE : 8.00E 001:~1.90E 01-l 1.30E 01 : 0.00E-01 : 0.00E-01 !.0.00E-01 :~4.00E 01:
SSE: 1.00E 00 : 9.00E 00. 1.80E 01 4.00E 00 : 0.00E-01 : 0.00E-01 : 3.20E 01:
S * ~ 00E 00't-7.00E 00 i 1.10E 01 : 7.00E 00 1 0.00E-01 1 0.00E-01 2.80E 01:
SSW: 0.00E-01 : 3.00E 00 : 1.50E 01 : 3.10E 01 : 1.00E 00 : 0.00E 5.00E
_.__________________________-01
___________'01: ___
SW 1.00E 00 2.00E:00 1.2.40E 01 :-6.80E 01 ! 7.00E 00 3.00E.00 1.05E 02:
WSW: 0.00E-01 : 3.00E 00
.._______________._________'3.60E 01 : 3.20E 01 : 1.00E 01 : 9.00E 00 : 9.00E 01:
W_ 1.00E 00 : 5.00E 00 3.80E 01 : 1 00E 01 : 0.00E 01 : 1.00E 00 5.50E 01:
'WNW: 1.00E 00 : 2.00E 00 : 1.30E 01 : 6.00E 00 0.00E-01 ;-3.00E 00 .2.50E 01:
NW 00 : 1.50E 01 : 0 00E-01 : 1 00E 00 3.20E 01:
_ 0.00E 01 : 7.00E 00 : 9.00E________________________________________________
___ ________________________ i NNW: 1.00E 00.1 7.00E 00 : 1.30E 01 1 20E 01 0.00E-01 : 1.00E 00 ! 3.40E 01:
TOT: 2.90E 01 : 1.31E 02 : 3.02E 02 3.10E 02 4.50E 01 2.10E 01 : 8 68E 02: ;
PERIODS OF CALM (HOURS): 0.000E-01 '
HOURS OF INVALID DATA 2.000E 01 HOURS OF 000D DATA : 8.400E 03 = 95.6% OF TOTAL HOURS
\
I I-56
m ,,
. ,\ f.-
s J) c'm~..;.'
'b. p_
-. 4j i
,c.
3
, r i 2 i
TABLE 10, Page 1 of 12
' SEMIANNUAL' RADIOACTIVE EFFLUENT RELEASE-RE' PORT
- AVERAGE ANNUAL RELATIVE CONCENTRATIONS: l LData' Period: -1988- ;4 UNDECAYED AND UNDEPLETED PARTICULATE,il of 3 1
i l
l i
_____________ ..___ . ____________.. _____ ..... ____________.___ l i
. KILOMETERS--> 0.4 .: 1.2 ~: 2.4- : 5.6 :: 10.5 : 14.5-~ :
D N -
l 1.86E-06 3.40E-07 ! 1.48E-07 : 5.46E-08 : 2.64E-08 : 1.79E-08 :
-NNE. .: 2.20E-06 : 4.17E-07 ! 1.76E-07 : 6.17E-08 : 2.84E-08 :'1.89C-08':
NE =1.97E-06 : 3.55E-07-l 1.44E-07 : 5.24E-08 :.2.51E-08 :;1.71E-08.
ENE : 1.90E-06 : 3.29E-07 : 1.30E-07 ! 4.76E-08 : 2.29E-08 : 1.56E-08 :
~
E. ! 1.38E-06l: 2.50E-07 1.00E-07 3.42E-08.: 1.5YE-08~ 1~.07E-08 !.
ESE- l 1.11E-06 : 1.89E-07 : 7.83E-08': 2.85E-08 '1.37E-08 : 9.30E-09 :
- i
' SE ' ___ _______._1.11
___ E_06. __: 1.93E 07 ! 8.45E-08 3.30E 08 : 1.62E 08 : 1 11E-08 .
....._____....__________ ____________ i SSE : 7.29E 07,!
_. ___________________.____1.33E_07 _____ ___ : '6.19E_08
___ ___ ...___ :'2.49E_08
..._ _____ . .__ _ _1.27E_08 : 8.46E-09__'
S : 7.04E 1.28E-07 :____ ______________. 2.40E-08 1.16E 08- 7.90E 6.12E V8 : _________........__________, .________.'.. 09 -
. ______.... .___-07._! i SSW 9.43E-07 : 6.8?E 08 !.2.60E-08 : 1.29E 08 8.91E 09 :
1.60E_07 _ _ _ _: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._.
SW :: 1.53E-06 : 2.59E-07 : 1.01E-07 : 3.55E-08 : 1.68E-08 : 1.14E-08 :
.WSW : 1.42E-06 2.34E-07-: 9.06E-08 1 3.30E-08 : 1.63E-08 : 1.13E-08 :
-W : 1.26E-06 2.05E 07.: 7.71E 08 : 2.81E-08 ! 1 38E 08 : ?.60E 09 !
WNW' : 7.37E-07 1.22E-07.! 4.94E-08 : 1.92E _08 : 9.82E ,
___ _________-09 :.6.95E_09 _:
1 NW : 8.56E-07 2.47E 08 : 1.24E 08 : 8.71E 09 : i;
__...._____ ....___...______________. 1.46E 07 : 6.40E.__08 .._________.____...____________ ___ _
'NNW : 1.11E 06 : 1.99E 07 : 8.65E 08 : 3.24E 08 : 1.57E______...____-08 08 : 1.07E :____ i i
k a
i
(
57
'd._ i i g; . . ,
.V l
-o ,
u i
d TABLE.10,.Page 2fof 12' SEMIANNUAL" RADIOACTIVE' EFFLUENT RELEASE REPORT. I AVERAGE ANNUAL RELATIVE CONCENTRATIONS-Data Period: 1988-
-UNDECAYED AND UNDEPLETED PARTICULATE, 2Lof 3
~
1
. .?
q KILOMETERS __>
20 1 .: -28.2 : -36.2 44.3
_ ___________________..___________________________________ : 52.3 : ~60.4 N : 1 22E-08 : .8.18E-09-! 6.09E-09.: 4.83E-09 : 3 98E-09:* 3.37E-09. .
NNE : 1.24E-08 : 8.28E-09 : 6.09E-09 ::4.77E-09 : 3.90E-09 :-3.29E-09 :
NE: -! 1 16E-08 : 7 78E-09-! 5.80E-09 : 4.59E-09 : 3.79E-09
- 3.21E-09 :
-ENE : 1.06E-08 : 7.16E-09 : 5.34E-09 : 4.24E-09 3.50E-09 : 2.97E-09 :
E
_ _ _ _ _ _ _: _ 7.18E 09 : 4.82E 09 : 3.59E 09 ESE :-6.33E-09 : 4 27E-09 : 3.20E-09. 2.54E-09 ; 2.10E-09 : 1.78E-09 :
SE-
- 7.50E-09 ; 5.04E-09 3.'75E-09 2.96E-09 : 2.44E-09 2.07E-09 )
SSE. 1.5.78E-09 3.91E-09 : 2.92E-09 : 2.32E-09 1.92E-09 : 1 63E-09 : .j S- :-5.36E-09 ! 3.'41E-09 ; 2.69E-D9 t 2.13E-09 : 1.76E-09 : 1.49E-09 :
SSW' 6.15E-09 : 4.21E-09~; 3.17E-09 : 2.53E-09J2.10E-09 1.79E-09 :
SW i 7 76E 09 : 5.24E 09 t 3.93E 09 t 3.12E 09 : 2.58E 09 l 2.19E 09 :
-WSW : 7.89E-09': 5.46E-09 l-4.15E-09 . 3.33E-09 : 2.78E-09 2.38E-09 :
W 6.67E-09 : 4.60E-09 : 3.49E-09 2.80E-09 : 2.33E-09 : .1.99E-09 : ;
WNW ' 4.91E-09't 3 44E-09 : 2.63E-09 2 13E-09 : 1.78E-09 : 1.53E-09 :
NW 6.11E 09 : 4.26E 09 : 3.25E 09 : 2.62E 09~; 2.19E-09 : 1.SSE 09 :
L 2.04E-09 :
. N N W ' _ _ ______
____ _~ . 7.28E 09 : 4.91E 09 : 3.67E-09
________________________________________ : 2.91E-09
__ ______ __ ...__._______ l 2.40E-09
]
58
.i e d.
4 e
.f
~.
TABLE 10, Page 3 of 12 i
SEMIANNUAL-RADIOACTIVE EFFLUENT RELEASE REPORT l AVERAGE ANNUAL RELATIVE-CONCENTRATIONS-Data Period: 1988 '
UNDECAYED AND UNDEPLETED PARTICULATE, 3.of 3 ;
l' v
-l 68.4 76.5 :
KILOMETERS N : 2 92E-09 : 2.58E-09 : j NNE : 2.84E-09 : 2.49E-09 : i NE : 2.78E-09 : 2.45E-09 :
ENE : 2.57E-09
_______..__....__.__..__ 2.27E _09 :
E : 1.72E-09 : 1.52E-09 :
ESE : 1.55E-09 : 1.36E-09 :
SE : 1.79E-09 1.57E-09 :
SSE : 1.41E-09 : 1.25E-09 :
S : 1.29E-09 : 1 14E-09 l SSW : 1.56E : 1.38E-09 : '
______ ___________-09 _..___ ....____ ~
WSW 2.08E-09 l 1.84E-09 : - l 1
- 1.74E-09 : 1.54E 09 :
W WNW 1.34E 09 : 1.19E
___________.._______...._-09 -___
NW : 1.64E 09 : 1.46E 09 :
NNW : 1.77E 09 : 1.56E 09 :
e i
59 j
= _ _ . - _ - - . - - _ _ ___ _ . _
s
.. ?
? 15 i f54 i- .
'I'
- -l
.l 1
TABLED 10, Page 4'of 12 SEMIANNUAL' RADIOACTIVE. EFFLUENT RELEASE' REPORT AVERAGE ANNUAL RELATIVE CONCENTRATIONS' Data Period:- 1988 DECAYED NOBLE GASES, 1 of 3 i
I
-KILOMETERS-->: 0.4- - -1.2 ! 2.4 5.6 ': 10.5 : 14.5 :
N. .
1.84E-06 ; 3.40E-07 1.47E-07 5.43E-08 : 2.60E-08 : 1.76E-08 :-
NNE- .: 2 20E-06 l 4.17E-07 }-1.75E-07l: 6.14E-08 2.81E-08 :-1.86E _08 : -
^ NE -l 1.97E-06 : 3.54E-07 1.44E-07 : 5.21E-08:: 2.48E-08 : 1.68E-08._ 4 ENE ~1.90E-06' ~3.29E-07 : 1.30E-07 4.73E-08 : 2.27E-08?: 1.54E _ _ _ _ _: _1.38E _ _ 06 _ _:.2.50E
_ _ _07 _ :_9.98E
_ _ _08_-3.40E
_ _ _ 08 _ _- 1.57E
_ _ _08..:
_ _1.05E_ _ _08_ :_ _ _ _ _ _ _
E i
_ 4
-ESE - '1 11E-06 : 1.88E-07 7 81E-08 :-2.83E-08 : l'.34E-08 : 9.06E-09-! .!i
- SE : 1.11E 06 : 1.92E 07 ! 8.43E 08 ! 3.27E-08
- 1.59E-08 : 1.08E 08 :
]
SSE 7.28E-07 ! 1.32E-07 : 6.17E-08 2.47E-08-: 1.21E-08 : 8.28E-09-!' .
