U-601018, Semiannual Radioactive Effluent Release Rept,870228-0630
| ML20237K101 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/30/1987 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| U-601018, NUDOCS 8709040192 | |
| Download: ML20237K101 (117) | |
Text
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CLINTON POWER STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FEBRUARY 27,1987 - JUNE 30,1987 7v I
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TABLE OF CONTENTS Page
1.0 INTRODUCTION
............................................ 1 2.0 GASEOUS EFFLUENTS....................................... 2 2.1 Regulatory Limits for Gaseous Effluents........... 2 2.2 Maximum Permissible Concentrations................ 3 l 2.3 Measurements and Approximations of Total.......... 3 Radioactivity 2.4 Gaseous Releases.................................. 5 2.5 Abnormal Releases................................. 6 2.6 Estination of Errors.............................. 6 3.0 LIQUID EFFLUENTS........................................ 6 3.1 Regulatory Limits for Liquid Effluents............ 6 3.2 Maximum Permissible Concentrations................ 7 3.3 Measurements and Approximations of Total Radioactivity..................................... 7 3.4 Batch Liquid Releases............................. 8 3.5 Abnormal Releases................................. 9 3.6 Estimation of Errors.............................. 9 4.0 SOLID WASTE............................................. 9 4.1 Regulatory Specifications 4.2 Solid Waste and Irradiated Fuel Shipments 5.0 SITE METEOROLOGY........................................ 10 6.0 RADIOLOGICAL IMPACT ON MAN............................. 10 6.1 Water Related Exposure Pathways 6.2 Gas Related Exposure Pathways
7.0 TECHNICAL SPECIFICATION REP 0RTS........................ 11 7.1 Limiting Condition for Operation Reports......... 11 7.2 Off-Site Dose Calculation Manual Changes......... 13 7.3 Solid Waste Process Control Program Changes...... 16
! 7.4 Major Changes to Radioactive Waste Treatment Systems.......................................... 17 7.5 Land Use Census.................................. 17 8.0 TABLES Table 1A Gaseous Effluents-Summation of All Releases Table IB Gaseous Effluents-Elevated Release Table 1C Gaseous Effluents-Mixed Releases Table 2A Liquid Effluents-Summation of All Releases Table 2B Liquid Effluents Table 3 Solid Waste and Irradiated Fuel Shipments Table 4A Joint Frequency Distribution of Meteorological Parameters Table 4B Classification of Atmospheric Stability Table 5 Radioactive Gaseous Waste Sampling and Analysis Program Table 6 Radioactive Liquid Waste Sampling and Analysis Program ATTACHMENT A - ODCM REVISION 2, AFFECTED PAGES ATTACHMENT B - SOLIDIFICATION VENDOR PROCEDURE / DOCUMENT APPROVAL
1.0 INTRODUCTION
This first Semiannual Radioactive Effluent Release Report is submitted in accordance with Section 6.9.1.7 of Appendix "A" (Technical Specifications) to License No. NPF-62. It covers the ,
period from initial criticality, February 27, through June 30, 1987. This report was prepared in accordance with Regulatory Guide 1.21, as applicable to the Clinton Power Station (CPS) Technical Specifications. Portions of the Technical Specifications applicable to this report, Sections 3/4.3.7.11, 3/4.3.7.12, 3/4.11, 3/4.12, 6.9.1.7, 6.13.2, 6.14.2, and 6.15.1, are herein referred to ;
collectively as the Radiological Effluent Technical Specifications l (RETS). j i
All liquid and gaseous radioactive releases to the environment l during this reporting period were sampled and analyzed / monitored in l accordance with the requirements of the CPS Technical Specifications. All effluent releases were within the {
concentration and release limits specified in the RETS.
Gaseous effluents due to their low concentrations, were not detected on the release point radiation monitoring equipment. For this reason estimates of gaseous releases were derived from alternate sources of sampling. Releases were a small fraction of any Technical Specification Limits.
Liquid releases during the first quarter of 1987 contained no measurable radioactivity. In the second quarter, activity released was a small fraction of Technical Specifications Limits.
There were no solid waste or fuel shipments from CPS during this reporting period.
Site meteorological data are not reported for the first six months j of 1987. Technical Specifications allow this material to be
{
submitted at the end of the annual reporting period. Site {
meteorology is discussed in Section 5.0.
Radiological impact on man assessment was performed for the liquid and gaseous releases according to the Offsite Dose Calculation Manual (ODCM). The results of this assessment reveal that all doses were a small fraction of Technical Specification Limits.
Section 7.0 comprises several reports of a special nature that are required by Technical Specifications. During this reporting period there were two incidences of equipment inoperability which prevented meeting a Technical Specification Limiting Condition for Operation, however, during these periods the Technical Specification Action Statement was met by analyzing grab samples.
Additionally, there have been revisions of both the ODCM and the Process Control Program (PCP) which are required to be reported.
In the case of the ODCM, changes reported were instituted between the time of ODCM acceptance by the USNRC ard the date of initial criticality.. j Page 1 of 17
I l
l Significant activity is defined as radioactivity greater than an i MDA value.
Minimum Detectable Activity (MDA) as referenced in this report is defined as the Lower Limit of Detection (LLD) calculated value according to the Technical Specification formula of Table ;
4.11.1-1 for the particular counting instrument at the time of J' actual counting. A shorthand method of specifying this is by stating that MDA is the "LLD at the time of counting."
Calculations and other terms utilized in this report are those outlined in the CPS Offsite Dose Calculation Manual Rev. 2 (ODCM).
2.0 GASEOUS EFFLUENTS j i
2.1 Regulatory Limits for Gaseous Effluents Technical Specification 3/4.11.2 describes the requirements for release of radioactive gaseous effluents to areas at or beyond the site boundary. Concentrations of radioactive materials in gaseous effluents are limited by quarter / annual dose and annual dose rate values. These values limit the concentrations of radioactive materials in unrestricted areas to less than those specified in 10CFR20, Appendix B, Table II, Column 1. Additionally they limit the amount released to that which could deliver the dose objectives {
The as specified in 10CFR50, Appendix I, Sections III.A and IV.A.
following is a list of the Technical Specification limits for radioactive gaseous effluents.
2.1.1 10CFR20 Limits - Gaseous Effluents Fission and Activation Gases - The relecse rate limit of any time for noble gases to areas at or beyond the site boundary shall be such that:
D = Average total body dose rate in the current year I b
(mrem / Year)
D tb d 500 mrem / Year to the total body D = Average skin dose rate in the current year s
(mrem / Year) I i
Dg 1 3000 mrem / Year to the skin l Radiciodines and Particulate - The release rate limit for the sampling period for all radiciodines, tritium and radioactive materials in particulate form with half lives greater than 8 days shall be such that:
D g = average organ dose rate in the current year (mrem / Year)
Page 2 of 17
Dg s1500 mrem / Year to any e+gan 2.1.2 10CFR50, Appendix I Limits Fission and Activation Gases - The dose in air from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that:
D g
= air dose due to gamma emissions from noble gases 5
D 8
5 mrad / Quarter ,
and 1 5 10 mrad / Year D = air dose due to beta emissions from noble gas 3
D b 5 10 mrad / Quarter ,
and !
5 20 mrad / Year j Radiciodines and Particulate - The dose from tritium, radiciodines and radiositive material in particulate form 3
]
with half-lives greater than 8 days in gaseous effluents j shall be such that: 1 D
p = dose to an individual from radiciodines and ,
radionuclides in particulate form with half-lives greater than 8 days (mrem)
D s7.5 mrem / Quarter to any organ P and s15 mrem / Year to any organ 2.2 Maximum Permissible Concentrations The Maximum Permissible Concentrations (MPC) for gaseous effluents are specified in 10CFR20, Appendix B, Table II, Column 1. Clinton Technical Specifications establish requirements to limit the rel se rate of effluents such that discharges will not result in the <xposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA either within or outside the SITE BOUNDARY to average annual concentrations exceeding MFC values.
l The MPCs of 10CFR20 are not utilized directly for limiting gaseous l effluents. (See Section 2.1.1, 10CFR20 Limits - Gaseous !
Effluents). !
2.3 Measurements and Approximations of Total Radioactivity Gaseous rele> Ulinton Power Station is confined to two paths:
the Heating, ventilation and Air Condition Stack (HVAC Stack) and the Standby Gas Treatment System Stack (SGTS Stack). Both HVAC and SGTS stacks are continuously monitored for gaseous activity Page 3 of 17 u--__------_--------------_----_--.-------__----__ _ _ _ . - _ - _ _ _ . - - - - _ _ - - - - - _ _ _
I concentration and each has an integrating type sample collection ,
device which concentrates particulate and iodine. These release 1 points also have flow measurement devices which continuously record the flow rate of gas released. In addition to the gaseous, particulate and iodine release measurements.. tritium, gross alpha, and gaseous isotopic measurements of each effluent stream are l conducted according to Technical Specification requirements (See ]
Table 5). After each semi-annual period a summary of the gaseous )
release for each quarterly period is compiled as follows: ]
1 2.3.1 Fission and Activation Gas The total amount of activity, in curies, is determined ]
for'each individual release and then summed for all I releases in the quarter. All gaseous releases are 4 continuous. Analysis of specific radionuclides in effluent samples taken at the release points is utilized with the corresponding system flow rates and monitor data )
to determine radionuclides composition and concentration 1 of effluents. These results along with the volume of :
radioactive discharges are used to determine the l cumulative amounts of material released, f
i During this reporting period all grab samples taken at I the effluent monitors were less than the LLD at the time j of counting. To estimate and assign a total amount l released.in the absence of detectable amounts of I radioactive material at the effluent monitor, main i condenser offgas treatment system sampling and flow !
monitoring results were used to estimate fission and I activation gases. This resulted in an estimate of l 5.77E-3 Ci of Kr-85m and 1.02 Ci of Ar-41 released during this period.
2.3.2 Radiciodine Releases Iodine releases are determined at least weekly for I-131 i and I-133 for each discharge ntack. Where significant i activity is not measured, MDAs are calculated. When calculated MDAs are below Technical Specification required LLDs, 0 (zero) release is reported.
Releases are summarized with the aid of the SR (effluent management) computer system and a quarterly total is prepared from the release permit summaries. The percent of the Technical Specification limit tabulated for I-131 and I-133 refers to the quarterly dose limit.
2.3.3 Particulate Releases Particulate releases are determined at least weekly for each discharge stack. Where significant activity is not measured, MDAs are calculated. When calculated MDAs are below Technical Specification required LLDs, Page 4 of 17
l 0 (zero) release is reported. Releases are summarized with the aid of the SR computer.
After each calendar quarter the particulate filters-from each discharge stack are combined and assayed for Strontium isotopes (Sr-89, Sr-90) by chemical separation techniques. Since sample flows and discharge stack flows are essentially constant over each monthly period, the filters from each discharge stack are dissolved together.
Decay corrections are made back to the middle of the quarterly collection period. Again the SR computer is used to aid in the calculation of the Strontium release.
Where significant Strontium activity is not detected, MDAs are calculated. When calculated MDAs are below Technical Specification LLDs, O(Zero) release is reported.
2.3.4 Gross Alpha Release The gross alpha activity released is analyzed each' month-by counting the particulate' filters'for gross alpha activity in a proportional counter. These results are recorded on a data sheet and the activity is used to determine total activity released each month, i
2.3.5 Tritium Release Tritium samples are obtained at least monthly from each discharge stack by passing a known volume of the sample-stream through a gas washer containing a known quantity of demineralized water. The tritium samples are distilled and analyzed by liquid scintillation. From the-measured tritium concentration, the volume of sample, the tritium collection efficiency, and the exhaust flow rates, the monthly tritium release is calculated for each-discharge stack. The quarterly release summary is generated from the monthly release calculations.
2.4 Gaseous Releases 2.4.1 Batch Releases (None during this period) 2.4.2 Continuous Releases Summaries of the radionuclides total curie activities and average release rates are included in Table.lA.
There was no detectable activity in the gaseous effluent
, samples taken at the effluent monitors for the period I
covered by this report. If a radionuclides was not-detected, zero activity was used for that isotoae in dose-calculations. A zero activity indicates that the radionuclides was not present at a level greater than the Lower Limit of Detection (LLD) of the instrumentation Page 5 of-17
r i
I used. In all cases, these LLDs were less than~the level required by the- !
Technical Specifications. The following are typical LLDs: I 1
Radionuclides LLD (uCi/ml) 1 Kr-87 2.7 E-8 l Kr-88 1.8 E-8 Xe-133 2.7 E-8 Xe-133m 9.5 E-6 F.e-135 9.2 E-8 Mn-54 2.3 E-13 Fe-59 5.4 E-13 i Co-58 2.7 E-13 )
Co-60 1.8 E-13 !
I Zn-65 7.0 E-14 1 Mo-99 7.5 E-13 Cs-134 8.5 E-14 i Cs-137 1.8 E-14 '
Ce-141 2.4 E-13 Ce-144 7.8 E-13 3
I-131 1.3 E-13 I-133 3.5 E-13 i Sr-89 1.0 E-13 )
Sr-90 1.0 E-13 1 H-3 3.7 E-7 Gross Alpha 1.5 E-14 2.5 Abnormal Releases (None during this period) 2.6 Estimation of Errors The estimate of overall error for gaseous effluents includes applicable random and systematic components of individual errors due to measurement of ventilation flow rates, measurement of sample, flow rates, non-steady state conditions, and errors involved in sample preparation and counting. The overall error for gaseous effluents is estimated to be 75%.
3.0 LIQUID EFFLUENTS 3.1 Regulatory Limits for Liquid Effluents Technical Specifications 3.11.1.1. and 3.15 . 2 establish concentration and dose limits to a member ' he public from radioactive material released in liquid e F rts to the UNRESTRICTED AREA.
Page 6 of 17
3.1.1 10CFR20 Limits - Liquid Effluents CPS RETS 3.11.1.1 requires that the' concentration of l radioactive material released in liquid effluents to l UNRESTRICTED AREAS shall be. limited to the concentrations specified in 10CFR20, 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 2E-4 microcuries/ml total' activity.-
3.1.2 10CFR50, Appendix I Limits CPS RETS 3.11.1.2 requires that the cumulative dose contributions to an individual from radioactive material in liquid effluents released to the UNRESTRICTED AREA be determined at least once per 31 days. The applicable dose limits are:
s 1.5 mrem / Quarter - to the total body 55.0 mrem / Quarter - to'any organ !
and 5 3.0' mrem / year - to the total body 510.0 mrem / year - to any organ 3.2 Maximum Permissible Concentrations l The Maximum Permissible Concentrations (MPC) of radioactive '
material in liquid effluents are limited by those values as specified by 10CFR20, Appendix B, Table II, Column 2. The MPC chosen is the most conservative value of (whether soluble or !
insoluble) MFC for each isotope. l 3.3 Measurements and Approximations of Total Radioactivity Representative pre-release grab samplesLare obtained and analyzed according to the Technical Specification requirements as shown in Table 6. Isotopic analyses are performed using gamma-ray spectroscopy. The results then are utilized with the actual discharge and dilution flows to calculate the total amount of 1 material released and the corresponding potential dose to man.