SL '7.04E 07 ! 1.28E 07 : 6 10E'08f 2.38E 08. 1 15E 08. .7.76E-09 :
SSW 9.42E-07 : 1 60E-07 '6.87E-08 2 58E-08 l 1.27E-08 : 8.'72E-09 SW- l11.53E-06 2.59E-07 :'1.01E-07-: 3.52E-08 1.65E-08 : 1.12E-08 :
WSW ! 1.42E-06' 2.34E-07 : 9.03E-08 : 3.27E-08 : 1.60E-08 : 1.11E-08 : i W 1.25E 06 : 2.05E-07 : 7.69E 08 : 2.78E-08 1.36E-08 : 9.41E-09 :
WNW 7.37E 07 ! 1.21E-07 : 4.91E 08 : 1.90E 08 :.9.63E 09 : 6.76E 09
- NW i 8.55E 07 1.16E 07 : 6.37E 08 2.45E 08 : 1.22E 08 : 8.51E-09 :
NNW 1 11E-06 -1.99E-07 : 8.62E-08 : 3.22E-08 : 1.55E-08 : 1.05E-08 : J 1
1 4
l 3
60
TABLE 10, Page 5 of 12 h
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AVERAGE ANNUAL RELATIVE CONCENTRATIONS Data Period: 1988 DECAYED NOBLE GASES, 2 of 3 20.1 : 28.2 36.2 : 44 3 : 52.3 : 60.4 :
KILOMETERS _->
N : 1.18E-08 : 7.86E-09 : 5.79E-09 : 4.53E-09 : 3 69E-09 : 3.09E-09 :
HNE
- 1.23E 08 : 3.05E-09 : 5.87E 09 l 4.57E 09 : 3.71E 09 : 3.10E-09 :
NE : 1.13E-08 : 7.55E-09 : 5.5SE-09 : 4.38E-09 : 3.58E-09 : 3.01E-09 :
ENE : 1 04E 08 : 6.95E 09 : 5.14E 09 : 4.04E 09 : 3.31E 09 : 2.78E 09 :
i : 4.67E 09 : 3.45E 09 : 2.71E 09 : 2.21E 09 : 1.86E 09 :
E_______________'7.03E_09 .. _ ____________ ___._________________ ________________________
ESE : 6.08E-09 : 4.03E-09 2.96E-09 : 2 31E-09 : 1.87E-09 : 1.57E-09 :
SE : 7.22E-09 : 4.77E-09 3.50E 09 ; 2.73E-09 : 2.22E 09 : 1.86E-09 :
________________== ___...__. _______..___.__.____ ..__.___..______---__________
SSE : 5 61E 09 : 3.75E-09 : 2 78E-09 : 2.18E-09 : 1.78E 09 : 1.49E-09 :
S : 5.23E-09 : 3.49E-09 2.58E-09 2.02E 09 : 1 65E 09 : 1.39E-09 : ._.
_ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . - - - - _ _ - - . . . _ _ _ _ _ _ _ _ = =.________ ______________-
SSW : 5.96E-09 : 4.03E-09 : 3.00E-09 : 2.36E-09 : 1.93E-09 1.63E-09 :
SW 7 53E-09 : 5.03E-09 : 3.72E-09 : 2.92E-09 2 39E-09 : 2.01E-09 :
WSW 3.94E 09 : 3.13E-09 : 2.58E
- 7.67E 09 : 5.25E-09-___..._______.._......_____.____.____ 09 : 2.18E 09 :
W : 6.49E-09 : 4.44E-09 : 3.33E-09 ; 2.64E-09 : 2.18E 09 : 1.85E-09 :
WNW 4.72E 09 : 3.26E 09 2.46E 09 : 1.96E 09 : 1.61E 09 : 1.36E
________..______...._________________-09 ____.
NW : 5 91E 09 : 4.06E 09 : 3.06E 09 : 2 01E 09 : 1.70E
- 2.44E ______________________-09
________________________________________.._ ..._______-09 :_____
NNW : 7.09E-09 : 4.74E-09 : 3.50E-09 2.75E-09 : 2.24E-09 : 1.8SE-09 :
e 61
4-
. .=
TABLE 10, Page 6 of 12 SEMIANNUAL RJ.DICACTIVE EFFLUENT RELEASE REPORT AVERAGE ANNUAL RELATIVE CONCENTRATIONS Data Period: 1988 s
I i
DECAYED NOBLE GASES, 3 of 3 KILONETE.S-->
7 68.4 : 76 5 :
N : 2 65E 09 : 2.31E 09 :
NNE ! 2.31E-09 :
- 2.65E ________________
___......___________-09 NE : 2 59E 09 : 2 26E-09 :
ENE : 2 39E 09 : 2.09E-09 :
E : 1.60E 09 : 1 40E 09 : .
- 1 34E : 1.16E
_- 0 9 : '
ESE.-____ ___.____....._-09 SE : 1 59E-09 : 1 38E-09 SSE .1 28E 1.12E-09 : ,
j
...__.-___..._______-09 :......__________- l S : 1.19E-09 : 1.04E-09 ;
SSW : 1.40E-09 : 1 22E 09 :
SW 1.50E 09 :
': 1.72E -___.___.__._-__
______-____..____ __-09 :
WSW 1.88E-09 1.65E-09 t' W : 1.59E-09 ! 1 40E-09 :
WNW : 1.18E-09 : 1 03E 09 : 4 HW : 1.47E-09 : 1.28E-09 :
NNW 1.62E-09 : 1.41E-09 :
D
~
62
o 4 t
1 TABLE 10, Page 7 of.12 i a
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AVERAGE ANNUAL RELATIVE CONCENTRATIONS Data Period: 1988 i DECAYED AND DEPLETED PARTICULATE AND RADIOIODINES, 1 of 3 i
4 0.4 : 1.2 2.4 : 5.6 : 10.5 : 14.5 :.
KILOMETERS __>:.....__________________....____________________________________
...._______ i N : 1.77E-06 :
3 05E-07 ! 1.29E-07 : 4.60E -
_08 : 2.16E-08 : 1.44E-08 :
NNE : 2.08E-06 : 3.73E-07 ; 1.52E-07 5.10E-08 2.26E-08 : 1.47E-08 :
NE
_______ _______ : 1.87E _06 : 3.17E
__ __ .____ 1.24E-07 4.31E 08 : 1.99E 00 : 1.32E-08 :
_07__.____________________________________________ )
- 1.80E-06 ENE 2.94E-07 ; 1.11E _07 : 3.88E 08 : 1.79E 08 :______________ _-08 : 1.19E E : 1.31E 06 2.24E 07 : 8.63E 08 2.80E 08 : 1.25E-08 : 8.18E
________________________________________________________ ____.. _______-09 _____
ESE <
1.06E 06 : 1.69E 07 : 6.81E-08 : 2.38E 08 : 1.10E 08 7.37E 09 :
SE : 1.06E-06 : 1.75E-07 : 7.41E-08 ; 2.80E-08 1.33E-08 : 8 94E-09 :
SSE : 6.92E 07 1.20E 07 : 5.48E 08 : 2.15E 08 : 1.04E 08 : 6.99E 09 : I S : 6.71E 07 1.16E 07 : 5.44E 08 2.07E 08 : 9.74E 09 : 6.51E 09 : i.
SSW : 8.96E 07 1.44E-07 : 6.01E 08 : 2 19E 08 : 1.05E 08 : 7.15E 09 :
___.-_________-- 1.45E_06 2.32E 07 : 8.68E 08 2.88E 08 1.30E-08 : 8 58E-09 :
WSW 1 34E 06 2.09E 07 : 7.75E 08 : 2 66E 08 : 1.26E-08
- 8.60E
.._________-09 :_____ '
_ _ _ _ _ _ _ _ _! 1 W _ 19E
_ _ _ 06 _ _ _ _1.83E____ 07_ :_6.57E
_ _ _ _08 _ _ _ 2.25E
_ _ _ _08 _ _: _1_ 06E
_ _ _08_ _: .7.18E ,.___ 09 ;
WNW
- 7 00E_07_== ______ 1.09E ___-07
- 4.27E
______...___-08
- 1.59E
_______.._-08 ._______-09
- 7 90E : 5.51E 09 :
NW 8.15E 07 1.32E 07 : 5.59E 08 : 2.09E 08 : 1.03E-08 : 7.09E-09 :
NNW : 1.05E 06 1.79E 07 : 7.52E-08 ; 2.73E 08 1.28E-08 : ,8.60E-09 : ;
4 63
~ - . _ _ _ . ___- - _ -
ei ,
+ '
, j l
1,.- 1 1
i
- TABLE 10, Page.8 of 12 1
SEMIANNUAL RADIOACTIVE ~ EFFLUENT RELEASE / REPORT l
- AVERAGE ANNUAL RELATIVE CONCENTRATIONS l Data Period:- 1988 :)
DECAYED.AND DEPLETED PARTICULATE AND RADIOIODINES, 2 of 3- j i
i KILONETERS-->: 20.1 : 28.2 .36.2 .: 44.3 : 52.3 60.4 !
N : 9.61E-09 : 6.31E-09 :-4.61E-09 3.58E 09 2.90E 091: 2.42E-09 :
NNE : 9.47E 09 : 6 05E 09 : 4.34E 09 3.32E 09 2.66E
_____________________________ ______________________________-09
- 2.20E
__________-09 _____
NE : 8.74E-09-! 5.72E-09 4 17E-09 f 3.24E-09-! 2 62E-09 2.18E-09 l' 7.90E : 5.17E-09 : 3.77E-09
_ _ _ _ _ _ _ _ _ _ _ _ _ _2.92E-09_ _ _ _ :_2.36E-09 _ _ _ _ _: 1.97E-09_ _ _ _ _!_ _ _ _ _ _ _ _ai ENE
_____________'_ ______-09 E .: 5.38E-09 3.51E-09 l 2.56E-09 : 1.98E-09': 1.61E-09 : 1,34E-09 :
ESE~
- ~4.89E-09 : 3.21E-09-_______
.____________________________ ! 2.34E _09 : 1.82E 09 ___________ 1 47E 09 : 1.22E 09 : l
________________________ j SE ! 5.93E-09 : 3.87E-09 2.81E-09 : 2 17E-09 : 1.75E-09 :~1.46E-09 : i SSE :
_______________'4.68E_09.:
3.10E 09 : 2.27E 09 : 1.77E 09 : 1.44E 09 : 1.20E_____ :
______________'________________________________________-09 S, 4.33E-09 1.2.85E-09 2.08E-09 : 1.62E-09 : 1.31E-09 : 1.10E-09 :
SSW -: 4 84E-09 : 3.24E-09 2.39E-09 l'1.88E-09-! 1.53E-09 : 1.28E L .SW- : -5.67E-09': 3 71E-09 ! 2.71E-09 : 2.10E-09 ! 1 70E-09 -1.42E-09 :
WSW- 5.87E-09 : 3.97E-09 ; 2.96E 09 : 2.34E 09 : 1.92E-09.: 1.61E-09 :. .i L ________________________________________________________________________________ -l W' .
4 88E-09 i'3 28E-09 : 2.44E-09 : 1.92E-09 : 1.57E-09 : 1.32E-09 :
WNW : 3 83E 09 ! 2.63E-09 : 1.98E-09 : 1.57E-09 : 1.30E 09-::1.10E :
_______________________________________ _________________________________-09 _____
NW : 4 90E-09 : 3.36E 09 : 2.52E-09 : 2.01E : 1.65E-09 : 1.40E-09 :
_________________________________~______- -________-09 ___________________________
NNW. ! 5.73E 09 : 3.78E 09 2.76E 09 : 2.15E 09 1 74E-09 : 1.46E 09 :
l 64 i
= - _ =___- _ _ _
,. . <p- 4
.c )
s 5 a
l 1
TABLE 10, Page 9 o'f 12 a, SEMIANNUAL RADIOACTIVE EFFLUENT'KELEASE~ REPORT AVERAGE ANNUAL' RELATIVE CONCENTRATIONS
. Data Period: 1988 s
DECAYED AND-DEPLETED PARTICULATE AND.RADIOIODINES, 3 of 3 i
KILONETERS--> 68 4- 76.5 1 N. 2.06E-0? l'.78E-09 !
]
, a NNE : 1.86E 09 : 1.61E 09-
}
NE
- 1.86E 09 : 1 61E
___________________________-09 ____
ENE. 1.68E-09 1.45E-09 :
E : 1 14E-09 : 9.87E-10 : .
. ESE : 1.04E 8.96E 10 :
.___ ______________-09 _______________ -
SE : 1.24E 09 : 1 07E 09 : {
SSE -l 1 03E
____ ___________-09 ..._________! 8.92E__10
___ 1 9.34E 10 8.10E 10 : i S'____________
i SSW 1.10E-09 : 9.57E 10 : ,
____________________________________ 1 SW 1.21E 09. 1.04E :
_______________________________-09 _____ j
. WSW ! 1 39E 09 ! 1.21E : '!
_______________________________-09
(
W 1.13E-09 : 9.R5E-10 ! i WNW . : 9.46E 10 : 8.28E 10 :
NW : 1.21E 09 1.06E 09 : I i
HNW :-1.24E 09 : 1.08E 09 :
l I
i l
l 65
=. t
_ _ _ __m_-__ - _ - _
r l
t
!. .C.
t-J. -
r I
{
TABLE 10, Page 10 of 12 l l
\
' SEMIANNUAL \DIOACTIVE EFFLUENT RELEASE REPORT AVERAG NNUAL RELATIVE CONCENTRATIONS i Data Period: 1988 -
}
DECAYED AND DEPLETED PARTICULATE l AND RADIOIODINES (DISPOSITION), 1 of 3 ;
r
,i i
4 1
l KILOMETERS--> 0.4 : 1.2 : 2.4 : 5.6 : 10.3 : 14.5 : )
N 5.33E 1.88E 09 : 4 67E-10 : 1 64E
- 2.29E _08
- -09__--_______
- ._____...____ __ __-10 : 9.51E-11 :
NNE : 2.50E-08 : 5.22E-0? : 1.84E-09 : 4.57E-10 : 1 59E-10 : 9.03E-11 : 4 l
NE : 1.49E-08 : 3.55E-0? 1.23E-09 : 3.05E-10 : 1.06E-10 ______._____ 6.09E-11 : l ENE t'1.53E-08 : 3.08E-09 : 1.06E-09 : 2.62E-10 : 9.05E-11 : 5.15E-11 :
E
- 2.02E-08 : 4.31E-09 : 1.49E-09 : 3.64E-10 : 1.26E-10 .._______
__...______ ____________...____________ .________ .._________ ___ -7.24E__._11 : a ESE
- 2.10E-08 : 4.49E-09 : 1.55E
= = _ _ - ____ _09 : 3.79E 10 : 1.32E 10 : 7.54E 11 :
SE : 1.43E 08 3.36E 09 : 1.20E 09 : 3.04E 10 : 1.07E 10 : 6.22E 11 : 1 SSE : 8.92E-09 : 2.23E-09 : 8.20E 10 : 2.10E 10 : 7.46E 11 4.34E 11
-= ____________ ...______ _____________ ______
S ! 9.11E 09 : 2.44E-09 : 9.19E 10 : 2.39E 10 : 8.55E 11 : 5.01E 11 f 4
______.._.. ____...__________ ...._____________________________________________. 3 SSW !.1.24E-08 2.92E-09 : 1.04E-0? : 2.61E-10 : 9.20E-11 : 5.34E-11 : ;
2.44E 10 : 8,51E-11 : 4.90E 11 !
_ _ _ _ _ _1.32E . . .08. .: 2_85E
_ _09_: _9.90E-10 _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _)
' WSW 7.61E-09 1.68E-09 : 5.85E 10 : 1.45E-10 : 5.08E 11 : 2.93E-11 : 1 W
- 5.90E-0? : 1.29E-07 : 4.44E-10
- 1.08E-10 : 3.80E 11 2.195
__.___________________,__________-11 ___
l' UNU 4.01E-09 : 1.0SE-09 : 3.85E 10 : 9.57E-11 : 3.44E-11 ! 2.03E-11 :
WW :........._.
8.06E-09....____
- 2.14E........_______________
0? : 7.71E 10
- 1.94E 10 : 6.93E 11 : 4.08E 11 :
NNW 1.1SE 00 2.78E 09 : 9.84E-10 : 2.44E 10 : 8.58E-11 4.98E 11 :
i l
+
F 66
i
/ 4 l
l .
E i TABLE 10, Page'11 of 12 i
l- SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AVERAGE ANNUAL RELATIVE CONCENTRATIONS Data Period: ~1988 l 3
DECAYED AND DEPLETED PARTICULATE AND RADICIODINES (DISPOSITION), 2 of 3 1 I
20.1 : 28.2 36.2 : 44.3 : 52.3 : 60.4 :
KILOMETERS __>:
N : 5.51E 11 : 3.17E 11 : 2.11E 11 : 1.53E 11 : 1.17E-11 : 9.39E 12 :
- === .____ _.____. ,
NNE -5.11E 11 : 2.85E 11 : 1.85E 11 : 1.31E 11 : 9.91E-12 : 7.82E 12 :
______ ___________________________ __. _________________________._______________ i NE~ : 3.48E 11 : 1.96E 11 : 1.29E 11 9.22E 12 : 7.05E-12 5.64E 12 : 1
_ _______...___________...______.______________ _.. __ ..._____.._-_____ .______ c ENE : 2.91E 11 : 1.63E 11 : 1.05E 11 7.47E 12 : 5.65E 12 : 4.47E-12 :
E 4.13E-11 : 2.33E 11 : 1.53E-11 : 1.09E 11 : 8.24E 12 : 6.50E-12 :
i
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . . . . _ _ _ _ _ _ _ _ _ _ _ = -
- 4.31E 11 : 2.44E 11 : 1.60E 11 : 1.14E-11 8.62E 12 : 6.7?E-12 l ESE SE : 3.61E 11 : 2.08E 11 : 1.38E 11 : 9.99E 12 : 7.64E 12 : 6.0SE 12 :
SSE : 2.53E 11 : 1.47E-11 : 9.83E-12 : 7.15E-12 : 5.51E-12 : .12E-12 : .
..__ .._.__.__________.._..____...___________..._____ ___.________.__._ ~
S
- 2.94E-11 ! 1.72E 11 : 1.16E 11 : 8.46E-12 : 6.52E_12 : 5.21E 12 :
SSW : 3.10E 11 : 1.79E 11 : 1.19E 11 : 8.63E-12 : 6.60E 12 : 5.25E 12 :
SW 2.81E 11 : 1.60E 11 : 1.05E 11 4 /.56E-12 : 5.76E 12 : 4.5SE 12 :
~ USW 1.69E-11 : 9.67E 12 : 6.41E 12 : 4.66E 12 : 3.60E 12 : 2.92E 12 :
W : 1.26E 11 : 7.24E-12 4.80E-12 : 3.49E 12 : 2.70E 12 : 2.1?E-12 :
- 1.21E-11 : 7.23E-12 : 4.?5E 12 : 3.66E 12 : 2.86E 12 : 2.31E 12 :
WNU NW : 2.42E 11 : 1.43E 11 : 9.71E-12 : 7 13E 12 : 5.53E 12 : 4.14E. 12
- k NNW
- 2.89E-11 : 1.67E 11 : 1.11E-11 : 8.08E-12 : 6.21E 12 :.1.96E 12 :
67
= b
. . i l
. i i
l TABLE 10, Page 12 of 12 8EMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AVERAGE ANNUAL RELATIVE CONCENTRATIONS-Data Period: 1988 DECAYED AND DEPLETED PARTICULATE AND RADIOIODINES (DISPOSITION), 3 of 3 68.4 ! 76.5 :
KILOMETERS-
____________________e_.
N : 7.73E 12 : 6.50E 12 :
NNE : 6.37E-12 : 5.31E-12 :
NE : 4.66E 12 ; 3.93E 12 :
ENE : 3.66E 12 : 3.07E :
____ _______..__________________-12 -.
E .;
5.20E-12 : 4.39E-12 :
.ESE_ _ _ _ _ _ t_5.52E-12 _ _ _ _ _* '4.57E-12 _ _ _ _ . :. . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
SC : 4.98E 12 4.16E 12 :
l SSE
- 3.64E 12 : 3.06E 12 :
S
- 4.27E 12 : 3.57E 12 :
- 4.30E 12 : 3.59E 12 ! _
9 s
SW 3.75E !2 : 3.14E 12 :
WSW 2.43E-12 : 2.08E 12 :
W 1.83E-12 : 1.56E 12 ! I WNW 1.91E-12 : 1.62E-12 : ?
NW : 3.66E 12 : 3.07E 12 :
NNW
- 4.08E-12 : 3.42E-12 :
m 68
1 -i r
.. .9 i
i l
l SECTION 6
\
, DOSE MEASUREMENTS AND ASSESSMENTS l
i a
M 69 I
l.