Aliquots of each pre-released sample, proportional to the waste :
volume released, are composited in accordance with Table 6.
Strontium determinations'are then made by performing a chemical ,
separation and counting the separated strontium using a gas flow '
proportional counter. Tritium and Iron-55 concentrations are determined by using liquid scintillation techniques. The concentrations of dissolved and entrained gases are determined by gamma-ray spectroscopy.
Page 7 of 17
- u. _ - . - - ___. _ _ - _ ____- _- - - _ _ _ _ _ _ _ - _ - - _ _ _ - _ - _ _ - _
The concentrations of composited isotopes and the volumes of the releases associated with these composites establish the proportional relationships that are then utilized for calculating the total activity released for these isotopes.
3.4 Batch Liquid Releases 3.4.1 Liquid Effluents For the first quarter of 1987 there were nine (9) batch and no continuous releases. Total waste volume for the 4 first quarter was 7.75E5 liters; total plant dilution volume during periods of release was 7,58E7 liters.
I For the second quarter of 1987 there were 37 batch and no continuous releases. Batch release total waste volume for the second quarter was 3.34E6 liters; total plant dilution volume during periods of release was 3.16E8 liters.
Summaries of the radionuclides total curie activities, average diluted concentrations, and concentrations as percentage of MPC are included in Table 2A and 2B, Tables are in the Regulatory Guide 1.21 format.
There was no detectable activity in the majority of the liquid effluent releases for the period covered by this report. If a radionuclides was not detected, zero activity was used for that isotope in dose calculations.
A zero activity indicates that the radionuclides was not present at a level greater than the Lower Limit of Detection (LLD) of the instrumentation used. In all cases, these LLDs were less than the level required by the Technical Specifications. The following are typical LLDs:
Radionuclides LLD (uCi/ml)
Mn-54 1.8E-8 Fe-59 2.9E-8 Co-58 1.6E-8 Co-60 3.3E-8 Zn-65 2.3E-8 Mo-99 1.1E-7 j I-131 3.5E-8 Cs-134 1.0E-8 Cs-137 1.8E-8 ,
Ce-141 2.1E-8 l Ce-144 7.9E-7 Sr-89 5.0E-9 Sr-90 5.0E-9 i Fe-55 1.0E-7 l' H-3 6.4E-8 Gross Alpha 9.9E-8 1
Page 8 of 17
3.4.2 Batch Releases LIQUID RELEASES February 27 - March 31, 1987 Bgtch Continuous Number of Releases 9 0 Total Time of Releases (min) 8.35E2 0 Maximum Time for a Release (min) 1.31E2 0 Average Time for a Release (min) 9.28E1 0 Minimum Time for a Release (min) 7.80El 0 Average Effluent Stream Flow During Periods of Release 9.28E2 0 (1/ min)
April 1 - June 30, 1987 Batch Continuous Number of Releases 37 Total Time of Releases (min) 3.35E3 0 Maximum Time for a Release (min) 1.25E2 0 Average Time for a Release (min) 9.05El 0 Minimum Time for a Release (min) 6.80E1 0 Average Effluent Stream Flow During Periods of Release 9.97E2 0 (1/ min) 3.5 Abnormal Releases (None during this period) 3.6 Estimation of Errors The estimate of overall error for liquid effluents includes individual errors due to measurement of flow rates, tank volumes, non-homogeneous samples and errors involved in sample preparation and counting. The overall error for liquid effluents is estimated to be 75%.
4.0 SOLID WASTE 4.1 Regulatory Specifications Regulatory Specifications for solid waste are governed by the CPS Technical Specifications, the Process Control Program (PCP), by Page 9 of 17
the NRC regulations of Title 10, Part 20 and 61, and the DOT regulations of Title 49 Part 71 and 178 of the Code of Federal
~ Regulations. These specifications require that the waste being shipped from the site for burial be classified, monitored, accounted for, and packaged for proper disposal.
4.2 Solid Waste and Irradiated Fuel Shipments During th4- reporting period there were no radioactive vaste or irradiated fuel shipments from CPS. This is reported in Table 3.
l 5.0 SITE METEOROLOGY l
Cumulative joint frequency distributions of wind speed, wind direction and atmospheric stability for the quarterly periods
, January 1, 1987, through June 30, 1987, are normally presented in l Table 4A. CPS Technical Specifications 6.9.1.7 allow this l information to be kept on file and provided to the USNRC upon request. The first six months of meteorological information will be included as an annual summary within the semiannual report to be submitted after January 1, 1988. The classification of atmospheric stability utilized in Table 4A is presented in Table 4B.
As per the CPS ODCM, the site specific annua 17 average dispersion factors (X/Q) are calculated as Mixed Release . In utilizing the .
Regulatory Guide 1.21 format for gaseous releases, all gaseous releases are considered as mixed mode. Mixed mode represents a combination of the ground level and elevated level criteria as described in Section 7.2 of the ODCM.
6.0 RADIOLOGICAL IMPACT ON MAN Dose calculations in the reporting neriod resulted in potential dose to individuals at levels well below 10CFR20 and 10CFR50 limits. The dose estimates reported in this section utilize the information in Tables 2.4, 3.4 and 3.5 of the ODCM. The methodology corresponds to that of the ODCM and utilizes the limiting pathwcys as def ined by Table 7.2-5 of the ODCM.
6.1 Water Related Exposure Pathways Total Dose Equivalent (mrem) 1st Quarter 1987 2nd Quarter 1987 Total Body 0.00E0 4.54E-06 Bone 0.00E0 1.77E-06 Liver 0.00E0 1.41E-05 Thyroid 0.00E0 2.76E-08 Kidney 0.00E0 2.82E-06 Lung 0.00E0 1.22E-06 GI-LLI 0.00E0 6.43E-05 1 The CPS ODCM refers to " Mixed Release" as mixed mode.
Page 10 of 17
6.2 Gas Related Exposure Pathways 2
6.2.1 Fission and Activation Gases Air Dose (mrad) 1st Quarter 1987 2nd Quarter 1987 Gamma 0.00E00 2.87E-04 Beta 0.00E00 1.01E-04 6.2.2 Particulate, Radiciodine and Tritium Dose Equivalent (mrem) 1st Quarter 1987 2nd Quartar 1987 ,
1 Any Organ 0.00E00 4.76E-08 to the Lung 7.0 TECHNICAL SPECIFICATION REPORTS Per the Clinton Power Station Technical Specifications, certain reportable items, changes to Technical Specification referenced documents, and findings are reportable in Semiannual Radioactive Effluent Release Report. e 7.1 Limiting Condition for Operation Reports These reports are provided pursuant to the Clinton Power Station Technical Specifications, Section 3.3.7.11. Limiting Conditions for Operation (LCO) are defined in the CPS Technical Specifications.
7.1.1 LCO Event 87-3-71 7.1.1.1 Information Operability Requirement: Table 3.3.7.11-1-2a j Date Entered : 3/21/87 @ ~t443 hrs Date Restored : 4/29/87 @ 1354 hrs Time Period of LCO : 39 days 4.1 hrs 2 Lower Limit of Detection (LLD) Methodologies Gaseous grab samples from the effluent monitor were below the lower limit of detection. The restlts greater than MDA from post treatment grab samples were utilized in an assessment of gaseous effluent release.
Page 11 of 17
7.1.1.2 Explanation:
On March 21, the Plant Service Water Effluent Process Monitor (1RIX-PR036) was declared inoperable due to spurious readings of the count rate. To remedy the problem, a calibration was immediately initiated under surveillance procedure CPS No. 9910.76. During the calibration, a maintenance request was submitted on March 24, 1987, after the monitor failed the linearity acceptance criteria. After changing detectors and subsequent refnilure of the linearity criteria, it was noted that the voltage setting for the detector was 270V, a value much too low for a scintillation detector. This i discovery resulted in a revision of the surveillance procedure that was completed on April 8, 1987, as l documented in Field Problem Report (FPR) 251,481. The 1
procedure was revised and successfully performed on April 29, 1987. The Monitor was returned to service on April 29, 1987.
There was no radioactive material detected in releases via this pathway during the monitor inoperability period.
7.1.2 LCO Event 87-3-71 s
7.1.2.1 Information Operability Requirement: Table 3.3.7.11-1-la Date Entered : 2/27/87 @ 1345 hrs Date Restored : 4/23/87 @ 1909 hrs Time Period of LCO : 55 days 5.3 hrs 7.1.2.2 Explanation:
Prior to February 4, reliability of the liquid radwaste discharge valve was hampered by an intermittent isolation signal from the liquid discharge monitor (ORIX-PR040).
The signal was a result of low sample flow through the monitor.
The process of diagnosing this problem was begun on January 31 by submittal of Maintenance Work Request (MWR)
C47428. The monitor was declared anoperable immediately prior to the start of wor? on February 27. On April 1, a series of tests were conducted in an effort to determine if the sample pump was functioning properly or if the orifice in the suction line was preventing sufficient flow to the monitor. The results of these tests indicated the piping and mechanical components were functioning properly; however, a design modification was needed. Plant modification PR-31 was initiated to remove sample probe OAE-WE090 and age 12 of 17
replace it wi th a Tee connection between the process 7.is charc a pipe and the semple line, thus removing the flow
- iction and allowing the sample pump to deliver its design flow rate of sample through the monitor.
MWR C15086 was initiated on April 14 to install the approved design and this work completed on April 18. The monitor and the associated piping was tested on April 22 ,
and then successfully returned to service on April 23 by-restoring LL.e operability status and closing the LCO.
7.2 Off-Site Dose Calculation Manual Changes Technical Specification 6.14.2.a.1 requires that revisions to the CPS ODCM be reported in the Semiannual Effluent Release Report.
The following is a list of pages and summary of revision 2 to the ODCM that was issued in October 1986. Attachment A contains copies of the changed pages and documentation of required reviews.
This revision of the ODCM involved three broad areas of scope:
- 1) NRC recommended changes as a result of the acceptance review, ,
- 2) technical refinement of the methodology in which the organ doses i are summed to demonstrate Technical Specification compliance, and
- 3) simple typographical corrections discovered as a. result of utlization.
PAGE
SUMMARY
OF REVISION i
2-1 Added reference to Figure 2.5-1 per Enclosure 2 to NRC letter dated i 2-14-86: CLINTON POWER STATION UNIT 1 - ACCEPTANCE OF ODCM.
2-3 Combined the C 7 term with the C summation for simplification of equation (2) and deleted all references to C .
7 2-4 Combined the C 7/MPC 7 fraction with the C /MPC fraction for g
simplification of equation (3) and deleted all references to C and 7
MPCI . Restated equation (4) for clarity.
2-5 Combined equations (5) and (6) with equation (4) for clarity.
2-6 Unrestricted area boundary relocated to follow geographical boundaries. No change to Table 3.4-3 required.
2-7 2.3.2 Revised WS effluent sampling and analysis commitments.
l l
I 2.3.2.1: Deleted instruction to perform Section 2.3.1.5 to determine PRM setpoint since a modified dilution i factor must be determined first.
2.3.2.2: Revised symbols consistent with equation (4).
Page 13 of 17 )
k l
l I
1 PAGE f
2-8 Added reference to Figure 2.5-2 per Enclosure 2 to NRC letter dated I 2-14-86. Corrected section references and revised CX/CC effluent sampling and analysis commitments.
2-9 Defined release time period using actual parameters to prevent misinterpretation.
1 2-11 Reformatted Table 2.4-1 and corrected the LIVER dose commitment factor for Cu-64 as a result of the ODCM verification and validation project, 2-12 Reformatted Table 2.4-1, 2-13 Reformatted Table 2.4-1.
2-18 Revised Figure 2.5-1 to include reference to those monitors requir.ed by the CPS Tech Specs per Enclosure 2 to NRC letter dated 2-14-86.
2-19 Added a new figure 2.5-2 per Enclosure 2 to NRC letter dated 2-14-86.
2-20 Deleted equations referenced in Section 2.6 since they are not being used. Defined "significant" and added an explanation as to the action CPS would exercise if new liquid effluent pathways are determined to exist.
2-21 Table 2.6-1 deleted since section 2.6 equations were deleted.
2-22 Table 2.6-1 deleted since section 2,6 equations were deleted.
3-1 Typo " considered".
3-3 Reduced the number of SGTS Exhaust PRM (1PR003, 1PR004) monitoring channels from 9 to 6 per plant modification AR-15 and FPR 200,082.
Added reference to Figure 3.3-1 per Enclosure 2 to NRC letter dated 2-14-86.
3-4 Added reference to Figure 3.3-1 per Enclosure 2 to NRC letter dated 2-14-86. Added PRM failure as an isolation signal and indicated that the reactor scram may occur.
3-5 Added " greater than" sign. Changed symbol for the inhalation l pathway dose factor by adding a subscript "j".
3-6 Revised definition of the inhalation pathway dose factor to be organ-specific. Replaced the technically flawed "omni-organ" dose !
rate concept with a true maximum organ dose rate calculation.
3-9 Expanded Table 3.4.-2 dose rate factors to allow calculation of a f true maximum organ dose rate instead of an "omni-organ" dose rate. j Page 14 of 17
PAGE l 3-10 Refer to page 3-9.
3-11 Refer to page 3-9.
3-12 Revised dose rates based upon corrected dispersion and deposition data supplied by S&L letter SLLI-1687 dated 6-6-86.
3-13 Typo "(x/q) ,".
3.14 Added definition of short-term.
3.15 Added definition of short-term.
3-25 Stated that CPS will demonstrate compliance with the non-noble gas dose rate limitation without relying on monitor setpoint alarms..
3-27 Clarified that the value calculated by equation (20) is a setpoint.
Deleted all text referring to calculations of isotope-specific maximum acceptable concentrations since this is accounted for in the equation (19) summation term.
3-28 Change "QTj " to "Qg3 " to avoid confusion with the value calculated by equation (19).
3-29 Revised equation reference due to previous deletions.
3-30 Unrestricted area boundary relocated to follow geographical boundaries. No change to Table 3.4-3 required.
l 3-31 Added the SGTS monitors to Figure 3.3-1 per Enclosure 2 to NRC letter dated 2-14-86.
V "
3-108 " Ray" YPo "R,13 i
5-1 Added description of compositing method per memo RFP-86-964 dated l
11-25-86.
5-2 Revised date to reflect receipt of latest EPA crosscheck results.
5-6 Added new upstream sample location beyond the influent of CPS liquid effluents.
5-8 Revised per Enclosure 3 to NRC letter dated 2-14-86. Added footnote regarding irrigation.
5-9 Revised per Enclosure 3 to NRC letter dated 2-14-86.
5-10 Corrected sector and distance locators.