TABLE 11 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MAXIMUM
- OFF-SITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC Data Period: 1988 DOSE ***
Source 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year **
1 1 1 **** 1 1 A. Waterborne j Effluents (mrem) 2.84E-02 6.02E-02 1.17E-02 6.16E-04 1.01E-04 !l 2 3 4 5 5 B, Airborne Effluents
- 1. Iodines and Particulate .6.11E-04 1.06E-04 6.24E-04 1.18E-02 1.22E-02 (mrem) 6 7 8
- 2. Noble Gases: Gamma 6.55E-05 7.13E-05 0 0 1.23E-04 (mrad)
- 6 7 8 Beta 8.39E-05 9.13E-05 0 0 1.57E-04 9 9 9 9 9 C. Direct Radiation 0 0 0 0 0 (mrem)
THERE ARE NO OTHER URANIUM FUEL CYCLE FACILITIES WITHIN 8 KM OF CPS -
- " Maximum" means the largest fraction of the corresponding Appendix I dose design objective.
- " Maximum" dose for the year may not equal the sum of the quarterly maximum doses because the doses may have been to different organs or at different receptor locations.
l3
- The numbered footnotas on the following page briefly explain how each l maximum dose was calculated, including the organ and predominant _
pathway (s).
70 I- .. _ _ _ - . _
d
c !
[
1 Footnotes for Table 11
- 1. Dose to the adult GI-LLI tract by the fish pathway.
o Calculated using . methodology contained in the CPS Offsite Dose Calculation Manual-(ODCM).
l
- 2. Dose to theLchild thyroid via the inhalation, ingestion i _- (grass-cow-milk), and. ground-plane pathways.
! Calculated at 4.5 miles ESE using methodology contained in the CPS ODCM.
- 3. Dose to the adult thyroid via the inhalation, vegetation and ground-plane pathways. . Calculated at 0.9 miles N using methodology contained in the' CPS ODCM.- l
- 4. See Footnote 3.
- 5. Same as Footnote 3, except the critical organ is the "
adult GI-tract.
- 7. 'Same as Footnote 6, except d. -a was calculated at .76 miles E.
- 8. Same as Footnote 6.
9.. Based on environmental th'ermoluminescent dosimeters placed near CPS in unrestricted areas'(see " Method for TLD Data Analysis" on the following page).
a
, 71
METHOD FOR TLD DATA ANALYSIS The h i storical relationship between CPS Radiological
- Environmental Monitoring Program preoperational TLD .
locations'within 0.5 miles of' CPS and the 1988'TLD's at the l same locations were used to estimate radiation levels at '
these TLD locations.
TLD values for the preoperational period (1985 and 1986) were compared to 1988 TLD values by means of a t-test.
The 1988 data does not represent a statistically different population from the preoperational population at the 95% 1 confidence level. It can be concluded that radiation levels !
measured at the 1988 TLD locations
- were not different from l
preoperational radiation levels. Direct radiation from CPS is therefore estimated to be O mR.
- 1988 TLD LOCATIONS: CL-23, CL-24, CL-25, CL-26, CL-28, CL-83.
l-s 1
& I 72 o.
'k v.,..
DOSES TO MEMBERS OF THE PUBLIC WITHIN THE SITE BOUNDARY I
l l CPG Technical Specification 6.9.1.7 requires that the Semiannual Radioactive Effluent Release Report be. submitted within 60 days after January 1 of each year and 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 for the previous year.
The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents shall be used for determining the gaseous pathway doses. Within the CPS site boundary there are seven areas which are open to members of the public as identified by CPS ODCM Table 3.4-3 (see Figure 8):
A road at 0.3 miles in the SE sector An agricultural acreage at 0.9 miles in the SW sector A portion of Clinton Lake at 0.2 miles in the NW sector The Department of Conservation Recreation Area at 0.8 miles in the ESE sector A residence at 0.8 miles in the SW sector A residence at 1.5 miles in the.WSW sector A residence at 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 1988 Annual Land Use Census. All dose calculations were performed using the methodology contained in the CPS ODCM.
73 )
FIGURE 8 AREAS WITHIN TIIE CPS SITE BOUNDARY OPEN - -Zv TO MEMBERS OF THE PUBLIC ]
CLINTON M '~
/
/
/= '
~
y Notes WAPELLA l MAROA , .... , ,,,, ,. ,s. ...,,..., ......
. ................i.m,.,,,,,,.
(o
.. . .....s... ......
e
, 2 ci. ...,c... . m . .. .s. ... .... ......
. ........ .,c. ........ .......... ....
,, m ,. ,,, ,s. ....... .,...., ...,.,
. ......... ..i,,. ,,, ,,. .... .... ......
. ......... .....,. ,,, ,s. ........,s.... ...... 1 7 ......... . 7 m . .. ,,,. .. . ... . .... ......
d d u .
Y '
3 8 s 5 i
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d P
1 N C .P.S.
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HACON CO. WELDONpff 4 ,
PIATT CO. b CISCO ce 72 A 7 4 7,# co >
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FARMER DELAND CITY ///
/
- 150 i
TO l ,
CHAMPAIGN 74 l
l 74 1
4
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TABLE 12 l SEMIANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING
-USE OF THE ROAD IN THE SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY. '
, Data Period: 1/1/88 - 12/31/88 ExDosure Pathway Orcrans Dose (mrem) ;
plume
- total body 3.76E-06 skin 9.97E-06 ground plane * : total body 5.55E-04 skin 6.53E-04 inhalation; four highest organ doses:
teen lung 2.50E-05 child lung 2.50E-05 adult lung '1.95E-05 infant lung 1.67E-05 .
- Doses via these pathways are not dependent upon age-group.
75
TABLE 13 SEMIANNUAL RADIOACTIVE EFFLUENT, RELEASE REPORT j CALCULATED DOSES TO MEMBERS OF THE PUBLIC '
DURING USE OF THE AGRICULTURAL ACREAGE IN THE SOUTH-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 1/1/88 - 12/31/88 EXDosure Pathway Orcang Dose (mrem) plume
- total body 2.38E-06 skin 6.29E-06 ground-plane
- total body 2.27E-04 skin 2 . 6 7 E - 0.4 o
inhalation; five highest organ d'ses:
teen lung 1.49E-05 child lung 1.16E-05 adult lung 1.16E-05 adult thyroid 7.17E-06 infant lung 7.17E-06
- Doses via these pathways are not dependent upon age-group.
4 M
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TABLE 14 -
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF CLINTON LAKE IN THE NORTHWEST SECTOR WITHIN'THE CPS 1 i'
SITE BOUNDARY Data Period: 1/1/88 - 12/31/88 Excesure Pathway Oraans Dose (mremi plume
- total body 3.66E-05 skin 9.69E-05 ground plane
- total body 8.10E-05 '
skin 9.51E-05 inhalation; four highest organ doses:
child _ thyroid 6.60E-05 teen thyroid 6.10E-05 infant thyroid 5.50E-05 adult thyroid -
5.20E-05 i
- Doses via these pathways are not dependent upon age-group. ;
4 m
77
16 TABLE 15 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 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 Data Period: 1/1/88 12/31/88 Exposure Pathway Orcans Dose (mrem) plume
- total body -1.77E-05 skin 4.68E-05 ground plane
- total' body 2.51E-05 skin 2.94E-05 inhalation; four highest organ doses:
child thyroid 9.24E-06 teen thyroid 8.84E-06 adult thyroid 7.74E-06 infant thyroid 7.44E-06 1
- Doses via these pathways are not dependent upon
' age-group.
e l
l 78 l
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, . 1 TABLE 16 SEMIANNUAL RADIOACTIVE EFFLUENT-RELEASE REPORT l
-CALCULATED DOSES FOR THE RESIDENCE IN~THE. SOUTHWEST SECTOR WITHIN i THE_ CPS SITE. BOUNDARY Data Period: 1/1/88 - 12/31/88 Exoosure Pathway Orcans Dose-(mrem) l l
plume
- total body 8.09E-05 skin 2.14E-04 !
I i
ground plane
- total body 7.96E-04 ;
skin. 9.36E-04 inhalation; five highest organ doses: )
i teen lung 1.27E-04 j teen thyroid 1.13E-04 ;
adult lung 1.12E-04 ;
child thyroid 1.09E-04 j child lung 1.09E-04 i
- Doses via these pathways are not dependent upon l age-group. l i
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_ _ - _ _ - _ _ . . - - _ _ _ _ - _ _ _ i
d
. - .3 TABLE 17
. SEMIANNUAL RADIOACTIVE EFFLUENT. RELEASE REPORT l CALCULATED DOSES FOR THE RESIDENCE IN THE WEST-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 1/1/88 - 12/31/88 Excosure Pathway Oraans Dose (mrem) plume
- total body 2.07E-05 skin 5.48E-05 1
ground-plane
- total body 2.13E-04 l skin 2.51E-04 inhalation; five highest. organ doses:
O :
teen lung 3.54E-05 teen thyroid 3.04E-05 child lung 3.04E-05 child thyroid 3.04E-05 adult lung 3.04E-05
- Doses via these pathways are not dependent upon age-group. .
i e
80
4
- 'g i TABLE 18 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALCULATED' DOSES FOR THE RESIDENCE IN THE SOUTH-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 1/1/88 - 12/31/88 4
Exoosure Pathway Qrg.a_rts . pose (mrem) l plume
- total body 6.86E-06 skin 1.81E-05 ground plane
- total body 1.15E-03 skin 1.36E-03 inhalation; three highest organ doses:
teen lung 5.53E-05 child lung 4.53E-05 adult lung 4.53E-05
- Doses via these pathways are not dependent upon age-group.
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l BECTION 7 j
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CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND THE SOLID WASTE PROCESS CONTROL PROGRAM 3 l
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I CHANGES TO THE-OFFSITE DOSE CALCULATION MANUAL In'accordance'with CPS Technical Specification 6.14.2 changes to'the CPS ODCM shall be reported in the Semiannual Radioactive Effluent Release Report. Revision 4 to the CPS ODCM was' approved by the CPS; Facility' Review Group on October 5, 1988. Attachment A contains' copies of the
. changed pages-and the documentation of required reviews. .A summary of revision is given on the next page.
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SUMMARY
OF REVISION Paae 2-1 Changed " Plant Service Water flow (22,000 GPM minimum)" to " Plant Service Water flow (minimum flow approximately 5000 GPM during plant shutdown periods depending.on system loads)..."
2-2 Clarified the definition of f by adding " liquid-radwaste discharge" flow setpoint...
2-3 ' Redefined liquid waste sampling frequency to agree with Tech. Spec. Table 4.11-1.
2-4 Clarified the definition of Dilution Factor (DF) by adding " equivalent to" the ratio...
2-5 Added parentheses for set point concentration (C p) I for parameter (Ftank/ fact)*
2-5 Typo; should be "(Ftank/ fact)"
3-12 Revised Table 3.4-3 to add information about annual doses at. residences identified by the 1987 Land Use census (due to incorrect values'used in calculations).
7-16 'In Table 7.2-5, _ replaced entries X/Q and D/Q for i the SSE and WSW-sectors back to the values recorded in Rev. 2-10/86 because unnecessary changes had been made to the two sectors.
7-16 Deleted comments for cow meat because the ODCM controlling location DZQ is equal to the census controlling location D/Q.
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. I CHANGES TO THE SOLID WASTE PROCESS CONTROL PROGRAM i
l In accordance with CPS Technical Specification 6.13.2 changes to the Solid Waste Process Control Program (PCP) shall be reported in the Semiannual Radioactive Effluent i i
Release Report. At Clinton Power Station the PCP consists of two documents:
CPS No. 1888.00, PROCESS CONTROL PROGRAM, which establishes process control requirements and methods.
Process Control Program - ATI Transportable Volume Reduction System (TVR) III, which implements process control requirements and methods.
Revision 3 of CPS No. 1888.00 was approved by the CPS Facility Review Group and Power Plant Manager on December 21, 1988, and revision 6 of the ATI Process Control Program was approved by the CPS Facility Review Group on September 13, 1988. Attachment B contains copies of documentation of approval by the CPS Facility Review Group for both documents.
The following is a list of all significant changes made to CPS No. 1888.00, PROCESS CONTROL PROGRAM, from Revision 2 to Revision 3. None of the changes made reduce the overall conformance of the solidified waste product to existing criteria for solid waste.
Section No. Brief Description of Chance Rev. 2 Rev. 3 1.0 1.0 A change was made to include Technical Specifications 6.9.1.7 and 6.8.1.h. A clarification was made to the procedure purpose to describe vice define the process 1
control methods.
2.1 2.1 Relocated program requirements to more appropriate sections.
Developed a discussion section which described the CPS waste streams and provided background information pertinent to the Process Control Program. Moved program requirements to more appropriate sections, other than this discussion section.
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'2.2- 2.2 Added CPS Technical: Specification
' descriptions forLProcess' Control
.s. Program and: solidification.'
- 3.0 3.0 Updated responsibilitiestsection to reflect that shipping and' waste.
. characterization is currently performed byLRadiological .
Engineering. Added the Facility ReviewlGroup's responsibility to j c review changes to the Process i control Program.- q
'5. 0 5.0 Relocated requirement to submit changes to the Process Control Program to the NRC.- Added-reference to ALARA program requirements as a prerequisite to-conducting activities related to Solid Waste Processing.
8.1 8.4.9 Relocated requirements associated 8.1.7 and with Free Standing Water.~
and 8.4.3 Relocated requirements.for 8.1.8 containers, Shipping Casks, and Packages. Provided mechanism to identify and easily update those
. procedures which implement the associated program and. regulatory ,
requirements via Radwaste Standing Order. ,
8.1.4 8.4.10 Relocated requirement.
8.1.5 8.4 Added entire new section
_ addressing contract vendors and specifying program requirements.
- Removed specific reference to l vendors to allow use of any vendor meeting program requirements.
Included 8.1.6, 8.1.7 and 8.1.1
[ into this section. Added Table 1 L which summarizes programmatic requirements for solidification ,
services at CPS.
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8.2 8.3 'These sections no longer exist as separate items. ~ Program requirements are specified'in section 8.4. 'Per discussion with NRC removed-~ requirement to seek NRC review'and approval prior to operation involving.new contract vendors that meet regulatory and-program requirements.
8.4 5.2 Relocated to prerequisite section.
8.5 8.5 Added additional administrative controls for changes to vendor Process Control Program. Removed .{
specific reference to vendor by !
name. Incorporated mechanism to identify 1and easily update a-list of vendors evaluated and approved i for use at CPS via Radwaste. !
Standing Order. Incorporated !
mechanism that can be updated easily to identify procedures j which implement program requirements.
8.6 Added a list of Technical 3 Specifications involved with'the l Process Control Program.
The following is a list of all significant changes made to ,
the Process Control Program - ATI Transportable Volume 1
-Reduction System (TVR) III, from Revision 5 to Revision 6. i ATI certifies that none of the changes made reduce the overall conformance of the solidified waste product to existing-criteria for solid waste. Changes which do not !
concern equipment performance, product quality, system safety or system effluents are considered insignificant and are not included in the following list, l
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1 .
Section No. Brief~ Description'of! Chance Rev. 5' Rev. 6 2.4.6- :2.4.6 A change'was made-to indicate that the distillate from-the TVR-III is further processed withian Ultra-filtration / Reverse Osmosis-System.
3.2.5 3.2.5 The description of-wasteLsludge was modified to' include the 1 4 possibility _of the' waste' .
containing some bead resins. The limit of 20% by volume on the 3 allowable resin-in.the waste !
sludge was deleted, since the ;
retreatment was modified to allow !
any. concentration of resins in the 1 waste sludge. ;
3.2.6 3.2.6 The definition of other wet waste' was expanded to include.the concentrate from the distillate UF/RO system. ;
4.1.1 4.1.1 A note was added to allow the use 1 of a centrifuge'for determining volume fraction settled solids.
4.1.2 4.1.2 The section was modified to allow the use of.a centrifuge'for determining volume' fraction settled solids.
5.1.1 5.1.1 Waste batch tank level was 1 modified to reflect the calibration of the new metritape i level probe. l
\
5.1.2 5.1.2 This section was modified to l require addition of sodium sulfate solution to waste sludge, due to l the possibility that the waste sludge may contain resins. Also modified to allow the addition of i sodium sulfate to be controlled by l monitoring the pH of the waste.
5.2.1 5.2.1 Figure 1 was modified to reflect _
the calibration of the new ,
metritape level probe.
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C; 5.3 5.3 This section was modified to include _the UF/RO concentrate in ,
the other wet waste section.
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6.2.2 6.2.2 This section was modified to allow decreasing bitumen flow rate, with some restrictions, when the product viscosity is very low.
7 1.5 7.1.5 This section was modified to include steam heating for heating the waste batch tank.
i 8.1 8.1 Table 1 was modified to reflect changes listed above for sections ['
5.1.2 and 6.2.2.
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SECTION 8 i
LIMITING CONDITION FOR OPERATION REPORTS O
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LIMITING CONDITION FOR OPERATION REPORTS In accordance with CPS Technical Specifications 3.3.7.11 and [
3.3.7.12 inoperable radioactive liquid and gaseous effluent monitoring instrumentation channels remaining in an inoperable condition for greater than 30 days shall be reported in the Semiannual Radioactive Effluent Release ;
Report. During this reporting period three inoperruility- ]
conditions occurred which require reporting. The following is a description of these conditions:
- 1. LCO Event: 87-07-74 Information:
Operability Requirement: Table 3.3.7.11-1.1.a Date Entered: 7/29/87 at 1745 Date Restored: 9/29/88 at 1425 Time Period: 427 days, 20.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Explanation: The cause of this Limiting Condition for Operation was presented in the Illinois Power Company Clinton Power Station '
Semiannual Radioactive Effluent Release Report for the period July 1, 1987, through December 31, 1987.
Following approval of amendment 10 to Facility Operating License NPF-62, a channel functional test was performed on the Liquid Radwaste Discharge Process Radiation Monitor j per CPS No. 9537.63 and channel checks performed per CPS No.
9911.24 on September 29, 1988, upon which the monitor was returned to service. !
- 2. LCO Event: 88-10-16 Information:
Operability Requirement: Table 3.3.7.11-1.3.b Date Entered: 10/19/88 at 0305 Date Restored: As of 12/31/88 at 2359 the instrument had not been restored to an operable condition.
Time Period: 73 days, 21.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (as of December 31, 1988)
Explanation: On October 19, 1988, during the performance of daily channel :
checks, in accordance with CPS No.
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9911.24, the Plant Service Water Effluent Line Monitor (0UIX-PR052 channel 3) failed its daily channel check because indicated flow was 91 l
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.'not within'25%Loffestimated flowTas specified in the acceptance criteria of~-CPS'No. 19911.24. I j1 Maintenance' Work Request'-(MWR),
L C57277'was' written.to troubleshoot
- and repair the cause of: failure.
On Octob'er 26', 1988, instrument calibration was.found acceptable in accordance with CPS'No.9432.45 with no repair-work performed. A' review-of equipment history indicated the-problem to be a design: problem..
Condition Report 88-10-102 was written:to resolve the problem. )
As a result-of Condition Report:88-10-102, MWR D05337 was written to vent the instrument transmitter and !
process lines and troubleshoot the .l flow transmitter loop as-necessary 1 to obtain flow indication. . On -
December 16,-1988,-during work under MWR D05337, it was discovered that because instrument lines from root valves: to the flow element-have negative slope, the root valves become the high point of the system process' making it'likely that air will collect at'this point and therefore give inaccurate readings.
1 Temporary Modification Permit 88- .{
.100 was. submitted on December 22, i 1988, to provide vent / test fittings-at the flow. transmitter to allow proper instrument line venting and q to recalibrates the flow transmitter j to a range of 0-50,000 tGPM instead -j of the current 0-75,000 GPM. j Measuring flow rates.within the lower range will provide increased-accuracy of indications at the j lower portion (0-25% scale) of !
measurement range. Results of the temporary modification will be evaluated for permanent 1 modification. This work is currently scheduled to occur on ,
February 25, 1989.
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"* 1 l 3. LCO Event: 88-11-63 i' Information:
l- Operability Requirement: Table.3.3.7-12-1,3.a i Date Entered: . 11/25/88 at 0900 Date Restored: 1/3/89 at 0118 Time Period: 38 days,.16.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Explanation: On November 25, 1988, it was noted by Operations personnel that, j during a routine 8-hour. cycle i calibration check,'the. hydrogen monitor (1N66N012B) on the Main Condenser Off-gas Treatment System Explosive Gas Monitoring System was spiking above the 2% .25%.value- l specified in the' monitor technical !
manual. MWR D01734 was initiated to troubleshoot and repair the
-cause of failure. j i
On. November 29, 1988, maintenance personnel performed CPS No.
9432.48, OFFGAS H2 ANALYZER 012A(B)
CALIBRATION, satisfactorily; ,
however, the monitor continued to {
operate erratically during 8-hour cycle calibration checks. On December 1, 1988, the monitor detector assembly was removed for troubleshooting and bench testing.
On December 16,.1988, the detector !
was reinstalled in the monitor and !
the monitor started up on December !