5-12 Corrected sector, distance and code locators.
l Page 15 of 17 L____________________________._____. _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ . _ _ _ _ _ _ _ . _ ._ _ _ . . . . _ _ _ . _ _ _ _ _
7 PAGE j 5-13 Added meteorological tower locations to Figure 5.0-1 per Enclosure 1 to NRC letter dated 2-14-86.
5-14 Revised the Non-Tech Spec well water sample location designator from "7E" to "7D" for consistency.
5-15 Added-new upstream surface water samp'le location "91" and new aquatic control sample location "105 .
6-1 Replaced reference to "RETS" with "0DCM methodology".
7-1 Stated that CPS may exercise the reporting option granted by. CPS TS 6.9.1.7. Added reference to the meteorological tower in Figure 5.0-1 per enclosure 1 to NRC letter dated 2-14-86.
7" Corrected dispersion and deposition data per S&L letter SLLI-1687 dated 6-6-86.
7-17 Added " delta" symbols.
7-21 SGTS Exhaust Stack diameter revised per memos DWH-D18-86. dated 1-22-86 and Y-32785 dated 1-13-86.
7-26 Added a "d" in the fourth term of equation (26).
7.3 Solid Waste PROCESS CONTROL PROGRAM Changes Technical Specification 6.13.2 requires that all changes to the Solid Waste Process Control Program (PCP) be reported in the Semiannual Report. The following is a list of those PCP changes that occurred during this report period.
The reference document is: " Process Control Program - ATI Transportable Volume Reduction System TVR III," Rev. 2, dated October 31, 1986. This document is proprietary to Associated Technologies Incorporated (ATI). ATI originated changes were made and implemented as applicable to CPS on June 15, 1987, as follows: j l
- 1. Specific procedures for waste sample analyses were deleted and replaced with a listing of the analyses required and a statement that analyses must be done in accordance with approved Clinton analytical chemistry procedures. This change was made so that methods of chemical analyses can be changed without changing the PCP.
- 2. Correction factors were added to correct the results.of sample analyses to account for dilution due to flushing the waste transfer line. This change was made so that the results of analyses of samples collected prior to the addition of the flush water can be correctly applied to the conterts of the Associated Technologies Incorporated (ATI) waste batch tank after the addition of flush water.
Page 16 of 17
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)
1 J
- 3. References to computer logging of the speeds of the surfactant i waste and bitumem pumps were deleted. This change was made to J reflect the actual method whereby the pump speeds are recorded in the operator log manually.
- 4. The frequency of recalibrating the evaporater feed pump was decreased. This change was made based on calibration history which indicated pump wear was slow and calibration frequency could be decreased.
- 5. Reference to an in-line conductivity meter in the distillate line was deleted. This change was made to reflect the actual condition. (The conductivity of the distillate is neither controlled nor recorded.)
- 6. An appendix, which detailed an analytical procedure for determining the reducing power for Class B and Class C sodium sulfate concentrates, was deleted. This change was made so that the method of chemical analysis can be changed without changing the PCP.
None of the changes made to the Process Control Program reduces the overall conformance of the solidified waste product to existing criteria for solid waste.
Revision 3 of the CPS-PCP, dated June 15, 1987, was reviewed and found acceptable by the Facility Review Group (FRG) on June 15, 1987. Attachment B provides documentation of FRG review and approval in the form of a " Solidification Vendor Procedure / Document Approval Cover Sheet," CPS No. 1913.03F001, 7.4 Major Changes to Radioactive Waste Treatment Systems Technical Specification 6.15 requires that revisions to the Effluent and Waste Treatment Systems be reported in the Semiannual Report. The following is a list of system changes that occurred during this report period.
o No major changes were made to the Waste Treatment Systems during this reporting period.
7.5 Land Use Census In accordance with Technical Specification 6.9.1.7, there were no new identified locations for dose calculations and/or monitoring sites identified by the July 1986 land use census required pursuant to Technical Specification 3.12.2.
Page 17 of 17
L.
8.0 TABLES TABLE 1A Gaseous Effluents-Summation of All Releases TABLE 1B Gaseous Effluents-Elevated Release TABLE 1C Gaseous Effluents-Mixed Releases TABLE 2A Liquid Effluents-Summation of All Releases TABLE 2B Liquid Effluents TABLE 3 Solid Waste and Irradiated Fuel Shipments TABLE 4A Joint Frequency Distribution of Meteorological Parameters TABLE 4B Classification of Atmospheric Stability TABLE 5 Radioactive Gaseous Waste Sampling and Analysis Program TABLE 6 Radioactive Liquid Waste Sampling and Analysis Program 1
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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1987)
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL i 1 2 ERROR, %
l A. FISSION & ACTIVATION GASES
- 1. Total release Ci 0.0 E0 1.03 EO 7.50 El
- 2. Average release rate for period uCi/sec 0.0 E0 1.31 E-1
- 3. Percent of Technical Specification limit % 0.0 0.0 B. I0 DINES
- 1. Total iodine-131 Ci 0.0 EO 0.00 EO 0.0 E0 j
- 3. Percent of Technical Specification limit % 0.0 0.0 i
C. Particulate
- 1. Particulate with half-life >8 days Ci 0.0 EO 3.64 E-5 7.50 El
- 2. Average release rate for period uCi/sec 0.0 EO 0.00 E0 j 3. Percent of Technical Specification limit % 0.0 0.0 1
- 4. Gross alpha radioactivity. Ci 6.54 E-7 2.05 E-7 D. Tritium
- 3. Percent of Technical Specification limit % 0.0 0.00 1
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l
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1 I
l TABLE IB GASEOUS EFFLUENTS -
ELEVATED RELEASE (All CPS Releases were considered Mixed Release )
1 See Section 5.0 for definition o' Mixed Re) case.
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TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1987)
GASEOUS EFFLUENTS - MIXED RELEASES i
CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2 ,
I
- 1. Fission Gases [None this period]
Krypton-85 Ci 0.00 EO U.00 EO . E . E Krypton-85m (Note 2) C1 0.00 EO 5.77 E-3 . E . E Krypton-87 Ci 0.00 EO 0.00 EO . E . E Krypton-88 C1 0.00 EO 0.00 EO . E . E Xenon-133 Ci 0.00 F0 0.00 EO . E . E Xenon-135 C1 0.00 EO 0.00 EO . E . E Xenon-135m Ci 0.00 EO 0.00 LO . E . E j Xenon-138 Ci 0.00 EO 0.00 EO . E , E Others (Specify) C1 0.00 EO 0.00 EO . E . E l Ar-41 (Note 2) Ci 0.00 E0 1.02 EO . E . E C1 0.00 EO 0.00 EO . E . E l Total for Period Ci 0.00 E0 1.03 EO . E . E l
l 2. Iodines l
l Iodine-131 Ci 0.00 EO 0.00 EO . E . E 1
! Iodine-133 Ci 0.00 EO 0.00 EO . E , E Iodine-135 C1 0.00 EO 0.00 EO . E . E Total for Period Ci 0.00 EO 0.00 EO . E . E
- 3. Particulate l
l Strontium-89 Ci 0.00 EO 0.00 EO . E . E Strontium-90 Ci 0.00 EO 0.00 EO . E . E Cesium-137 Ci 0.00 EO 0.00 EO . E . E Barium-lanthanum-140 C1 0.00 EO 0.00 EO . E . E Others (Specify) Ci 0.00 EO 0.00 EO . E . E Chromium-51 C1 0.00 EO 3.64 E-5 . E. . E_ _
C1 . E . E . E . E l
l l
1 See Section 5.0 for Definition of Mixed Release.
2 Estimation based on Offgas System samples.
I l
TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1987) )
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total )'
1 2 Error, %
A. Fission and Activation Products
- 1. Total release (not including tritium, gases, alpha) Ci 0.00 E0 2.82 E-4 7.50 El
- 2. Average diluted concentration during period uCi/ml 0.00 EO 8.83 E-10
- 3. Percent of applicable limit % 0.0 < 0.1 B. Tritium
- 2. Average diluted concentration during period uCi/ml 0.00 EO 0.00 E0,
- 3. Percent of applicable limit % 0.0 0.0 C. Dissolved and entrained gases
- 3. Percent of applicable limit % 0.0 0.0 D. Gross alpha radioactivity
~~
- 1. Total Release Ci 4.46 E-7 4.18 E-6 7.50 El E. Volume of waste released (prior te dilution) liters 7.75 E5 3.34 E6 1.5 El F. Volume of dilution water used during period liters 7.58 E7 3.16 E8 1.5 El 1
m_________________._. _
TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1987)
LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2 Strontium-89 Ci . E . E 0.00 E 0.00 E Strontium-90 Ci . E . E 0.00 E 0.00 E Cesium-134 C1 . E . E 0.00 E 0.00 E Cesium-137 Ci . E . E 0.00 E O.00 E Iodine-131 Ci . E . E 0.00 E 0.00 E Cobalt-58 C1 . E . E 0.00 E 3.50 E-5 Cobalt-60 C1 . E . E 0.00 E 0.00 E-0 Iron-59 Ci . E . E 0.00 E 1.28 E-5 Manganese-54 C1 . E . E 0.00 E 1.43 E-5 Chromium-51 Ci . E . E 0.00 E 2.20 E-4 Zirconium-niobium-95 Ci . E . E 0.00 E 0.00 E Molybdenum-99 C1 . E . E 0.00 E 0.00 E Technetium-99m Ci . E . E 0.00 E 0.00 E Barium-lanthanum-140 C1 . E . E 0.00 E 0.00 E Cerium-141 Ci . E . E 0.00 E 0.00 E Other (Specify) Ci . E . E O.00 E 0.00 E C1 . E . E 0.00 E 0.00 E C1 . E . E 0.00 E 0.00 E C1 . E . E O.00 E 0.00 E Ci . E . E 0.00 E 0.00 E Total for period (above) Ci . E . E 0.00 E 2.82 E-4 Xenon-133 Ci . E . E 0.00 E 0.00 E Xenon-135 Ci . E . E 0.00 E 0.00 E
\~
TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1987)I SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1. Type of Waste Unit 6-month Est. Total Period Error, %
- a. Spent resins, filter sludges, evaporator m 0.00 E0 bottoms, etc. Ci 0.00 EO 0.0 3
- b. Dry compressible waste, contaminated m 0.00 E0 equip, etc. Ci 0.00 EO 0.0
- d. Other (describe) m 0.00 E0 Ci 0.00 EO 0.0
- 2. Estimate of major nuclide composition (by type of waste) a.None Z . E
% . E
% . E b None % . E
% . E
% . E c.None % . E
% . E
% . E d.None % . E
% . E
% . E
- 3. Solid Waste Disposition
)
Number of Shipments Mode of Transportation Destination J None B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination i
None l C. TECHNICAL SPECIFICATIONS CLASSIFICATION REQUIREMENTS - NA I
1 No solid waste or irradiated fuels during this reporting period.
L 1
f-l' l
l 1
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I TABLE 4A '
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL PARAMETERS l
I 1
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l 1
1 Not submitted this period; see section 5.0.
TABLE 4B CLASSIFICATION OF ATMOSPHERIC STABILITY.
Stability Pasquill log Temperature change Classification Categories (degrees) with height ('C/100m)
Extremely unstable A 25.0 -1.9 Moderately unstable B 20.0 -1.9 to -1.7 Slightly unstable C 15.0 -1.7 to -1.5 Neutral D 10.0 -1.5 to -0.5 Slightly stable E 5.0 -0.5 to 1.5 Moderately stable F 2.5 1.5 to 4.0 Extremely stabic 0 1.7 4.0 ,.
1 Standard deviation of horizontal wind direction over a period of 15 minutes to I hour. "
The values shown are average for each stability classification. l l
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LIl f 1 1 1 Tm4 6 4 6 ly 1 1 1 RC/ - - - - - - - ~ -
EEi 0 0 0 0 00 0 0 0 WTC 1 1 1 1 11 1 1 1 OEu x x x x xx x x x LD( l 1 1 1 1l l 1 1 M s s s A r r r R e e e G t t t O t t t R i i i P m m m S E E E S I I S a a a) ms S Y m m
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_ O NAE n n ea E INR o o eh eaa ooaa uoaa
_ S MAF M M WC WPS MCPS QCPS
_ A G
e e E l l s s s s V Y p p u u u u I GC m m o o o o T NN ya ya u u u u C IE lS lS n n n n A LU h h i i i i O PQ tb tb t t t t I ME na na n n n n D AR or or o o o o A SF MG MG C C C C R
w d o sn E ml ea P ef p Y t yA T sn T C ye n E A sSh ei S V a w s A H Gt ad .
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S A . . .
G_ A B C ll\
Table 6
_ RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION ,
LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) l TYPE FREQUENCY FREQUENCY ANALYSIS (uci/ml) ,
A. Batch Waste Prior to Prior to Principal Gamma 5x10-7 j Release each each Emitters I release- release Each Batch Each Batch ^
)
I-131 1x10-6 Prior to Monthly Dissolved and 1x10-5 each Entrained Gases release (Gamma Emitters) !
Prior to Quarterly H-3 1x10-5 each Composite release-Each Batch Gross Alpha 1x10~7 Prior to Quarterly Sr-89, Sr-90 1x10-8 q each Composite release-Each Batch Fe-55 1x10-6 1
l 1
1
q l
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i l
i CLINTON POWER STATION j SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT )
l February 27, 1987 - June 30, 1987 !
l 1
l ATTACHMENT A f l
W OFFSITE DOSE CALCULATION MANUAL REVISION 2 AFFECTED PAGES i
i
ATTACHMENT A ODCM REVISION 2, EFFECTED PAGES
- 1) 10CFR 50.59 Safety Evaluation Form
- 2) Revision Summary & Approval
- 3) Revision 2 Pages
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. 10CFR50:59 SAFETY 'EVALIJATION FORM -
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s .l Document' Evaluated: Mud (cDo U h 2. - (oIP& L&S Lo*g #: a~NP l d% m -
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.l s NOTE: Every statement or conclusion (YES or NO) on this form must be justified in the space provided. (Use additional pages if necessary). -
~
i I
1 4 q BLOCK A 1 -
The document.to which this evaluation applies constitutes a:
P) ~ .
YES./NO A. Change to Clinton Power Station permanent V .
, equipmerit , systems or structures. ,
v YES NO. B. Procedure or change to a procedure as described
.. . in the FSAR. -
/ YES v'NO C.
D.
Test not described in the FSAR.
- YES s./ NO Experiment noe described in the FSAR..
Because: Adsie,, L b b onc.K Cms Wkhd 6 heeccnsa b 5 A9c fdha bd Id (c /1; A IIcw e e,b b e 4t$ we bM( . d, A ant [(' L1'P) 7Il' m. /jl.@ -/,. (( ,,
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l l If any of the above statements were answered "YES", ccmplete i
-- blocks B, C, D, and E. If all of the above statements were I answered "NO", a 10CFR50.59 review is not recuired; ccmrletion of blocks 3 and D is optional; block C shall'be complet'ed. .
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- applies
3 I
. involves,a mo~dificati'n o to the Radiological Waste
..,dI Treatment System, as; described in the FSAR.
Because: $ oncS Owulus kc N5 a3 kf 8c5 cembout t Eh .
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Safety Evaluation for Changes to Radioactive Waste Treatment <
System. .
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. , j BLOCK C .
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YES V NO The document to which this evaluation applies 1nvolves a. change to the Technical Specifications or Operating License. -
Because: 4k crtn s'< a Gaoluu anulud 1% %lo.de. $ %e:Llc 2 k.D A mt$,
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Implementation or performance of the action described in the evaluated document will: '
YES , NO A. Increase the probabilii:y of occurrence of an accident previously evaluated in the FSAR.
YES / NO B. Increase the consequences of an accident i previously evaluated in the FSAR. '
YES / NO C. Create the possibility,of an accident of a different tfpe than any already evaluated in the 1 FSAR. '
YES [ NO D. Increase the probability of'a malfunction of equipment impcrtant to safety previously i evaluated in the FSAR. .
)
NF-002-2 (9/S6) .
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., YES. NO: F. Create.the. poss'ibility.of a malfunction of -
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YES VNO Reduce the margin of safety as defined i'n the G. l basis for any technical'. specification. .
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If any statement'in this section was answered "YES", the action i described in the evaluated document involves an Unreviewed. Safety Question._
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Check'the applicable boxe's: ' ' '- '
((. Evaluated'documeNit'dcesnbtk.nv'olveachangatotheTechnica1.'.'
~
Specifications or Operating;. License or an Unrev.'.ewed Safety 1 Question. Proceed.with implementation. .
[] ..
The evaluated documen't involves a change i:o the Technical Specifications or Operating License. NRC. approval is l
required before implementation. .
,j
[].
I Evaluated document involves Unreviewed Saf'ty e Question. NRC i approval required before implementation. !
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Orig'nsco g Date Manager - Lice 1 Ming & Safety Date Dep t=e 't He c b Il- 4!- Date Ils
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NF-002 4 (9/86)
CPS-0DCM l Revision Summarv i
! l l Page l i
2-1 Added refet .ce to Figure 2.5-1 per Enclosure 2 to NRC letter I l dated 2-ll od: CLINTON POWER STATION UNIT 1 - ACCEPTANCE OF i i THE ODCh. 1 I
2-3 Combined the C 7 term with the C g summation for simplification of equation (2) and deleted all references to C 7.
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2-4 Combined the C 7/MPC 7 fraction with the C /MPC g g fraction for l simplification of equation,(3) and deleted all references to C 7 i i and MPC7 . Restated equation (4) for clarity.
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2-5 Combined equations (5) and (6) with equation (4) for clarity. i 2-6 Unrestricted area boundary relocated to follow geographical 4 boundaries. No change to Table 3.4-3 required.
2-7 2.3.2 Revised WS effluent sampling and analysis 1 commitments. I J
2.3.2.1: Deleted instruction to perform section 2.3.1.5 to determine PRM serpoint since a modified dilution factor must be determined first.
2.3.2.2: Revised symbols consistent with equation (4).
2-8 Added reference to Figure 2.5-2 per Enclosure 2 to NRC letter 1 dated 2-14-86. Corrected section references and revised SX/CC !
effluent sampling and analysis commitments. ;
1 2-9 Defined release time period using actual parameters to prevent i misinterpretation.
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2-11 Reformatted Table 2.4-1 and corrected the LIVER dose commitment factor for Cu-64 as a result of the ODCM verification t;d -
validation project.
2-12 Reformatted Table 2.4-1.
2-13 Reformatted Table 2.4-1.
2-18 Revised Figure 2.5-1 to include reference to those monitors required by the CPS Tech Specs per Enclosure 2 to NRC letter dated 2-14-86.
2-19 Added a new Figure 2.5-2 per Enclosure 2 to NRC letter dated 2-14-86.
CLINTON-I 1 Rev. 2-10/86
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CPS-0DCML )
l Revision Summary +
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2-20 Deleted equations referenced in section 2.6 since they ar'e not being used. Defined "significant" and added an explanation as
to the action CPS would exercise if new liquid effluent pathways are determined to exist.
2-21 Table 2.6-1 deleted since section 2. 6 equations were deleted.
2-22 Table 2.6-1 deleted since section 2.6 equations were deleted.
l 3-1 Typo " considered".
i 3-3 Reduced the numoer of SGTS Exhaust PRM (lPR003, 1PR004) monitoring channels from 9 to 6 per, plant modification AR-15 and FPR 200,082. Added reference to Figure-3.3-1 per Enclosure 2 to NRC letter dated 2-14'-86.
l 3-4 Added reference to Figure 3.3-1 per Enclosure 2 to NRC letter dated 2-14-86. Added PRM failure as an isolation signal and indicated that the reactor scram may occur.
! 3-5 Added " greater than" sign. Changed symbol for the inhalation pathway dose factor by adding a subscript "j " .
3-6 Revised definition of the inhalation pathway dose factor to be i
organ-specific. Replaced the technically flawed "omni-organ" l dose rate concept with a true maximum organ dose rate-calculation.
3-9 Expanded Table 3.4-2 dose rate factors to allow calculation of a true maximum organ dose rate instead of an "omni-organ" dose rate.
l 3-10 Refer to page 3-9.
3-11 Refer to page 3-9.
3-12 Revised dose rates based upon corrected dispersion and l deposition data supplied by S&L letter SLLI-1687 dated 6-6-86.
3-13 Typo "(x/q) ".
3-14 Added definition of short-term.
3-16 Added derinition of short-term.
3-25 Stated that CPS will demonstrate compliance with the non-noble I gas dose rate limitation without relying on monitor setpoint alarms. ,
I CLINTON-I 2 Rev. 2-10/86
CPS-0DCM ,
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Revision Summary Page )
l 3-27 Clarified that the value calculated by equation (20) is a setpoint. Deleted all text referring to calculation of isotope-specific maximum acceptable concentrations since this is accounted for in the equation (19) summation term.
3-28 Changed "Q Tj " U "9 Sj "t av id confusion with the value calculated by equation (19).
3-29 Revised equation reference due to previous deletions.
3-30 Unrestricted area boundary relocated to follow geographical boundaries. No change to Table 3.4-3 required.
3-31 Added the SGTS monitors to Figure 3.3-1 per Enclosure 2 to NRC letter dated 2-14-86.
l l 3-108 Typo "R 13 l 5-1 Added description of compositing method per memo RFP-86-964 l
dated 11-25-86.
5-2 Revised date to reflect receipt of latest EPA crosscheck results.
5-6 Added new upstream sample location beyond the influence ot' CPS liquid effluents.
l 5-8 Revised per Enclosure 3 to NRC letter dated 2-14-86. Added footnote regarding irrigation.
5-9 Revised per Enclosure 3 to NRC letter dated 2-14-86.
5-10 Corrected sector and distance locators. I l
5-12 Corrected sector, distance and code locators. !
5 13 Added meteorological tower locations to Figure 5.0-1 per l l Enclosure 1 to NRC letter dated 2-14-86. l 1
5-14 Revised the Non-Tech Spec well water sample location designator from "7E" to "7D" for consistency.
5-15 Added new upstream surface water sample location "91" and new aquatic control sample location "105".
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6-1 Replaced reference to "RETS" with "0DCM methodology".
1 CLINTON-I 3 Rev. 2-10/86
CPS-0DCM .] 1 Revision Summary e P, age, 7-1 Stated that CPS may exercise the reporting option granted by .
CPS TS 6.9.1.7. Added reference to the. meteorological tower in Figure 5.0-1 per Enclosure 1 to NRC letter dated 2-14-86.
7-6 Corrected dispersion and deposition data per S&L letter through SLLI-1687 dated 6-6-86.
7-13 7-15 SGTS Exhaust Stack physical dimensions and exit velocity l revised per memos DWH-018-86 dated 1-22-86 and Y-32785 dated ]
1-13-86. 1 7-16 Corrected dispersion and deposition data per S&L letter SLLI-1687 dated 6-6-86.
7-17 Added " delta" symbols. ,
7-21 SGTS Exhaust Stack diameter revised per memos DWH-D18-86 dated 1-22-86 and Y-32785 dated 1-13-86.
7-26 Added a "d" in the fourth term of equation (26).
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i Pursuant to CPS Technical Specification 6.14.2.a.3, revision 2 to the CPS-0DCM has been reviewed and found to be acceptable by the FRG.
&h 7m*t -- a- 2 z-PA \
/qg/ Chairman Approval Date 1
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CLINTON-I 4 Rev. 2-10/86 l i _ _ _ - _ _ - _ _
CPS-0DCM '
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ILLIN0IS POWER COMPANY CLINTON POWER STATION UNIT 1 i
0FFSITE DOSE CALCULATION MANUAL l
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Docket No. 50-461 'J l
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CLINTON-I Rev.2-10/86 l
, CPS-0DCM , 4 Illinois Power Company Clinton Power St'ation OFFSITE DOSE CALCULATION MANUAL Table of Contents Section Title Page 1.0 PREFACE l-1 2.0 LIQUID EI FLUENTS 2-1 i 2.1 Introduction 2-1 2.2 L'iquid Radwaste Discharge P'roces's Radiation 2-1 Monitoring (PRM) System 2.2.1 Method of Representative Sampling 2-1 l
l 2.3 10CFR20 Release Rate Limits 2-1 2.3.1 Liquid Radwaste Discharge PRM 2-2 j Setpoints '
2.3.2 ' Plant Service Water Effluent 2-7 PRM Setpoints l 2.3.3 Shutdown Service Water (SX) Effluent 2-8 l PRM Setpoints ,
2.3.4 Fuel Fool Heat Exchanger Service 2-8 Water Effluent PRM Setpoints i 2.4 10CFR50, Appendix I Release Rate' Limits 2-9 1 2.5 Compliance With CPS RETS 3.11.1.3/3.11.1.4 2-20 1
2.6 Doses From Other Significant Liquid Effluent l Pathways 2-20 h c
3.0 GASEOUS EFFLUENTS 3-1 3.1 Introduction 3-1 3.2 Gaseous Effluent Release Point Monitoring 3-2 3.2.1 HVAC Stack Process Radiation 3-2 Monitoring (PRM) System CLINTON-I i Rev.2-10/86
CPS-0DCM Table ~of Contents Section Title _Page-3.0 3.2.2 SGTS Stack Process Radiation 3-2 Monitoring (PRM) System l
3.3 Main Condenser Off-Gas Monitoring System 3-3 3.3.1 Pre-Treatment Air Ejector Off-Gas 3-3 PRM 3.3.2 Post-Treatment Air Ejector Off-Gas 3-4 PRM 3.4 10CFR20 Release Rate Limits 3-4 l
l 3.4.1. Dose Rate Due to Noble Gases 3-5 !
3.4.2- Dose Rate Due to Radioiodines, 3-5 Particulate and Tritium j i
3.5 10CFR50, Appendix I Release Rate Limits 3-13 3.5.1 Noble Gas Air Dose 3-13 3.5.2 Radiciodines, Particulate and 3-15
. Tritium Dose ,
3.6 Compliance With CPS RETS 3.11.2.4/3.11.2.5 3'-25 3.7 Effluent Monitor Setpoint Calculations 3-25 ;
i 3.7.1 Total Body Dose Rate Setpoint 3-26 3.7.2 Skin Dose Rate Setpoint 3-28 1
4.0 COMPLIANCE WITH 40CFR190 4-1 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5-1 5.1 Interlaboratory Comparison Program 5-1 6.0 ADJUSTMENT OF THE CPS ODCM METHODOLOGY 6-1 j 7.0 ATMOSPHERIC TRANSPORT AND DISPERSION MODEL 7-1 CLINTON-1 ii Rev.2-10/86
CPS-0DCM l
l Tab'e l of' Contents Section Title _ _ _
Page. )
7.0 7.1 Introduction 7-1 I
7.2 Historical Meteorological Data Processing 7-1 7.2.1 Numerical Model 7-2 7.2.2 Source Configuration Considerations 7-3 7.2.3 Relative Deposition Factor 7-4 7.3 Concurrent Meteorological Data Processing 7-17 1 7.3.1 Determination of Pasquill Stability 7-17 Class 7.3.2 Calculation of Stack Height Wind 7-18 Speed 7.3.3 Determination of Release Mode and the 7-19 Entrainment Coefficient l
7.3.4 Calculation of Vertical Standard 7-20 Deviation 7.3.5 Calculation of'the Build'ing Wake 7'20 Correction s
7.3.6 Calculation of Momentum Plume Rise 7-21
- j. 7.3.7 Calculation of Effective Plume Height 7-22 7.3.8 Determination of Affected Sectors 7-22 7.3.9 Calculation of Depletion and 7-23 Deposition Factors 7.3.10 Ground Level X/Q, D2DPXQ, D1XQ, D/Q 7-27 l Analysis j 1
l 7.3.11 Elevated X/Q, D2DPXQ, D1XQ, !