17, 1988. CPS No. 9432.48 was performed satisfactorily on December 18, 1988; however, erratic "
8-hour cycle calibration check indications continued. At this-point vendor ~ assistance was obtained to determine the cause of !
the erratic detector performance. l The vendor identified the major l cause for the hydrogen analyzer ;
sensor failure as being due to ;
liquid water on the sensor. To l correct this problem the vendor i recommended removing water ;
currently maintained within the i sample chamber of the monitor and operating the monitor in a dry -
condition using a design which ;
replaces the flame arrester function that the water provided. ,1 I
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On January'3,'1989, the. required I operating mode for operation of the j
' hydrogen monitors was exited and l the limiting condition of operation ,
'was cleared. Restraints were put on'the mode-restraint' list to have hydrogen monitors.operableLprior to ;
operation of the main condenser air E ejectors. Prior to this time the monitor sensors,will be dried and
'in-line. filters upstream of.the sensor'will be-cleaned.as per i
-vendor. recommendation, and the. l hydrogen monitor will be returned ]
to service. Modifications t recommended by the vendor to operate the monitor in a dry mode-and. replace the in-line filter with a'large, more' efficient filter are being evaluated by Nuclear Station-
-Engineering personnel.
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4 SECTION 9 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMI.
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MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS j In accordance with CPS Technical Specification 6.15 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 1 major changes to the Waste Treatment Systems were reviewed and approved during this reporting period.
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s SECTION 10 NEW LOCATIONS FOR DOSE CALCULATION AND/OR ENVIRONMENTAL MONITORING i
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6 NEW LOCATIONS FOR DOSE CALCULATION AND/OR ENVIRONMENTAL MONITORING In accordance with CPS Technical Specification 6.9.1.7 new locations for dose calculations and/or environmental monitoring identified by the Annual Land Use Census shall be reported in the Semiannual Radioactive Effluent Release Report. No new environmental monitoring locations were identified by the 1988 Annual Land Use Census completed on Septemb'er 1, 1988. However, several new locations were identified for the nearest garden and/or meat producing livestock in the 16 geographical sectors surrounding CPS.
In addition, residences were added in two sectors because they were at the same distance from CPS as existing residences. The following is a summary of changes identified.
- 1. Nearest Residence
- a. Added C. Groves residence with Whitehead 2.5 miles ENE since both residences are equal in distance from CPS.
- b. Added L. Disney with D. Newburg 3.0 S since both residences are equal in distance from CPS.
- 2. Garden Census
- a. Identified 63 gardens in the 16 sectors within a 5-mile radius of CPS. Specifically broad leaf vegetation was identified for this report. In most cases tomatoes, sweet corn and beans were grown in all sectors.
- b. Changes in census locations for the nearest garden were identified in 8 of the 16 sectors and are shown in the following table:
1987 Census Location 1988 Census Location 0.9 miles NNE (S. Kuntz) 2.0 miles NNE (J. Spencer)
( 2.5 miles ENE (Whitehead) 2.6 miles ENE (several residences) l 1.1 miles E (F. L. Reynolds) 1.5 miles E (Defebaugh)
I 2.9 miles SE (R. Twist) 4.6 miles SE (J. H. Weaver) 2.7 miles SSE (M. West) 2.6 miles SSE (Waterhouse) 3.6 miles SW (K. Lane) 0.8 miles SW (R. Reynolds) 1.4 miles W (J. Shaw) 2.3 miles W (Russell Kuntz) 1.0 miles WNW (P. Stapleton) 0.8 miles WNW (P. Stapleton) 98 L - - - - . - - - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _
- 3. Livestock / Dairy
- a. No goats were identified in 1988.
- b. Identified over 485 head of cattle, of which over 204 are cows whose milk is used for nursing calves ,
only: one farmer uses the milk for human l consumption and then only occasionally. The '
balance (over 281) of cattle are solely used for
) . meat production. There were 664 other farm animals identified; the predominant species of livestock were chickens, pigs, hogs and sheep,
- c. Changes in the census location for the nearest livestock were identified in 6 of the 16 sectors and are shown in the following table:
1987 Census Location 1988 Census Location 0.9 miles N (R. Wilson) 3.0 miles !! (H. Marx)
None in ENE sector 4.6 miles ENE (J. C. Swigart) 2.3 miles NE (J. Larry) None identified 2.7 miles SSE (C. L. Baker) 2.4 miles SSE (T. J.
Shinnemann)
None in NW sector 2.2 miles NW (W. Bastings) 0.9 miles NNW (R. Wilson) None identified 99 C
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4 ATTACHMENT A I
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ODCM Revision 4, Affected Pages 1
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SAFETY'EVALUATIdN FORM
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fDocument Evaluated: . ces OffiLe, hi (hMl.. m%J . L&S Log . p : 03o4.. '
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References:
m .as.nr us,. i ens w.w Loi uJ Ou. Cws, .
8 "
ff T 0 47 2f2
- ces acc.M vnai.M i 141. i f 2; */,1.l j '
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. CPS H A 1 TAAff 11. 3 -i
- TW.a bar Dlc V.ll.l= /j CF3.Q4CM -
$stfiens 2.h 2.1.1 3 2.3 1./, t.3 est3 7,.).l.fj oots As,, 3
~
,; i te ss.fs 2. 4 3 e a A ~1.1 - 5 t TdcM SP8C ( . t h. i. !
NOTE: Each block (including the lines provided for a written 4
' response following the YES/NO. questions) must.be 'i completed. ;
i Describe.the basic document or system and the changen being made. l Include the interface / impact on other systems.
.'t 'l +,, F L o nc M A
- M d .u . nf 3 . che V ud 4 ax, de0 caw A L tk Sdik. P A . M . G a,cL L A s .~ 1 0
1 m.3,1 tk e steJ ,s-Aas . A elq u, n -,-L . ones' m i s . y , t ...., , ;
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a BLOCK A - 10CFR50.59 APPLICABILITY' l
Answer the question corresponding . to .the... type _ouf.. change.. being . ...-.. ....
made (i.e., question "a" for modifications; question "b" for '
procedures; question "c" for tests; and g' uestion "d" for l experiments). Mark all other questions N/A". For any question (s) not marked "N/'A", provide an explanation for your answer.
YES NO V N/A a. Is this a change to the facility as described in the FSAR7 YES < NO N/A b. Is this a new procedure or a change to a procedure as described in the FSAR? -
YES NO t N/A c. Is this a test not described in the FSAR7 ' *
- YES NO / N/A d. Is this an experiment not described in the FSAR?
e Page 1 of i _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ -
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s l SAFETY EVALUATION F01(M (Con't)
BLOCK A - 10CFR50.59 APPLICABILITY (Con't)
Explain the reason for the YES/NO Answer:
m rs n a cL> w a h & o n e m ; # p r- < n2.ad-us cA rL_.
rso A,1 '
mm -, , :~ w 2 i oww '
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f, NOTE: If any of the questions in Block A is checked YES, then 10CFR50.59 applies to the change or activity, and it will be reported to the NRC in the annual report..
BLOCK B - RADWASTE TREATMENT SYSTEMS YES /NO The proposed activity involves a modification to the Radiological Waste Treatment Systems described in Chapter 11 of the FSAR.
Because: Tbmv OhCM cAqw 21o a mah o ~hath n To *
- i icA m T N .
Rh o ect CJh Jm StavA .
If the above statement was answered YES, complete CNP 1,09 Attachment 3, " Safety Evaluation for Changes to Radioactive Waste Treatment System" BLOCK C - TECH. SPEC. / LICENSE IMPACT 1 YES /NO The proposed activity -involves- a change to- any - "--
part of the Operating License, including the
.. Technieal. Speeificati.on .and_ Appendix _.3 _. ..-_.--.-...~
Because: 7'L. GAc M 1 cv h h2 nm,,LL A M, d ;, udtA & Ops h h c3 ' %ct occm cAenyo %
. . m &
oltuu4L M y OS NRts t -
NmW p b. SPFC. 6.N.1.
BLOCK D - UNREVIEWED SAFETY OUESTION Implementation or performance of the proposed -
activity will:
YES A 0 a. Increase the probability of occurrence of an accident previously evaluated in the FSAR.
! YES V NO b '. Increase the consequences of an accident
, previously evaluated in the FSAR.
Page 2 of [
p.J .
SAFETY EVALUATION FOP}I (Con' t) 1 BLOCK D - UNREVIEWED SAFETY O_UESTION (Con't)
YES / NO c. Create the possibility of an accident of a different type than any already evaluated in I the FSAR.
YES /NO
- d. Increase the probability of a malfunction of I equipment important to safety previously evaluated in the FSAR. s YES / NO e. > Increase the consequences of a malfunction of equipment important to safety previously evaluation in the FSAR.
YES / NO f. Create the possibility of a ma,1 function of l equipment important to safety different than previously evaluated in the FSAR.
YES_ A 0 g. Reduce the margin of safety as defined in the basis for any technical specification.
Provide the written bases for your answers to the YES/NO questions. Include discussions of the system / procedural -
functions and the effect of the change on these functions, operating characteristics, hazards analyses, radioactive releases ,.and~ interfacing. sya temsw .,-(#secadditionalepages 3. ifm . ..a--
necessary) -
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If any statement in this block was answered YES, the action described in the evaluated document involves an Unreviewed Safety Question.
Page 3 of i
.- I y
\ .
i SAFETY EVALUATION FORM (Con't)
BLOCK E - SUte4ARY ,
Check the applicable boxes:
( W The evaluated document does not involve a change to the Technical Specifications, Operating License, or an j Unreviewed Safety Question. Proceed with implementation.
[ ] The evaluated document involves a change to the Technical Specifications or the' Operating License. NRC approval is required before implementation.
[ ] The evaluated document involves Unreviewed Safety Question. NRC approval is required before implementation.
/k %/o ORIGINATOR Ou>tns Print Name 9 CuYd {& Signature /Date7/h/77 DEPT. HEAD %,,:) (A). Ni/le/~
Print Name Sigriature/Dateqg Y/W ,
2., f,, cy MANAGER NSED k.h t#&l44#L- ud4W -
f Print Name Signature /Date MANAGER L&S 5, 4. t,(I inLL-Print Name
/*
Oc+1 ,OG b
> Signature / gate
/t.6/t2P FRG S 0 &O265d822d -
t- /# '5'N Print Name Sig6 pre /Date i
NRAG NA e t o/c/8 9, Pri'nt Name Signature /Date l =m*
e h
l '
I
(_ . _ _ . Jema A rad W-- . - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
x q
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Safety Evaluation
? Prograrnatic Review Checklist l 14S Log 8: M-O -
Document revieved: @ M N _ CAA COU3;TtD4 Mudoo,L l NOTE: Questions should be answered based on the as received form, not af ter cocoent resolution.
Yes No N/A f
1 _ _ 1. Has the document or activity evaluated been properly identified?
1 _ _ 2. Does the description adequately tell vhat's being done or changed?
f 3.
4 _ _ Is block A properly filled out, is it consistent with NRC interpretations, and is there adequate justification?
g__4 Does block E give an adequate reason if checked NO, based on FSAR system definition or equivalent authority?
I _ _ 5. If No, does block C give an adequate justification why the Tech Specs, including environmental Tech Specs and Operating License do r.ot need to be changed?
_ _ 4\ 6. If YES, does block C provide a reference to either the Proposed Tech Spec Change Package number or the Proposed License Change number?
1 _ _ 7. Does t$1ock D give the reasons for the YES/NO items checked? Are they valid reasons that vould star.d up independently under audit? Is the full scope of the description covered?
1 _ _ 8. Have specific sections of the FSAR, Technical Specifications, and other docuraents used in answering the questions on the form been referenced? .
-C 9. Have the above FSAR & Technical Specification references been properly interpreted, and do the other references appear appropriate?
$ 10. Have applict.ble codes, standards, and regulations been considered?
_ _ 1 11. Are the supporting analyses (if required) attached?
T 12. Have the supporting analyses been properly documented and do they cover the approriate scope?
I _ _ 13. Have required reviews been performed?
g _ _ 14 Is the NSED Technical Review Checklist attached?
1 _ _ 15. The correct response is checked in Block E.
_ _ 1 16. Have all other areas, if required, been addressed? (list, if any)
ProblemsIdentified(ifany)d
~
l Corrective Action I hb -
- ) d k fIAS i ie/s/
Date e
,n wayny
. 1 I
YES NO l 10CFR50.59 Evaluation () TT Radwaste System' Safety () ()
Evaluation (IE-80) '
)
1 s k REVIEW OF SAFETY EVALUATION BY OTHERS LOG #:
TITLE:ce sitJe VV
/04.u h >Ma wal_
YES NO, N/A N' () [] 1. Document and Safety Evaluation read and understood.
M () () 2. Objective statements correctly reference to FSAR/ Tech Spec.
W' [] () 3. Objective statements appropriate to scope of change.
[] () M 4. Critical technical data validated to
. design base documents.
(4 [] [] 5. FSAR/ Tech Spec / Design Base data i consistent with document reviewed.
[] [] N 6. Comments, if any, resolved with originator.
COMMENTS:
Prepared by: M/- Date:/9 6 65W Supervisor: [ .
7 , /,1, Date: /o/1/ e 9 I- Director: T[ - , _ /m Date: /o/1/6 e r :
{
c NF-004.(7/86) _ ____ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ _ - _ -
-CPS-0DCM -
. List of Effective Pages Page' ' Revision Page Revision Pg Revision Page Revision-
-1 16 2 3-65 l' ' 4 1-3-17 3 '
- 11 -2 1 1 Liii= 1 3-18 1 3-67 1 5-1. 2 iv- 2 3 1 ~3-68 1 5-2 2 v -1 ~3 1 3-69 1 5-3 1.
vi 2 3-21 1 3-70 1 5 1 viiJ 4 3-22 1 3-71 1 5-5 'l 3-23 , 1 3-72 1 5-6 2 1-1 1 3-24 1 3-73 1- 5-7 l' 3-25 2 3-74 1 5-8 2 2-1 4 3-26 1 3-75 1 5-9' 3 2-2 4 3-27 2 3-76 1- 5-10 2
'2-3 .4 3-28 2 3-77 1 5-11 1 2-4 4. 3-29 2 3-78 1 5-12 2
.2-5 4 3-30 2 3-79 1 5-13 3-6- 2 3-31. 2 3-80 1 5-14 3 2-7. 3 3-32 1 3-81 1 5-15 2 2 2 3-33 1 3-82 1 2-9 2 3-34 1 3-83 1 6-1 2 2 1 3-35 1 3-84 1 2-11 2 3-36 1 3-85 1 7-1 2 2-12 2- 3-37 1 3-86 1 7-2 1 2-13 2 3-38 1 3-87 l 7-3 1 3-39 1 3-88 'l 7-4 1 2-14 1 3-40 1 3-89 1 7-5 1 2-15 1 41 1 3-90 1 7-6 2 2-16 1 3-42 1 3-91 1 7-7 2 2-17 1 3-43 1 3-92 1 7-8 2 2-18 2 3 '- 4 4 ' 1 3-93 1 7-9 2 2-19 2 3-45 1 3-94 1 7-10 2 2-20 2 3-46 1 3-95 1 7-11. .2 2-21 2 3-47 1 3-96 1 7-12 2 2-22 2 3-48 1 3-97 1 7-13 2 l 3-49 1 3-98 1 7-14 1 l 3-50 1 3-99 1 7-15 2 3-100 7-16 3-51 1 1 4 3 2 3-52 1 3-101 1 7-17 2 3-2 1 3-53 1 3-102 1 7-18 1 3-3 2 3-54 -1 3-103 1 7-19 1 3-4 2 3-55 1 3-104 1 7-20 1 3-5 2 3-56 1 3-105 1 7-21 2 3-6 2- 3-57 1 3-106 1 7-22 1 3-7 1 3-58 1 3-107 1 7-23 1 l- 3-8 1 3-59 1 3-108 2 7-24 1 3-9 2 3-60 1 3-109 - 1 7-25 1
~3-10 2 3-61 1 3-110 1 7-26 2 - '
3-11 2 3-62 1 3-111 1 7-27 1 3-12 4 3-63 1 3-112 1 7-28 1 3-13 2 3-64 1 3-113 1 7-29 1 3-14 2 3-114 1 7-30 1
'3 1 3-115 1 7-31 1
.CLINTON-I vii Rev.4-10/88
CPS-0DCM 2.0 LIQUID EFFLUENTS j 2.1 Introduction Liquid radwaste effluent released from CPS will meet 10CFR20 l concentration limits at the point of discharge to the unrestricted i l area shown in Figure 2.1-1. This design and operation objective I will be achieved at all times. Actual discharges of liquid
'radwaste effluent will occur on a batch basis and the average, concentration at the point of discharge will normally be only a small percentage of the allowed limits. Reference Clinton FSAR Section 11.5 for a description of radiation monitoring, sampling and effluent control systems.
Cumulative quarterly dose contributions due to radioactive effluents released to the unrestricted area will be determined once every 31 days using NUREG-0133 and Regulatory Guide 1.109 methodology and parameters.
2.2 Liquid Radwaste Discharge Process Radiation Monitoring (PRM) System This monitoring subsystem measures liquid radwaste effluent radioactivity prior to the effluent joining plant service water and i circulating water dilution streams. A high radioactivity signal from this gamma scintillation detector automatically terminates the liquid radwaste effluent release. The~ liquid radwaste effluent flow, variable from 10-60 GPM or 50-300 GPM, combines with Plant l Service Water flow (minimum flow approximately 5000 GPM during plant shutdown periods depending on system loads) and Plant Circulating Water flow (0-567,000 GPM) in the Seal Well prior to entering the 3.4 mile discharge flume to Lake Clinton (see Figure 2.5-1). ,
2.2.1 Method of Representative Sampling To obtain a representative sample of the liquid radwaste tank to be discharged, the tank is isolated from all inputs and recirculated a minimum of two tank volumes at which time a sample is obtained for isotopic analysis. .
2.3 10CFR20 Release Rate Limits The requirements pertaining to discharge of liquid radwaste effluent to the unrestricted area are specified in CPS RETS 3.11.1.1:
CLINTON-I 2-1 Rev.4-10/88
, CPS-0DCM "The concentration of radioactive material released in liquid effluents to UNRESTRICTED. AREAS shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for non-noble For dissolved or entrained noble gases, gas radionuclides.
the concentration.shall be limited to 2E-04u Ci/ml total activity."
To comply with the above requirements, setpoints will bc calculated to assure that Seal Well concentrations do not exceed 10CFR20, Appendix B, Table II, Column 2 values at any time.
2.3.1 Liould Radwaste Discharge PRM Setpoints i
To achieve CPS RETS 3.11.1.1, and for.the purpose of j implementation of CPS RETS 3.3.7.11, the alarm / trip setpoints i for liquid effluent monitors and flow measurement devices are i set to assure that the following equation is satisfied: i cf <CMPC (1) >
F+f-C = the effluent concentration limit MPC (CPS RETS 3.11.1.1) implementing 10.CFR20 for the site, corresponding to the specific mix of radionuclides in the effluent stream being considered, in uCi/ml i c =
the setpoint, inp Ci/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint is
, inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream (s) plus the effluent stream.
F = the dilution water flow setpoint as determined at the Seal Well, in volume per unit time
~
f = The liquid radwaste discharge flow setpoint as determined at the liquid radwaste discharge PRM location, in volume per unit time (same units as F) 1
- l CLINTON-I 2-2 Rev.4-10/88 i
~_m___________________ _ _ _ _ _ .
CPS-0DCM' N'
The available dilution water flow (F) should be constant for a given release, an!. the liquid radwaste tank discharge flow (f): and
, . monitor setpoint (c) are set to meet the condition of equation (1)
E for a given effluent concentration ( 6 The method by which thisisaccomplishedisillustratediWhe)c. tions 2.3.1.1.through 2.3.1.5.
2.3.1.1 .The isotopic concentration for a liquid radwaste tank to be discharged'is obtained from the sum of the measured ;
concentrations as determined by the analyses required ih CPS RETS Table 4.11-1:
{Ct
=
gC+[C,+{C+C+CFe, g s T p Ci/ml (2) where gCg
= The sum.of concentrations C g of each measured _ gamma emitter g (including I-131) '
observed by gamma spectroscopy of'the waste sample, pCi/ml.
E =
C of alpha emitters (a) 8 8 The sum of in liquid concentrations radwaste as measu C@ed in the most current .
QUARTERLY composite discharge tank sample, pCi/ml. j IC ss
= The sum of concentrations.C of Sr-89/Sr-90.in-liquid radwaste as observedsin the most current QUARTERLY composite discharge tank sample, pCi/m1'.
C T
= The measured concentration of H-3 in liquid radwaste as determined from analysis of the most current
' QUARTERLY composite discharge tank sample, uCi/ml. ,
C* p = The measured concentration of Fe-55 in liquid radwaste as observed in the most current QUARTERLY composite discharge tank sample, 'u Ci/ml.
CLINTON-1 2-3 Rev.4-10/88
" i CPS-0DCM e
2.3.1.2 The' measured radionuclides concentrations are used to calculate a DILUTION FACTOR (DF) which is equivalent to the ratio of total dilution flow rate to liquid radwaste tank J effluent flow rate required to assure that the limiting concentrations of 10CFR20, Appendix B, Table II, Column 2 are met at the point of discharge to the unrestricted area.
DF = SF [gC i ), dimensionless (3) f ppyi .
C C C C C
= SF g t_jt_ ,ta a 4r s , T , Fe s )
8MPC MPC, MPC MPC T MPC g s Fe where l
Cg = The measured concentrations C , C 3, C, C' g s T C
Fe as defined in equation (2), pCi/ml.