I D/Q Analysis 7-29 7.3.12 Short Term Dispersion Calculations 7-30 4 I
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' CPS-0DCM Tables Table Title Page 2.4-1 Adult Ingestic - Dose Commitment Factors-A 2-11 j 13 2.4-2 Bioaccumulation Factors-BF g 2-14 2.4-3 Adult Ingestion Dose Factors-DF f 2-15 f 2.6-1 Input parameters for Calculating Rad (DELETED) 2-21 l 3.4-1 Dose Factors For Noble Gases and Daughters 3-8 3.4-2 Inhalation Pathway Dose Rate Factors (CHILD)-P g 3-9 l 3.4-3 Annual Doses in Unrestricted Areas 3-12 l 3.5-1 Inhalation Dose Factors For Infant-(DFAg)a 3 3.5-2 Inhalation Dose Factors For Child-(DFAg )a 3-35 l
3.5-3 Inhalation Dose Factors For Teen-(DFAg ), 3-38 3.5-4 Inhalation Dose Factorc For Adult-(DFAt )a 3-41
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3.5-5 Ground Plane Dose Factors-DFG 1 3-44 3.5-6 Ingestion Dose Factors For Infant-(DFLg ), 3-46
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3.5-7 Ingection Dose Factors For Child-(DFLg)a 3-49 l
3.5-8 Ingestion Dose Factors For Teen-(DFLg )a 3-52 ]
3.5-9 Ingestion Dose Factors For Adult-(DFLg)a 3-55 3.5-10 Input Parameters For Calculating RC 3-58 aij 3.5-11 Input Parameters For Calculating R 3-59 13 3.5-12 Input Parameters For Calculating R 3-60 l 13 I
3.5-13 Inhalation Pathway Dose Rate Factors - RaQ (INFANT) 3-61 l 3.5-14 InhalationPathwayDoseRateFactors-Rft) (CHILD) 3-64 3.5-15 Inhalation Pathway Dose Rate Factors - R (TEEN) 3-67 3.5-16 Inhalation Pathway Dose Rate Factors - R,1j (AD M ) 3-70 CLINTON-I iv Rev.2-10/86
CPS-ODCM ,
Tables Table Title Pane 3.5-17 CowMilkPathwayDoseRateFactors-Rff3(INFANT) 3-73 3.5-18 Cow Milk Pathway Dose Rate Factors - R 13 (CHILD) 3-76 3.5-19 Cow Milk Pathway Dose Rate Factors - R,C (TEEN) 3-79 l 3.5-20 Cow Milk Pathway Dose Rate Factors -Rfgj (ADULT) 3-82 3.5-21 GoatMilkPathwayDoseRateFactors-Rfg3(INFANT) 3-85 C
3.5-22 Goat Milk Pathway Dose Rate Factors - Ray (CHILD) 3-88 3.5-23 GoatMilkPathwayDoseRateFactors-Rff) (TEEN) 3-91 3.5-24 C Goat Milk Pathway Dose Rate Factors - RaQ (ADULT) 3-94 3.5-25 Meat Pathway Dose Rate Factors - R (CHILD) 3-97 3.5-26 Meat Pathway Dose Rate Factors -R (TEEN) 3-100 3.5-27 Meat Pathway Dose Rate Factors - R (ADULT) 3-103 3.5-28 Vegetation Pathway Dose Rate Factors - R 13 (CHILD) 3-106 3.5-29 Vegetation Pathway Dose Rate Factors - RY (TEEN) ~ 3-109 aij 3.5-30 Vegetation Pathway Dose Rate Factors - R Y (ADULT) 3-112 aij 3.5.31 Ground Plane Pathway Dose Rate Factors - R G 3-115 5.0-1 Radiological Environmental Monitoring Program Sampling and Collection Frequencies 5-3 7.2-1 Annual Average Mixed-Mode X/Q 7-6 7.2-2 Annual Average Mixed-Mode D/Q 7-10 7.2-3 Wind Speed and Wind Direction Classification 7-14 7.2-4 Gaseous Effluent Release Point Characteristics 7-15 7.2-5 Site Boundary Dispersion and Deposition Parameters 7-16 CLINTON ' v Rev.1-11/85
CPS-0DCM' Figures
. l Figure Title P3ge 2.1-1 Unrestricted Area Boundary For Liquid Effluents 2-6 2.5-1 Liquid Radwaste Treatment System 2-18 2.5-2 Shutdown and Fuel Pool Heat Exchanger Service Water Effluent Monitors ,
2-19 3.1-1 CPS Site Boundary For Gaseous Effluents 3-30 3.3-1 Main Condenser Off-Gas Treatment System 3-31' 5.0-1 REMP Locations Within 1.5 Miles of CPS 5 5.0-2 REMP Locations Within 6 Miles of CPS 5-14 5.0-3 REMP Locations Within 50 Miles of CPS 5-15 l
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l CLINTON-I vi Rev.2-10/86
. List of Effective Pages Page Revision Page Revision Page Revision Page Revision i 2 3-16 2 3-65 1 4-1 1 11 2 3-17 1 3-66 1 iii 1 3-18 1 3-67 1 5-1 2 l iv 2 3-19 1 3-68 1 5-2 2 l v 1 3-20 1 3-69 1 5-3 1 vi 2 3-21 1 3-70 1 5-4 1 ;
vii 2 3-22 1 3-71 1 5-5 1 l 3-23 1 3-72 1 5-6 2 1-1 1 3-24 1 3-73 1 5-7 1 3-25 2 3-74 1 5-8 2 2-1 2 3-26 1 3-75 1 5-9 2 2-2 1 3-27 2 3-76 1 5-10 2 2-3 2 3-28 2 3-77 1 5-11 1 2-4 2 3-29 2 3-78 1 5-12 2 2-5 2 3-30 2 3-79 1 5-13 2 2-6 2 3-31 2 3-80 1 5-14 2 2-7 2 3-32 1 3-81 1 5-15 2 2-8 2 3-33 1 3-82 1 2-9 2 3-34 1 3-83 1 6-1 2 2-10 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 1 7-3 1 2-13 1 3-39 .1 3-88 1 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 3-44 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 2-23 2 3-49 1 3-98 1 7-14 1 2-24 2 3-50 1 3-99 1 7-15 2 2-25 2 3-51 1 3-100 1 7-16 2 3-1 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 2 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 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 2 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 3-15 1 3-115 1 7-31 1 CLINTON-I vii Rev.2-10/86
CPS-0DCM 2.0 LIQUID EFFLUENTS l
2.1 Introduction l I
Liquid radwaste effluent released from CPS will meet 10CFR20 l
concentration limits at the point of discharge to the unrestricted area shown in Figure 2.1-1. This design and operation obj ective ;
will be achieved at all times. Actual discharges of liquid j radwaste effluent will occur on a batch basis and the average concentration at the pofat of discharge will normally be only a j small percentage of the allowed limits. Reference Clinton FSAR j Section 11.5 for a description of radiation monitoring, sampling and effluent control systems. l 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 i 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 p:. ant service water and circulating water dilution streams. A high radioactivity signal from this gamma scintillation detector automatically terminates the liquid radwaste effluent release. The liquid radwaste effluent l flow, variable ~from 10-60 GPM or 50-300 GPM, combines with Plant l l Service Water flow (22,000 GPM minimum) and Plant Circulating Water j l flov (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). l.'
2.2.1 Method of Representative Sampling To obtain a representative sample of the liquid radwaste tank i to be discharged, the tank is isolated from c!1 inputs and l recirculated a minimum of two tank volumes at which time a j sample is obtained for isotopic analysis. ;
2.3 10CFR20 Release Rate Limits The requirements pertaining to discharge of li. quid radwaste effluent to _he unrestricted area are specified in CPS RETS 3.11.1.1:
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l CLINTON-I 2-1 Rev.2-10/86
CPS-0DCM L 1
The available dilution water flow (F) should be constant for'a I given release, and the liquid radwaste tank discharge flow (f) and l monitor setpoint (c) are set to meet the condition of equation (1) l for a given effluent concentration ( The method by which d this is accomplished is illustrated i pke)c.tions 2.3.1.1 through 2.3.1.5.
1 2.3.1.1 The isotopic concentration for a liquid radwaste tank to be I discharged is obtained from the sum of the measured )
concentrations as determined by the analyses required in CPS ;
RETS Table 4.11-1: )
{Ct -gC+jC+jC+C+C g a s T Fe, UCi/ml (2) where EC = The sum of concentrations C of each l 88 8 l1 measured gamma emitter g (including I-131) I l
observed by gamma spectroscopy of the waste sample, uCi/ml.
EC = The sum of Concentrations C of alpha emitters (a) aa in liquid radwaste as measu9ed in the MONTHLY !
composite sample, pCi/ml.
TC Bs = The sum of concentrations C of Sr-89/Sr-90 fn liquid radwaste as observedsin the QUARTERLY composite sample, uCi/ml.
C T = The measured concentration of H-3 in liquid radwaste l as determined from analysis of the MONTHLY composite '
sample, pCi/ml.
C Fe = The measured concentration of Fe-55 in liquid radwaste as observed in the QUARTERLY composite sample, LCi/ml.
CLINTON-1 2-3 Rev.2-10/86
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CPS-0DCM 2.3.1.2 ~The measured radionuclid'e concentrations are used to calculate a DILUTION FACTOR (DF) which is the ratio of I total dilution flow rate to liquid radwaste tank 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 g _), dimensionless (3) i
=
C g C, .C s C T
C Fe SF g . . , , 3 MPC MPC a MPC s MPC T MPC Fe g g 3 s 1 where C - The measured concentrations C , C,, C , C '
1 g s T C
Fe as defined in equation.(2), pCi/ml.
MPC f = The limiting concentration of the corresponding radionuclides MPC , MPC , MPC , MPC , MPC f#
- g a s T Fe 10CFR20, Appendix B, Table II, Column 2, uCi/ml.
For dissolved or entrained noble gases, the concentration shall be limited to 2E-04pCi/ml total activity. j 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:
F tank
=
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 f
rank = 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),
dimensionless CLINTON-I 2-4 Rev.2-10/86
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CPS-0DCM Equation ('4) is val'id. only ~ for DF > 1; for DFc 1, the liduid radwaste tank effluent concentratfbn meets the limits of 10CFR20 without dilution and therefore F tank may assume any value not to exceed discharge pump capacity. l 2.3.1.4 The liquid radwaste discharge PRM setpoint may now be specifiedbasedonthevaluesof{Cg (Eq.2) and Frank (Eq.4) l which were determined to provide compliance with the l concentration limits of 10CFR20, Appendix B, Table II, Column
- 2. The monitor response is primarily a gamma response and the actualsetpointisthereforebasedon{Cg (Eq.2). The monitor setpoint, in counts per minute (cpm), which corresponds to the particular setpoint concentration, C, M is 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 a laboratory methods of determination are proven more accurate
, than the monitor data.
The set point concentration, C, M is obtained by the following equation:
C M
= tank E C , p Ci/ml (5) f 88 act l
where
=
f act The actual liquid radwaste effluent flow rate, volume / time If (f tank / fact)> 1, the value obtained for CM da used to determine the monitor setpoint above backgrcund, cepm, from either of the two methods described above. In the case where (F <l die 8EIr/fgcha)rame,tervaluesno g release (DF, mayfact)*
Ftank, be made us!.ng the existing l
The setpoint concentration is conservative, even if F is 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, g,calculatedbyequation(5). This setpoint is valid only du_ing periods of actual liquid radwaste discharges.
CLINTON-I 2-5 Rev.2-10/86
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CPS-ODCM 2.3.2 Plant Service Water Effluent PRM Setpoints Plant service water effluent continuously releases to the Seal Well where it mixes with circulating water effluent (if present) prior to entering Lake Clinton via the 3.4 mile discharge fiume. The plant service water effluent is not considered a radioactive discharge pathway unless liquid radwaste discharges are in progress or any service water cooling load heat exchanger has been detected as failed. To ensure that Plant Service Water intersystem leakage has not occurred, weekly Service Water effluent grab samples will be obtained (when in service) and analyzed to determine the identity and quantity of principal gamma-emitting radionuclides. In addition, a quarterly composite of positive grab samples will be analyzed to determine the quantity of H-3, Sr-89, Sr-90, Fe-55 and gross alpha species released. The analytical Lower Limit of Detection (LLD) for these analyses are specified in CPS-RETS Table 4.11.1-1.A.
If the weekly grab sample analysis indicates the absence of contamination above background, the Plant Service Water effluent PRM setpoint should be established at three times background. This setpoint shall not exceed the corresponding MFC for the most limiting radionuclides (normally I-131) before applying safety and dilution factors.
1 If the weekly grab sample analysis indicates the presence of contamination above background, PRM setpoints will be established following section 2.3.1 methodology as follows:
l l 2.3.2.1 Perform section 2.3.1.2, solving equation (3) for DF using I
the appropriate values in the concentration term from the grab sample analysis. I 2.3.2.2 A modified dilution factor, DF , must be determined so that m
available dilution flows may be apportioned among simultaneous discharge pathways. The modified dilution factor is defined as:
DF = DF (6) m 7-A where F A is an administrative allocation factor which may be assigned any value between 0 and 1 under the condition that CLINTON-I 2-7 Rev.2-10/86
CPS-0DCM i l
l (FA )n d 1 (7) and where n = the number of. liquid discharge pathways for which DF >l and which are planned for simultaneous release.
For simplicity, F A may be assigned the value 1/n. Calculate j F in equation (4) by substituting the value of DF m f r DF tank and perform the calculation specified in section 2.3.1.4 to i determine flow rate and PRM setpoints.
I 2.3.3 Shutdown Service Water (SX) Effluent PRM Setooints )
i Shutdown Service Water, when initiated, is a potential !
continuous radioactive discharge pathway to the Ultimate Heat i Sink (UHS) (see Figure 2.5-2). The SX effluent is not I considered a radioactive discharge pathway unless any SX cooling load heat exchanger has been detected as failed. SX effluent sampling, analysis and setpoint establishment will be performed as discussed for the Plant Service Water system l in section 2.3.2. j i
2.3.4 Fuel Pool Heat Exchanger Service Water Effluent PRM Setpoints The Fuel Pool Heat Exchanger Service Water is normally j supplied by the Component Cooling Water (CC) system (a closed I loop system). The CC system rej ects heat loads to the Plant 1 Service Water system where intersystem leakage would be detected as described in section 2.3.2. The Fuel Pool Heat i Exchanger Service Water effluent is considered a potential radioactive discharge pathway when SX replaces CC as the heat sink for.the fuel pool heat exchangers. To account for a potential batch release of CC radioactivity to the Ultimate ;
Heat Sink via SX, CC will be sampled and analyzed as discussed in section 2.3.2. The analysis results will then be used to establish Fuel Pool Heat Exchanger Service Water PRM and flow rate setpoints following section 2.3.2.1 and 2.3.2.2 methodology.
l Any releases of radioactivity to the environment from the Plant Service Water (except during liquid radwaste discharges), Shutdown Service Water or Fuel Pool Heat i Exchanger Service Water Systems are considered abnormal events. Such events will be accounted for as unplanned releases in the SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.
1 CLINTON-I 2-8 Rev.2-10/86
CPS-ODCM 2.4 10CFR50, Appendix I Release Rate Limits CPS RETS 3.11.1.2 requires that the cumulative dose contributions to an individual from radioactive material in liquid effluents released to the unrestricted area be determined at least once per 31 days. The applicable dose limits are:
31.5 mrem / calendar quarter - TOTAL BODY 35.0 mrem / calendar quarter - ANY ORGAN l
33 mrem / calendar year - TOTAL BODY j10 mrem / calendar year - ANY ORGAN The dose contribution to the maximum exposed individual from all radionuclides identified in liquid effluents released to the unrestricted area is calculated as follows:
m D) =
A ig 1, 6 ty C F f1 7 mrem (8).
where D = The cumulative calendar quarter or yearly dose to
- d any organ j from liquid effluent for the total release period, mrem q at y = The length of the lth release time period over which i
C 11 and F 1 are averaged for liquid releases, hours l
l = Liquid Radwaste Tank Volume / Liquid Radwaste l Discharge Flow Rate l C,7 = The average concentration of nuclide i in undiluted j liquid effluent durin release period at for any t
liquid release, uCi/m j l
F = The near field average dilution factor for C 1
duringanyliquidettluentrelease,dimensiobbess.
Defined as the ratio of the average undiluted liquid radwaste flow during the release to the product of the average flow from the discharge structure to unrestricted receiving water and Z
= Average Undiluted Liauid Waste Flow (9)
(Average Discharge Structure Flow) Z
! Z = The applicable dilution factor for Lake Clinton, dimensionless
= 1.0 CLINTON-1 2-9 Rev.2-10/86
CPS-0DCM TABLE 2.4-1 ADULT INGESTION DOSE C01011TMENT FACTORS - A ij.
(mrem /hr per UCi/ml)
ISOTOPE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 C-14 3.12E+04* 6.24E+03 6.24E+03 6.24E+03 6.24E+03 6.24E+03 6.24E+03 NA-24 4.06E+02 4.06E+02 4.06E+02 4.06E+02 4.06E+02 4.06E+02 4.06E+02 P-32 4.61E+07 2.87E+06 1.78E+06 NO DATA NO DATA NO DATA 5.19E+06 CR-51 NO DATA NO DATA 1.27E+00 7.60E-01 2.80E-01 1.68E+00 3.20E+02 MN-54 NO DATA 4.37E+03 8.34E+02 NO DATA 1.30E+03 NO DATA 1.34E+04 MN-56 NO DATA 1.10E+02 1.95E+01 NO DATA 1.40E+02 NO DATA 3.51E+03 FE-55 6.57E+02 4.54E+02 1.06E+02 NO DATA NO DATA 2.53E+02 2.60E+02 FE-59 1.04E+03 2.44E+03 9.34E+02 NO DATA NO DATA 6.81E+02 8.13E+03 i
Co-58 NO DATA 8.90E+01 2.00E+02 NO DATA NO DATA NO DATA 1.80E+03 Co-60 NO DATA 2.56E+02 5.64E+02 NO DATA NO DATA NO DATA 4.80E+03 NI-63 3.11E+04 2.15E+03 1.04E+03 NO DATA NO DATA NO DATA 4.49E+02 NI-65 1.26E+02 1.64E+01 7.48E+00 NO DATA NO DATA NO DATA 4.16E+02 CU-64 NO DATA 9.97E+00 4.6TE+00 NO DATA 2.51E+01 NO DATA 8.48E+02 ZN-65 2.31E+04 7.36E+04 3.33E+04 NO DATA 4.92E+04 NO DATA 4.64E+04 ZN-69 4.92E+01 9.42E+01 6.55E&00 NO DATA 6.12E+01 NO DATA 1.41E+01 BR-83 NO DATA NO DATA 4.03E+01 NO DATA NO DATA NO DATA 5.81E+01 BR-84 NO DATA NO DATA 5.23E+01 NO DATA NO DATA NO DATA 4.10E-04 BR-85 NO DATA NO DATA 2.15E+00 NO DATA NO DATA NO DATA LT E-15**
RB-86 NO DATA 1.01E+05 4.70E+04 NO DATA NO DATA NO DATA 1.99E+04 RB-88 NO DATA 2.89E+02 1.53E+02 NO DATA NO DATA NO DATA 4.00E-09 RB-89 NO DATA 1.92E+02 1.35E+02 NO DATA NO DATA NO DATA 1.11E-11 SR-89 2.21E+04 NO DATA 6.34E+02 NO DATA NO DATA NO DATA 3.54E+03 SR-90 5.43E+05 NO DATA 1.33E+05 NO DATA NO DATA NO DATA 1.57E+04 SR-91 4.06E+02 NO DATA 1.64E+01 NO DATA NO DATA NO DATA 1.99E+03 SR-92 1.54E+02 NO DATA 6.67E+00 NO DATA NO DATA NO DATA 3.05E+03 Y-90 5.75E-01 NO DATA 1.54E-02 NO DATA NO DATA NO DATA 6.10E+03 CLINTON-I 2-11 Rev.2-10/86
~
4 ._._.&. _. .... .._ _ , .._ .__ . 1 CPS-0DCM TABLE 2.4-1 (continued) )
i ADULT INGESTION DOSE COMMITMENT FACTORS - A gj j 1
(mrem /hr per pCi/ml) j ISOTOPE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l l
Y-91m 5.43E-03 NO DATA 2.10E-04 NO DATA NO DATA NO DATA 1.60E-02 l Y-91 8.42E+00 NO DATA 2.25E-01 NO DATA NO DATA NO DATA 4.64E+03 !
Y-92 5.05E-02 NO DATA 1.48E-03 NO DATA NO DATA NO DATA 8.84E+02 l l
Y-93 1.60E-01 NO DATA 4.42E-03 NO DATA NO DATA NO DATA 5.08E+03 ZR-95 2.40E-01 7.69E-02 5.20E-02 NO DATA 1.21E-01 NO DATA ,2.44E+02 ZR-97 1.32E-02 2.67E-03 1.22E-03 NO DATA 4.04E-03 NO DATA 8.28E+02 NB-95 4.46E+02 2.48E+02 1.33E+02 NO DATA 2.45E+02 NO DATA 1.51E+06 M0-99 NO DATA 1.03E+02 1.96E+01 NO DATA 2.33E+02 NO DATA 2.39E+02 TC-99m 8.86E-03 2.50E-02 3.19E-01 NO DATA 3.80E-01 1.23E-02 1.48E+01 l l k TC-101 9.11E-03 1.31E-02 1.29E-01 NO DATA 2.36E-01 6. 70E-03 3.94E-14 RU-103 4.42E+00 NO DATA 1.90E+00 NO DATA 1.69E+01 NO DATA 5.16E+02 ]
{
l RU-105 3.68E-01 NO DATA 1.45E-01 NO DATA 4.76E+00 NO DATA 2.25E+02 j l i RU-106 6.57E+01 NO DATA 8.32E+00 NO DATA 1.27E+02 NO DATA 4.25E+03 AG-110m NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA l TE-125m 2.57E+03 9.28E+02 3.43E+02 7.70E+02 1.04E+04 NO DATA 1.22E+04 TE-127m 6.47E+03 2.31E+03 7.89E+02 1.65E+03 2.63E+04 NO DATA 2.17E+04 i
TE-127 1.05E+02 3.77E+01 2.28E+01 7.79E+01 4.28E+02 NO DATA 8.30E+03 1 l TE-129m 1.10E+04 4.10E+03 1.74E+03 3.78E+03 4.59E+04 NO DATA 5.54E+04 l TE-129 3.00E+01 1.13E+01 7.31E+00 2.30E+01 1.26E+02 NO DATA 2.26E+01 TE-131m 1.65E+03 8.09E+02 6.74E+02 1.28E+03 8.19E+03 NO DATA 8.03E+04 TE-131 1.88E+01 7.87E+00 5.95E+00 1.55E+01 8.25E+01 NO DATA 2.67E+00 l l TE-132 2.41E+03 1.56E+03 1.46E+03 1.72E+03 1.50E+04 NO DATA 7.37E+04 I-130 2.71E+01 7.99E+01 3.15E+01 6.7bE+03 1.25E+02 NO DATA 6.88E+01 I-131 1.49E+02 2.13E+02 1.22E+02 6.99E+04 3.66E+02 NO DATA 5.63E+01 ,
1 l I-132 7.28E+00 1.95E+01 6.81E+00 6.81E+02 3.10E+01 NO DATA 3.66E+00 I-133 5.09E+01 8.85E+01 2.70E+01 1.30E+04 1.54E+02 NO DATA 7.96E+01 I-134 3.80E+00 1.03E+01 3.69E+00 1.79E+02 1.64E+01 NO DATA 9.00E-03 l
l CLINTON-I 2-12 Rev.2-10/86 l
CPS-0DCM TABLE 2.4-1 (continued)
ADULT INGESTION DOSE COMMITMENT FACTORS - A g3 (mrem /hr per pCi/ml)
ISOTOPE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI I-135 1.59E+01 4.16E+01 1.53E+01 2.74E+03 6.67E+01 NO DATA 4.70E+01 CS-134 2.97E+05 7.07E+05 5.78E+05 NO DATA 2.29E+05 7.60E+04 1.24E+04 CS-136 3.11E+04 1.23E+05 8.84E+04 NO DATA 6.84E+04 9.37E+03 1.40E+04 CS-137 3.81E+05 5.21E+05 3.41E+05 NO DATA 1.77E+05 5.88E+04 1.01E+04 CS-138 2.64E+02 5.21E+02 2.58E+02 NO DATA 3.83E+02 3.78E+01 2.22E-03 BA-139 9.27E+01 6.60E-04 2.72E-02 NO DATA 6.18E-04 1.40E-01 4.00E+02 BA-140 1.94E+02 2.44E-01 1.27E+01 NO DATA 8.29E-02 1.40E-01 4.00E+02 BA-141 4.50E-01 3.40E-04 1.52E-02 NO DATA 3.16E-04 1.93E-04 2.12E-10 BA-142 2.04E-01 2.09E-04 1.28E-02 NO DATA 1.77E-04 1.18E-04 2.89E-19 LA-140 1.49E-01 7.53E-02 1.99E-02 NO DATA NO DATA NO DATA 5.53E+03 LA-142 7.65E-03 3.48E-03 8.66E-04 NO DATA NO DATA NO DATA 2.54E+01 CE-141 2.24E-02 1.51E-02 1.72E-03 NO DATA 7.03E-03 NO DATA 5.78E+01 CE-143 3.94E-03 2.92E+00 3.23E-04 NO DATA 1.28E-03 NO DATA 1.09E+02 CE-144 1.17E+00 4.88E-01 6.26E-02 NO DATA 2.89E-01 NO DATA 3.94E+02 PR-143 5.50E-01 2.20E-01 2.72E-02 NO DATA 1.27E-01 NO DATA 2.41E+03 PR-144 1.80E-03 7.47E-04 9.14E-05 NO DATA 4.21E-04 NO DATA 2.59E-10 ND-147 3.76E-01 4.34E-01 2.60E-02 NO DATA 2.54E-01 NO DATA 2.08E+03 W-187 2.95E+02 2.47E+02 8.63E+01 NO DATA NO DATA NO DATA 8.09E+04 FT-239 2.84E-02 2.80E-03 1.54E-03 NO DATA 8.72E-03 NO DATA 5.74E+02
- 0 3.12 x 10
- Less than 10-15 CLINTON-I 2-13 Rev.2-10/86
CPS-0DCM FIGURE 2.5-1 LIQUID RADWASTE TREATMENT SYSTEM X i
~" a ,
n ; ~ai-I, O l - ows ott4 l
i ows o* "
][f>p es
] owu2r4
& ewsom
! r -t>< ,
p:><- cou. c?f
[
a oweeies -
wro+1 swroo swrets L X: ,, x '
=cozrc **E0m +
owm3 owa oir owr oe p bg H s 5sw
-mg 3
- 1. w
- 72 a, " -
gx gi CcHecf;en 3** '
5,yste m
, gg -
g s gg oaa.5, .C.n AN Fium e Nokr S
- Monitors required by CPS TECHNICAL SPECIFICATIONS 1WF01S Floor Drain 0WZ01P Chem. Wst. 2WF04T Floor Drain 0WE02TA,B, and C Waste Evaporator Evap. Tank Pump Evaporator Tank Samp. Tk Pumps 2WF0lS Ficor Drain 0WE01FA,B, and C OWZOIT Chem. Waste OWE 01TA and B Excess Evaporator Waste Filters Evaporator Tank Water Tanks 0WZ0!S Chemical OWE 01DA,B, and C IWF04P Fir. Drn. 0WE01PA and B Excess Waste Evaporator Waste Demins Evap. Tank Pump Water Tank Pumps 1WF04T Floor Drain 0WE02TA,B, and C 2WF04P Fir. Drn. 1PR036 Service Evaporator Tank Waste Sample Tks. Evap. Tank Pump Water PRM 1FR040 Liquid kW Discharge PRM CLINTON-I 2-18 Rev.2-10/86
CPS-ODCM FIGURE 2.5-2 SHUTDOWN AND FUEL POOL HEAT EXCHANGER SERVICE WATER EFFLUENT MONITORS
"*a ! .- ;,,
gt
. 1A12 72004 WATER L Mb b
)[
m,, ,,m,, H05";u'a "" "'"
L l22 ""I- -
- ^=
LDAD$
C LJ NG C00
. WATER , hATEL f"~1 .
L.J UAN uttturs . mg, ,oog -
3
$NUTDOWl8 fggggg q, COOLING MEAT EACWGER "S*
<r db WATER SERvtCE
"' "' ,idATER 4 SHtfrDOWII db U"E'#^."j"
'"4"f"" MM p,g,g,N,Nlc.
- or oCom .- -
i NORMAL COOLING SUPPLY - COMPONENT COOLING WATER EMERGENCY COOLING SUPPLY - SHUTDOWN SERVICE WATER
- Monitors required by CPS TECHNICAL SPECIFICATIONS 1PR038 Shutdown Service 1PR005 Fuel Pool heat Water Effluent "A" Exchanger Service Water PRM 1PR039 Shutdown Service 1PR004 Fuel Pool Hea t Water Effluent "B" Exchanger Service Wa ter PRM CLINTON-I 2-19 Rev. 2-10/86
CPS-0DCM
~
2.5 Compliance With CPS RETS 3.11.1.3/3.11.1.4 The projected doses due to releases of liquid radwaste effluents will be calculated using equation (8). If the' sum l-of the accumulated dose to date for the month and the projected dose for the remainder of the month exceeds CPS RETS 3.11.1.3 limits, then the liquid radwaste treatment system shall be used. This is to ensure compliance with the OPERABILITY requirement of CPS RETS 3.11.1.3; Figure 2.5-1 shows the appropriate portions of the liquid radwaste treatment system which will be used.
The use of temporary liquid radwaste hold-up tanks may occur at CPS.
To comply with CPS RETS 3.11.1.4, the amount of liquid radwaste stored in such tanks shall be limited to 10 curies, excluding tritium and dissolved or entrained noble gases. In lieu of the 10 curie limit, the methodology presented in Appendix B of NUREG-0133 (BWR-RATAFR code) will be used to establish the curie limit.
2.6 Doses From Other Significant Liquid Effluent Pathways Section 2.4 of the CPS-ODCM describes demonstrating compliance with CPS RETS 3.11.1.2 based upon the aquatic food and potable water exposure pathways only. Other exposure pathways, namely shoreline deposits and irrigated foods, may arise at Clinton Power Station and will be included in the section 2.4 dose contribution if they are likely to provide a significant contribution to the total dose. A pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all other existing pathways. Methods for calculating doses from other potentially significant liquid effluent pathways are presented in Appendix A to Regulatory Guide 1.109.
When it is determined that other liquid effluent pathways do exist, the Regulatory Guide 1.109 Appendix A equations and parameters will be used in lieu of site-specific data to determine a pathway's significance.