MPC g = The limiting concentration of the corresponding radionuclides MPC , MFC,, MPC ,g MPCT, MPCFe f#
- 10CFR20, Appendix B, Table II, Column 2, p Ci/ml.
For dissolved or entrained noble gases, the
. concentration shall be limited to 2E-04pCi/ml total activity.
SF = The conservative SAFETY FACTOR normally applied to compensate for statistical fluctuations and measurement errors, dimensionless. ;
2.3.1.3 The maximum permissible liquid radwaste tank effluent flow rate, F tank, is calculated by the following equation:
Ftank = 0.9 (Fdil + ftank), v lume/ time (4)
DF where ,
F = Miminum expected dilution water flow rate dil ,
(Circulating and/or Service Water systems),
volume / time ftank = Maximum expected liquid radwaste tank effluent flow rate, volume / time 0.9 = Flow rate correction factor to provide a 10% margin for variations in flow rates, dimensionless
~
DF = The DILUTION FACTOR calculated by equation (3), i dimensionless _
. 9 CLINTON-I 2-4 Rev.4-10/88
. 1
- a
i- Equation (4) is valid only for DF> 1; for DF< 1, the liquid l radwaste tank effluent concentration meets the limits of l 10CFR20 without dilution and therefore F tank may assume any
]
value not to exceed discharge pump capacity. l 3
2.3.1.4 The liquid radwaste discharge PRM setpoint may now be ]
specified based on the values ofE Ct 1 (Eq.2) and Ftank ( 9' ) !
which were determined to provide compliance with the concentration limits of 10CFR20, Appendix B, Table II, Column
- 2. The monitor response is primarily a gamma response and the i actual setpoint is therefore based on ECg g (Eq.2). The i
monitor setpoint, in counts per minute (cpm), which corresponds to the particular setpoint concentration, C , is M
determined based on monitor calibration data or operational data which correlates monitor response to sample analyses associated with the actual liquid radwaste discharged. The second method is considered valid only if the integrity of laboratory methods of determination are proven more accurate than the monitor data.
The set point concentration, CM, is obtained by the following equation:
C M =( tank) IC , uCi/ml gg (5) act where .
f act
= The actual liquid radwaste effluent flow rate, volume / time If (F tank Nact)> 1, the value obtained for CM is used to determine the monitor setpoint above background, ccpm, from either of the two methods described above. In the case where (F <1 digaRitr/fg8cEa)rame,tervaluesno (DF,release F may be made using the existing i f,ce).
e ,,y, The setpoint concentration is conservative, even if F s tank attainable , since the calculated flow rate contains the SAFETY FACTOR, dilution flow rate and liquid radwaste tank effluent flow rate margins.
2.3.1.5 To prevent spurious alarms, revise the Plant Service Water Effluent PRM setpoint to coincide with the setpoint concentration, Cu, calculated by equation (5). This setpoint is valid only dufing periods of actual liquid radwaste discharges. -
CLINTON-I 2-5 Rev.4-10/88
u el TABLE 3.4-3 ANNUAL DOSES'IN UNRESTRICTED AREAS
,1 Total Body Skin ~ Organ:
' Distance 0ccupancy Dose Rate ' Dose Rate. Dose Race *i Location- (mile / meter) Sector (hrs /yr). (mrem /yr) (mrem /yr) (mrem /yr)
Road 0.3/495' 'SE - 243(1) 0.04 0.08 - 0.,0 2 -
Agricultural Acreage (2) ' 0.9/1372- SSW 964(3) 0.02. 0.05 0.01 Clinton Lake- 0.2/335 NW 2208(4) 1.0 2.1 0.51 Department of Conservation >l Recreation Area 0.8/1287 .ESE 2208(5) 0.1 0.2 0.05 ]
Residence 0.8/1219 . SW 8760 0.5 1.0 0.24
, , 'Rssidence 1.5/2414 WSW 8760 0.2 0.4 0.10 Rasidence 1.7/2736 SSE 8760 0.1 0.2 0.05' (1)' Assumes travel on road for forty minutes per day.
-(2) Maximum farm acreage (276) within site boundary.
(3) ' Assumes 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in field per acre farmed.
'(4)' Assumes continuous occupation on Clinte Lake for the months of j June, July, and August.
(5) Assumes-continuous occupation on Department of Conservation camping areas for the months of June, July, and August.
- Child inhalation -
CLINTON-I 3-12 Rev.4-10/88 1
r- ; CPS-0DCM l
u-TABLE 7.2-5 SITE BOUNDARY DISPERSION AND DEPOSITION PARAMETERS Sector Distance Release Point XTQ Release Point D/Q (mile / meter) (sec/m3) (m 2)
HVAC Stack SGTS Stack HVAC Stack SGTS Stack N 0.9/1402 9.537E-7 9.537E-7 6.224E-9 6.224E-9 NNE 0.8/1341 7.543E-7 7.543E-7 5.548E-9 5.548E-9 NE 0.7/1097 8.750E-7 8.750E-7 6.616E-9 6.616E-9 ENE 0.8/1219 >
4.679E-7 4.679E-7 3.443E-9 3.443E-9 E 0.8/1219 5.127E-7 5.127E-7 4.040E-9 4.040E-9 ;
ESE 3.0/4816 6.970E-8 6.970E-8 4.695E-10 4.695E-10 SE 2.4/3841 8.696E-8 8.696E-8 5.589E-10 5.589E-10 SSE 2.1/3353 8.252E-8 8.252E-8 5.398E-10 5.398E-10 S 2.1/3353 8.565E-8 8.565E-8 3.911E-10 3.911E-10 SSW 2.9/4633 4.976E-8 4.976E-8 2.318E-10 2.318E-10 SW 3.2/5121 7.591E-8 7.591E-8 2.722E-10 2.722E-10 USW 2.1/3414 1.307E-7 1.307E-7 4.053E-10 4.053E-10 W l.4/2256 2.045E-7 2.045E-7 7.755E-10 7.755E-10 WNW 0.7/1097 4.414E-7 4.414E-7 2.356E-9 2.356E-9 NW 0.9/1463 3.871E-7 3.871E-7 1.578E-9 1.578E-9 NNW 1.0/1585 5.089E-7 5.089E-7 2.640E-9 2.640E-9
. Controlling CPS RETS Pathway Sector Comments 3.11.2.1 Immersion N Considers occupancy factors for other sectors 3.11.2.1 Inhalacion N Considers occupancy factors for other sectors 3.11.2.2 Air Dose N Considers occupancy factors for other sectors 3.11.2.3 Inhalation N Considers occupancy factors for other sectors 3.11.2.3 Ground Plane N Considers occupancy factors for other sectors 3.11.2.3 Cow Milk NE Nearest milk cow is at 3.2 miles in NE sector (2) 3.11.2.3 Goat Milk N No milking goats within 5 mile radius of CPS (3) 3.11.2.3 Cow Meat N 3.11.2.3 Vegetation N Notss (1) Controlling locations and sectors are based on 1987 Land Use Census.
(2) Nearest milk cow is at 3.2 miles in NE sector. Milk sample is not available, alternate vegetation samples are collected in N and NE sectors. At distance 3.2 miles, D/Q in N sector is 1.295 x D/Q in NE sector.
(3) Assumes a milking animal resides at a distance of 4.5 miles from CPS in the worst case sector as stated on page 30 of NUREG-0133.
CLINTON-I 7-16 Rev.4-10/88
a n 1 l
ATTACHMENT B Solidification Vendor. Procedure / Document Approv.Il Cover. Sheet i
\
e ee
-- --m--_-_____. _ _ _ _ _ , , , _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
y ~ CPS No. 1005.01F006 i
! ! Gev.-5)
? .:
l-p CPS No. 1888.00 I l
b Rev. No. 3 .
l Class Code SNQN I l'
A TION-P.ROCEDURE APPROVAL FORM P .., m ... 4 5;;,
1
- v. - -
9 3 2
- FILE COPY. 3 i TITLE: k EESS40NTROL"" PROGRAM .i PROCEDURE TRAINING REQUIRED: X YES NO !
_fMW hays for Key Personnel
- 2 SAFETY EVALUATION APPLICABILITY Does this procedure:
YES NO
- 1. Cause a change to.the facility as described in the FSAR? X
- 2. Conflict with any FSAR requirement? X
- 3. Cause an abnormal mode of operation for the system or components involved? . X
- 4. Affent. nuclear. safety in: a way not previously evaluated? X
- 5. Require a change.,to Technical Specifications or the operating license? X ORIGINATOR.................. FA !-
GROUP SUPERVISOR............
DEPARTMENT HEAD,............ p%C_
INDEPENDENT REVIEWER........
v hd) .
NSED........................ //A COMPLIANCE.................. [//,/T7L /R/
QUALITY ASSURANCE........... bh [M FACILITY REVIEW GROUP....... [ v t
p' MANAGER - CLINTON POWER STATION............... / O)\
/ n) i DEC 21198B l} VJ " )
Page 1 of 1 x_--_ua.---_--__.____ _ _ _ . . _ . - _ _ _ - . - _ _ _ . _ _ - - - _
-~ ~ ' ~ ' ~'
_ _ _ _ ,? CLASS / CODE:_ ~ . -SNQD1 I., 4i h .
. SOLIDIFICATION VENDOR ' PROCEDURE / DOCUMENT APPROVAL COVER SHEET I
y TITLE: .
P FCCESS CONTROL PFO;?#1 FOR CLINION IMR STATION
.REV. 6
' SAFETY EVALUATION' APPLICABILITY Does this procedure:
YES NO
- 1. : Cause'-a change to the fteility as described in the FSAR? -
. 2. Co'nflict vie. :ny FSAR requirement ? b
- 3. ' Cause ~ an~ abnormal mode of operation .for the sys tem or components involved? -
4... Affect nuclear safet'y in a way not previcusly evaluated?- -
i 5., Require a changeLto Technical Specifications er the operating license? _
2 MAINTENANCE DEPAR'nfENT . . . . . . . . . . Is/A /
Signature Date CHEMISTRY GR'0UP.................. $b Signature 1A / 9-/366 Date TECHNICAL DEPARTMENT ............ 14A /
Signature Date NUCLEAR STATION '
Y ~'
ENGINEERING DEPARTMENT. . . . . . . . . . . #e8m 44 ve/ / 9-u -@
Signature Date-RADIATION PROTECTION DEPARTMENT . v/A /
Signature Date QUALITY ASSURANCE DEPARIMENT .... _A /ht b Signature
/ 9-/8-((
Date RADWASTE GR0UP................... / I' '
- 5igera; cure f Date FACILITY REVIEW GROUP............,',
7 Md Signature
/ 9rMF Date RCCL #53.120 Page 1 of 1
.