CLINTON-I 2-20 Rev.2-10/86
- - ;- . . . , . , . - -. : , . . o. - ~ _ ,
CPS-0DCM TABLE 2.6-1 i
Input Parameters for Calculating Rapj , (
- {,
k) 1 DELETED s J
J l ;
1 l
l
)
3 l
- i. f I
1 i
' l i
i l
l CLINTON-I 2 .2 1 Rev.2-10/86
CPS-ODCM TABLE 2.6-1 '
Input Parameters for Calculating R apj
[ .
l DELETED sa s
's I
A CLINTON-I 2-22 Rev.2-10/86
__ :.u;_ . n CPS-0DCM' l
l 3.0 GASEOUS EFFLUENTS 3.1 Introduction Gaseous effluents from CPS are released on both a batch and continuous basis. Gaseous effluents are '
normally discharged on a long tenn basis. High volume Continuous Containment Purge and mechanical vacuum pump discharge may be considered short term releases. l There are two gaseous effluent release points to the environment: the Common Station HVAC Stack and the Standby Gas Treatment System (SGTS) Stack. The height of these stacks is such that all gaseous effluents are treated as mixed-mode releases (rererence Table 7.2-4). The SGTS is an Engineered Safety Feature filter system utilized following an accident to reduce iodine and particulate activity in gases leaking from the primary containment and which are potentially present in the secondary containment. The Common Station HVAC Stack ("HVAC Stack") receives process and ventilation exhaust from the following inputs:
i 1)
Continuous Containment Purge (CCP)
, 2) Containment Building Ventilation
- 3) Turbine Building Ventilation ,
- 4) Radwaste Building Ventilation j
- 5) Auxiliary Building Ventilation I
- 6) Fuel Building Ventilation
- 7) Auxiliary Building Refrigerant Purge
- 8) Laboratory Ventilation System
- 9) Counting / Equipment Decon Rooms l Ventilation
- 10) Steam Packing Exhauster
- 11) Mechanical Vacuum Pump
- 12) Drywell Purge The effluent exiting the SGTS stack is monitored at the SGTS stack and the combined inputs to the HVAC stack are monitored at the HVAC stack. All inputs to the HVAC Stack, with the exception of input numbers 7 through 10, can be monitored prior to entering the stack.
Figure 3.1-1 delineates the CPS site boundary for implementation of the gaseous effluent CPS RETS.
CLINTON-I 3i Rev.2-10/86
l CPS-0DCM 1
- 2) Gamma scintillator for iodine
- 3) Iodine background subtraction i 1
- 4) beta scintillator for low range noble j gas l i
- 5) Energy-compensated G-M detector for i intermediate range noble gas 1
- 6) Energy-compensated G-M detector for i gamma area subtraction This monitor has no control function but annunciated in the Main Control Room and !
the Radiation Protection Office where proper response actions will be initiated in accordance with CPS procedures.
3,3 Main Condenser Off-Gas Monitoring System 3.3.1 Pre-Treatment Air Ejector Off-Gas Process Radiation Monitor (PRM) f The Pre-Treatment Off-Gas PRM monitors j hydrogen recombiner effluent ror gross noble gas radioactivity. This effluent is then ,
routed to the charcoal adsorbers for eventual j release to the environment via the station HVAC Stack (see Figure 3.3-1). The PRM l]'
detector configuration consists of a single energy-compensated G-M detector mounted in a gas volume. l The monitor has no control function but I annunciated in the Main Control Room and the !
Radiation Protection Office where proper response actions will be initiated in ,
accordance with CPS procedures. '
CLINTON-I 3-3 Rev.2-10/86
m--- r .---
_2 . _ . .
CPS-OLCM 3.3.2 Post-Treatment Air Ejector Off-Gas Process Radiation Monitor (PRM)
The Post-Treatment Off-Gas PRM monitors the gaseous radioactivity at upstream, intermediate or downstream sections of the charcoal adsorber beds prior to the effluent entering the station HVAC Stack for release to the environment (see Figure 3.3-1). The PRM l detector configuration is as described for the HVAC-Stack PRM (section 3.2.1).
The monitor has two control functions.
l Upon detection of noble gas activity in l
excess of the ALERT setpoint, the charcoal adsorber bypass valves shut (if in the charcoal bypass mode) and the off-gas is routed through the adsorbers.
Should noble gas activity exceed the HIGH setpoint, or upon PRM failure, the off-gas system is automatically isolated from the HVAC Stack and a reactor scram may occur if loss of condenser vacuum occurs.
The Main Condenser Off-Gas Treatment System is shown in Figure 3.3-1.
3.4 10CFR20 Release Rate Limits Limits for release of airborne effluents to the unrestricted area are stated in CPS RETS 3.11.2.1.
The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
(a) Noble Gases - <-
500 mrem / year to the total body and 1 3000 mrem / year to the skin (b) Radiciodines, Particulate and Tritium - 11500 mrem / year to any organ
.e CLINTON-I 3-4 Rev.2-10/86
, ,. . . . ~. . w .. - .. a - .. - ~ u. .+ w .--. w.n. : . . a. . . .. . - -
CPS-0DCM j i
3.4.1 Dose Rate Due To Noble Gases j i
In order.to comply with CPS RETS 3.11.2.1(a),
the dose rate at or beyond the site boundary due to noble gases shall be calculated as l follows: l D
e =l tt K ((%7Q),Q im 3 (1)
= total body dose rate at time of release, mrem / year D
s"k(b+1.1M)[(%7Q)miml i t O (2)
= skin dose rate at time of 1 release, mrem / year The terms in the above equations are defined in section 3.4.2.
Dose' Rate Due To Radiciodines, Particulate i 3.4.2 and Tritium In order to comply with CPS RETS 3.11.2.1(b), organ dose rates due to radiciodines (I-131, I-133), particulate with half-lives > 8 days and tritium shall l be calculated as follows:
Dg =kjt3(%fQ)m1m P 9 (3)l
= organ dose rate at time of release, mrem /yr The terms used in equations (1) through (3) are defined as follows:
K g= The total body dose factor due to gamma emissions for each identified noble gas radionuclides i, mrem /yr per pCi/m3 L.=
1 The skin dose factor due to beta emissions for each identified noble gas radionuclides 1, mrem /yr per pC1/m3 Mt= The air dose factor due to gamma emissions for each identified noble gas radionuclides 1, mrem /yr per pCi/m3 (1.1 mrem / mrad converts air dose to skin dose)
CLINTON-I 3-5 Rev.2-10/86 i
.- ,. , a .- . . . , .. au.a _
.. :. 1 . -- - , u a yc.=;.: m..
CPS-0DCM P
f3 = The dose factor.for non-noble gas radionuclides i and organ j which includes. pathway transport parameters, receptor usage factors and the dosimetry of the exposure. The dose factors for the inhalation, mrem /yr per uCi/m3, pathway are listed in Table 3.4-2 (CHILD). Dose factors are based on NUREG-0133, Section 5.2.1.1 assumptions unless otherwise stated.
Q*=t The release rate of noble gas radionuclides i in gaseous effluent from mixed-mode release points, UCi/sec Q*=f The release rate of non-noble gas radionuclides i in gaseous effluent from mixed-mode release points, uCi/sec
(%7Q)m = The highest calculated annual average relative concentration for any area at or beyond the site boundary from mixed-mode releases, sec/m3 D is calculated for each of six organs and the total body; the mRximum D g value is then used to determine compliance with CPS RETS 3.11.2.1(b).
CLINTON-I 3-6 Rev.2-10/86
' l CPS-0DCM '
TABLE 3.4-2 INHALATION PATHWAY DOSE RATE FACTORS (CHILD) - P..
(mrem /yr per pCi/m3) M ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 1.12E+03* 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 NA-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 P-32 2.60E+06 1.14E+05 9.88E+04 NO DATA NO DATA NO DATA 4.22E+04 CR-51 NO DATA NO DATA 1.54E+02 8.55E+01 2.43+01 1.70E+04 1.08E+03 MN-54 NO DATA 4.29E-04 9.51E+03 NO DATA 1.00E+04 1.58E+06 2.29E+04 MN-56 NO DATA 1.66E+00 3.12E-01 NO DATA 1.67E+00 1.31E+04 1.23E+05 FE-55 4.74E+04 2.52E+04 7.77E+03 NO DATA NO DATA 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 NO DATA NO DATA 1.27E+06 7.07E+04
]
1 C0-58 NO DATA 1.77E+03 3.16E+03 NO DATA NO DATA 1.11E+06 3.44E+04 I
C0-60 NO DATA 1.31E+04 2.26E+04 NO DATA NO DATA 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 NO DATA NO DATA 2.75E+05 6.33E+03 {
1 NI-65 2.99E+00 2.96E-01 1.64E-01 NO DATA NO DATA 8.18E+03 8.40E+04 CU-64 NO DATA 1.99E+00 1.07E+00 NO DATA 6.03E+00 9.58E+05 3.67E+04 ZN-65 4.26E+04 1.13E+05 7.03E+04 NO DATA 7.14E+04 9.95E+05 1.63E+04 ZN-69 6.70E-02 9.66E-02 8.92E-03 NO DATA 5.85E-02 1.42E+03 1.02E+04 BR-83 NO DATA NO DATA 4.74E+02 NO DATA NO DATA NO DATA LT 3.70E-15** !
BR-84 NO DATA NO DATA 5.48E+02 NO DATA NO DATA NO DATA LT 3.70E-15 BR-85 NO DATA NO DATA 2.40E+01 NO DATA NO DATA NO DATA LT 3.70E-15 RB-86 NO DATA 1.98E+05 1.14E+05 NO DATA NO DATA NO DATA 7.99E+03 RB-88 NO DATA 5.62E+02 3.66E+02 NO DATA NO DATA NO DATA 1.72E+01 RB-89 NO DATA 3.45E+02 2.90E+02 NO DATA NO DATA NO DATA 1.89E+00 SR-89 5.99Et05 NO DATA 1.72E+04 NO DATA NO DATA 2.16E+06 1.67E+05 SR-90 1.01E+08 NO DATA 6.49E+06 NO DATA NO DATA 1.48E+07 3.43E+05 SR-91 1,21E+02 NO DATA 4.59E+00 NO DATA NO DATA 5.33E+04 1.74E+05 SR-92 1.31E+01 NO DATA 5.25E-01 NO DATA NO DATA 2.40Ev04 2.42itub Y-90 4.11E+03 NO DATA 1.11E+02 NO DATA NO DATA 2.62E+05 2.68E+05 CLINTON-I 3-9 Rev.2-10/86
___ -. ,, 3, , , , , ._ _ , , , , , ,_
CPS-0DCM TABLE 3.4-2 (cont'd) l INHALATION PATHWAY DOSE PATE FACTORS (CHILD) -P (mrem /yr per uCi/m3) U ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE I Y-91m 507E-01 NO DATA 1.84E-02 NO DATA NO DATA 2.81E+03 1.72+03 Y-91 9.14E+05 NO DATA 2.44E+04 NO DATA NO DATA 2.63+06 1.84E+05 )
Y-92 2.04E+01 NO DATA 5.81E-01 NO DATA NO DATA 2.39E+04 2.39E+05 l
)
Y-93 1.87E+02 NO DATA 5.11E+00 NO DATA NO DATA 7.44E+04 3.89E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 NO DATA 5.96E+04 2.23E+06 6.11E+04 .
ZR-97 1.88E+02 2.72E+01 1.60E+01 NO DATA 3.89E+01 1.13E+05 3.51E+05 i NB-95 2.35E+04 9.18E+03 6.55E+03 NO DATA 8.62E+03 6.14E+05 3.70E+04 MO-99 NO DATA 1.72E+02 4.26E+01 NO DATA 3.92E+02 1.35E+05 1.27E+05 TC-99m 1.78E-03 3.48E-03 5.77E-02 NO DATA 5.07E-02 9.51E+02 4.81E+03 TC-101 8.10E-05 8.51E-05 1.08E-03 NO DATA 1.45E-03 5.82E+02 1.63E+01 RU-103 2.79E+03 NO DATA 1.07E+03 NO DATA 7.03E+03 6.62E+05 4.48E+04 RU - 105 1.5 E+00 NO DATA 5.55E-01 NO DATA 1.34E+0D 1.59E+04 9.95E+04 RU-106- 1.36E+05 NO DATA 1.69E+04 NO DATA' 1.84E+05- 1.43E+07 4.29E+05 AG-110m 1.69E+04 1.14E+04 9.14E+03 NO DATA 2.12E+04 5.48E+06 1.00E+05 TE-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 NO DATA 4.77E+05 3.38E+04 TE-127m 2.49E+04 8.56E+03 3.03E+03 6.07E+03 6.36E+04 1. 4 8~E+06 7.14E+04 TE-127 2.77E+00 9.51E-01 6.11E-01 1.96E+00 7.07E+00 1.00E+04 5.62E+04 TE-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 TE-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.53E+03 2.55E+04 TE-131m 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 TE-131 2.17E-02 8.44E-03 6.59E-03 1.70E-03 5.88E-02 2.05E+03 1.33E+03 TE-132 4.81E+02 2.72E+02 2.63E+02 3.18E+02 1.77E+03 3.77E+05 1.38E+05 I-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 NO DATA 5.11E+03 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 NO DATA 2.84E+03 I-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 NO DATA 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 NO DATA 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 NO DATA 9.55E+02 CLINTON-1 3-10 Rev.2-10/86 w _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. . . ., . . . ..u. . . , .
.a.. .~_ wm CPS-0DCM TABLE 3.4-2 (cont'd)
INHALATION PATHWAY DOSE RATE FACTORS (CHILD) -
P (mrem /yr per pCi/m3 ) U ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 NO DATA 4.44E+03 CS-134 6.51E+05 1.01E+06 2.25E+05 NO DATA 3.30E+05 1.21E+05 3.84E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 NO DATA 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 NO DATA 2.82E+05 1.04E+05 3.62E+03 CS-138 6.33E+02 8.40E+02 5.55E+02 NO DATA 6.21E+02 6.81E+01 2.70E+02 BA-139 1.84E+00 9.84E-04 5.37E-02 NO DATA 8.62E-04 5.77E+03 5.77E+04 BA-140 7.40E+0/ 6.48E+01 4.33E+03 NO DATA 2.11E+01 1.74E+06 1.02E+05 BA-141 1.96E-L_ 1.09E-04 6.36E-03 NO DATA 9.47E-05 2.92E+03 2.75E+02 BA-142 5.00E-02 3.60E-05 2.79E-03 NO DATA 2.91E-05 1.64E+03 2.74E+00 LA-140 6.44E+02 2.25E+02 7.55E+01 NO DATA NO DATA 1.83E+05 2.26E+05
'LA-142 1.'30E+00 4.11E-01 1.29E-01 NO DATA NO DATA 8.70E+03 7.59E+04 CE-141 3.92E+04 1.95E+04 2.90E+03 NO DATA 8.55E+03 5.44E+05 5.66E+04 CE-143 3.66E+02 1.99E+02 2.88E+01 NO DATA 8.36E+01 1.15E+05 1.27E+05 CE-144 6.77E+06 2.12E+06 3.62E+05 NO DATA 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 NO DATA 3.00E+03 4.33E+05 9.73E+04 PR-144 5.96E-02 1.85E-02 3.00E-03 NO DATA 9.77E-03 1.57E+03 1.97E+02 ND-147 1.08E+04 8.73E+03 6.81E+02 NO DATA 4.81E+03 3.28E+05 8.21E+04 W-187 1.63E+01 9.66E+00 4.33E+00 NO DATA NO DATA 4.11E+04 9.10E+04 NP-239 4.66E+02 3.35E+01 2.35E+01 NO DATA 9.73E+01 5.81E+04 6.40E+04
- 1.12 x 103
- Less than 3.70 x 10
-15 CLINTON-I 3-11 Rev.2-10/86
, - - - w. .a... . - - . - +
CPS-00CM TABLE 3.4-3 ANNUAL DOSES IN UNRESTRICTED AREAS Total Body Skin Organ Distance Occupancy Dose Rate Dose Rate Dose Rate
- Location (mile / meter) Sector ihrs/yr) (mrem /yr) (mrem /yr) (mrem /yr)
I Road 0.3/495 SE 243(1) 0.04 0.08 0.02 {
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 l I
Department of l Conservation 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 l 1
i i l l
l t
(1) Assumes travel on road for forty minutes per d<ay.
(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. ;
1 (4) Assumes continuous occupation on Clinton Lake for the months of June, July, and August.
(5) Assumes continuous occup"ation on Department of Conservation camping areas for the months of June, July, and August.
- Child inh 91ation CLINTON-I 3-12 Rev.2-10/86
--..=a.- = . . ax= .a=c --
w - :n- -. ..
CPS-0DCM
)
R 3.5 10CFR50, APPENDIX I RELEASE RATE LIMITS The requirements pertaining to 10CFR50 gaseous release i rate limits are stated in CPS RETS 3.11.2.2 and 3.11.2.3. CPS RETS 3.11.2.2 requires that the air fi dose at or beyond the site boundary, due to noble I gases, shall be limited to the following: q l
(a) During any calendar quarter, <5 mrad l (gamma) and < 10 mrad (beta) arid , )
(b) During any calendar year,jl0 mrad (gamma) and j20 mrad (beta).
CPS RETS 3.11.2.3 requires that the dose to an individual at or beyond the site boundary, due to radiciodines (I-131, I-133), tritium and all particulate with half-lives >8 days, shall be 3
, . limited to the following: j (a) .During any calendar quarter, j7.5 mrem to-any organ and, l (b) During any calendar year, 115 mrem to any )
organ. !
3.5.1 Noble Gas Air Dose The air dose at or beyond the site !
. boundary-due to noble gases released in gaseous effluent will be determined using the following equations.
3.5.1.1 During any .clendar quarter or calendar year, for gamma radiation:
Dy = 3.17 x 10-8 (M g[(X/Q)m 91m +
(4)
(x/q),qim3 l 3.5.1.2 During any calendar quarter or calendar year, for beta radiation:
Dg = 3.17 x 10-8{g Ng [ W Q)mSim +
(x/q)m 91m) (5)
Vihere M =
The gamma air dose factor for 1
each identified noble gas radionuclides i, mrad / year per pCi/m3 (M v Table 3.4 11.
)alues are listed in CLINTON-I 3-13 Rev.2-10/86
. .; , . -, . .. -- . : -. RE_ _2 T- T R. ; _ T CPS-ODCM Ng =
The beta air dose factor for each-identified noble gas radionuclides i, mrad / year.per pC4/m3 (N g ;
values'are listed in Table 3.4-1).
(X7Q)* = The highest calculated annual average relative concentration from mixed-mode relcase points for areas at or beyond the site boundary for long-term (> 500 hrs /yr) releases.
(x/q)* = The relative concentration from mixed-mode release points for areas at or beyond the site boundary for short-term (< 500 ;
hrs /yr not to exceed 150 hrs /qtr) releases.
Q.1* = The average release of noble gas radionuclides i for long-term releases from mixed-mode release points, PCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
qim = The average release of noble gas radionuclides i for short-term releases from mixed-mode release points, pCi. Releases shall be ;
cumulative over the calendar quarter or year, as appropriate.
3.17 x 10-8 =
The inverse of the number of seconds in a year.
t l
CLINTON-I 3-14 Rev.2-10/86
, ,, , , L' , *
. *&*v I. . l dTi. f:L5.Xl . _ L s ~-
CPS-0DCM q15
=
The releases of radionuclides i (I-131, I-133, tritium and particulate) for short-term (5500 hrs /yr not :o exceed 150 hrs /qtr) releases from mixed-mode release points, Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.
(U7Q)m = The relative deposition from mixed-mode release points for areas at or beyond the site boundary for long-term
(> 500 hrs /yr) releases, m-2 .
(d/q)m = The relative deposition from m1xed-mode release points for areas at or beyond the site boundary for short-term (j500 ers/yr not to eyceed 150 hrs /qtr) releases, m W* = The dispersion parameter for
- estimating the dose to an individual at a controlling location for long-term mixed-mode releases.
=
(274) , sec/m3, for the inha19 tion pathway
=
(U7Q)m, m , f r the food and ground plane pathways w
=
The dispersion parameter for estimating the dose to an individual at a controlling location for short-term mixed-mode releases.
= (x/q) sec/m3, for the inhalEtion pathway
=
(d/q)m, m f r the food and ground plane pathways CLINTON-I 3-16 Rev.2-10/86
^
CPS-0DCM 3.6 Compliance With CPS-RETS 3.11.2.4/3.11.2.5 CPS RETS 3.11.2.4 recuires that.the Offgas Treatment l System shall not be used in the charcoal bypass mode j unless the Post-Treatment Air Ejector Offgas radiation monitor is operable per CPS RETS 3.3.7.12. Prior to 31 acing the offgas Treatment System in the charcoal aypass mode, the alarm setpoints for the Station HVAC Exhaust and the Post-Treatment Offgas radiation monitors shall be calculated to account for the increased fractions of short-lived noble gases. The noble gas release fractions shall be based either on actual measured values or on design basis noble gas concentration fractions (30 minute decay) in the primary coolant offgas.
CPS RETS 3.11.2.5 requires that the Ventilation Exhaust Treatment. System (VETS) shall be used when.the projected doses due to VETS releases to areas at and beyond the Site Boundary would exceed 0.3 mrem to any' organ in a 31 day period. The projected doses resulting from such releases will be calculated using l ODCM section 3.5.2 methodology. If the dose impact resulting from the projected 31 day release exceeds 0.3 mrem and the VETS is capable of reducing the projected impact to less than 0.3 mrem, the VETS shall be used.
3.7 Effluent Monitor Setpoint Calculation _s i l
Gaseous effluent Process Radiation Monitor (PRM) alarm i setpoints shall be calculated to ensure that the dose
, rate in unrestricted areas due to noble gases released
)
4 1
do not exceed 500 mrem / year to the total body and 3000 mrem / year to the skin. The initial setpoints will be ,
calculated using the BWR-GALE code radionuclides mix !
obtained for CPS; once CPS becomes operational, the actual radionuclides mix will be used. The PRM l setpoints are based on the instantaneous noble gas dose rates and are applied at the point of which the !
effluent enters an unrestricted area. Further, the bases for each setpoint consider the type of release at the PRM loca* don (long or short term using the appropriate atmo ,,heric dispersion conditions).
Due to PRM limitations, non-noble gas setpoints will not be implemented to demonstrate c.ompliance with CPS RETS 3.11.2.1(b). Compliance with the organ dose rate limitation is demonstrated during performance of sampling and analysis activities required by CPS RETS Table 4.11.2-1.
J l CLINTON-I 3-25 Rev.2-10/86 L-_ ------ -
..._ x- .
- +
- --- . r : -
CPS-0DCM 500'= Total body dose rate. limit specified in' CPS RETS 3.ll.'2'la,-
mrem / year
]
= The highest relative (X/Q)3 concentration of release. path j j at the site beundary )
=
(X7Q) or (x/q) de
.duratTon of relWa,se,pending sec/m3 on 3 (reference section 3.5.1)- l K = The total' body dose factor due to 1
gamma emissions of noble gas j radionuclides i as. listed in Table 1 B-1 of Regulatory Guide 1.109 and i Table 3.4-1 of this Manual, 1 mrem /yr. peru Ci/m3 f =
The: fraction as defined by f3 equation (18), dimensionless The total maximum acceptable concentration setpoint of noble gas. radionuclides in l.
release path j is calculated using- the following equation:
C Tj_ . T1,.uCi/cc (20)
, d where Cm. =
The total maximum acceptable
^3 concentration setpoint of all l noble gases in release path j ,
uCi/cc Q.= The maximum acceptable release T3 rate of all noble gases in release path j determined from i equation (19), pCi/sec R
3
=
The effluent release rate of release point j , cc/sec )
1 CLINTON-I 3-27 Rev.2-lu/86 l
I
- c. .. . ~w .-. : a w :._ w . ,. e.. , . ...
CPS-ODCM 3.7.2 Skin Dose Rate Setpoint To ensure compliance with the CPS RETS 3.11.2.la skin dose rate limit, PRM setpoints shall be calculated using the methodology presented in section 3.7.1 and by substituting the following equation for equation (19):
3000 F i ,pCi/sec (21)
Qg) = (X/Q)3[f(L f tl.1Mf )r f3 l l where Qg3 - The maximum acceptable release l rate of all noble gases in release path j, pCi/ sec F
d= Total dose rate allocation factor assigned to release path j (varying between 0.0 and 1.0), dimensionless 3000= Skin dose rate limit specified in CPS RETS 3.11.2.la, mrem / year (X/Q)$ = The highest relative concentration of release path j at the site boundary
=
(27Q),or'(x/c)m depending on duration of release, sec/m3 (reference section 3.5.1)
L1= The skin dose factor due to gamma emissions for each identified noble gas radionuclides i, mrad /yr per uCi/m3, as listed in Table 3.4-1 of this Manual.
1.1 = An air dose to skin dose equivalent conversion factor, mrem / mrad M
f= The air dose factor due to gamma emissions for each identified noble gas radionuclides i, mrad /yr per pCi/m3, as listed in Table 3.4-1 of this Manual f,=
f s The fraction defined by equation (18)
CLINTON-I 3-28 Rev.2-10/86
, , r . . : .. ;L . i .i..~'~ .3%' h. Te ~
CPS-0DCM The calculated total body and skin maximum acceptable concentration setpoints are l compared and the more restrictive setpoint used. a safety factor may also be applied to the concentration setpoint calculated by equation (20) to compensate for l statistical fluctuations and measurement errors.
CLINTON-I 3-29 Rev.2-10/86
1li
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i i
FIGURE 3.3-1
{
MAIN CONDENSER OFF-GAS TREATMENT SYSTEM YstR55$ yom $
IN66 Zoo 3A - _._
T 5 m%y ->--. f oonca s
-)--. Hvac 19R5'f3 m
/ l wwg\)&s m ,3 ~
ST* "
l] {
~
t i 1
n 7 '
u [lNMboloA T _
k, v
k,,
-l I I y sa4400:6 p l l1NwDouS4I f*
- PA 3
/ saiusows ,
g l i i m 0011 l { g 4
tMw ooo5s (N662 0o36 1 1AA nu mA6 1N66 0011 JN66oC13 T I ocAotTA A
.LPP<>Cu;; '
n n ovaotpA oCAC176 "" -
+ SGTS
( 1CDotA )- - -
Exha us t
( )
'^ 2'S 9' gg Stack l
Prima ry/ Second ary Co ntai nmen t Exhaust
- Monitors required by CPS TECHNICAL SPECIFICATIONS i
ICD 01A Main OCA01TA CV 1N66B010B Cooler 1N66D013 1PR355 off-Gas Condenser Separator Tank A Condenser B Charcoal Adsorber Post Treatment PRM ,
ICA01AA Steam Jet OCA01TB CV 1N66Z003A IN66D016 HEPA 1PR41S Off-Gas l
Air Ejector A Separator Tank B Dessicant Dryer A Filter Post Treatment PRM l ICA01AB Steam Jet 1N66D005A IN66Z003B OPR01S HVAC 1PR003 Standby Gas l
Air Ejector B Recombiner A Dessicant Dryer B Stack PRM #1 Treatment PRM OCA01PA Condenser 1N66D005B IN66B011 Gas OPR02S HVAC 1PR004 Standby Gas Vacuum (CV) Pump A Recombiner B Cooler Stack PRM #2 Treatment PRM OCA01PB CV Pump B IN66B010A Cooler 1N66D012 1PR34S Off-Gas Condenser A Charcoal Adsorber Retreatment PRM CLINTON-1 3-31 Rev.2-10/86
. .. . - :-. w :: . . w. :------ - -
CPS-0DCM TABLE 3.5-28 (continued)
VEGETATION PATHWAY DOSE RATE FACTORS - R (CHILD)
(m2 mrem /yr peraCi/sec)
ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE I-135 6.48E+04 1.17E+05 5.51E+04 1.03E+07 1.79E+05 NO DATA 8.88E+04 CS-134 1.60E+10 2.63E+10 5.55E+09 NO DATA 8.15E+09 2.92E+09 1.42E+08 CS-136 8.23E+07 2.26E+08 1.46E+08 NO DATA 1.20E+08 1.80EM7 7.95E+06 l CS-137 2.39E+10 2.29E+10 3.38E+09 NO DATA 7.46E+09 2.68E+09 1.43E+08 CS-138 1.32E+07 1.84E+07 1.17E+07 NO DATA 1.29E+07 1.39E+06 8.47E+06 BA-139 4.97E-02 2.65E-05 1.44E-03 NO DATA 2.32E-05 1.56E-05 2.87E+00 BA-140 2.77E+08 2.42E+05 1.62E+07 NO DATA 7.89E+04 1.45E+05 1.40E+08 3A-141 2.04E-21 1.14E-24 6.64E-23 NO DATA 9.88E-25 6.71E-24 1.16E-21 BA-142 9.70E-39 6.98E-42 5.42E-40 NO DATA 5.65E-42 4.11E-42 1.27E-40 LA-140 3.24E+03 1.13E+03 3.82E+02 NO DATA NO DATA NO DATA 3.16E+07 LA-142 3.39E-04 1.08E-04 3.38E-05 NO DATA NO DATA NO DATA 2.14E+01 CE-141 6.55E+05 3.27E+05 4.85E+04 NO DATA 1.43E+05 NO DATA 4.08E+08 CE-143 1.71E+03 9.29E+05 1.35E+02 NO DATA 3.90E+02 NO DATA 1.36E+07 CE-144 1.27E+08 3.99E+07 6.79E+06 NO DATA 2.21E+07 NO DATA 1.04E+10 PR-143 1.45E+05 4.37E+04 7.22E+03 NO DATA 2.36E+04 NO DATA 1.57E+08 PR-144 5.64E-26 1.74E-26 2.84E-27 NO DATA 9.22E-27 NO DATA 3.75E-23 ND-147 5.41E+05 4.38E+05 3.40E+04 NO DATA 2.41E+05 NO DATA 6.95E+08 W-187 6.44E+04 3.81E+04 1.71E+04 NO DATA NO DATA NO DATA 5.36E+06 NP-239 2.56E+03 1.84E+02 1.29E+02 NO DATA 5.31E+02 NO DATA 1.36E+07
- mrem /yr per Ci/m3 5
- 3.75x10 CLINTON-I 3-108 Rev.2-10/86
, 7_
t CPS-0DCM 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING The.Clinton Power Station (CPS) Radiological Environmental Monitoring Program (REMP) implements' CPS Technical Specification 3/4.12.1. Table 5.0-1 and Figures 5.0-1, 5.0-2 and 5.0-3 describe the program required by the Technical Specification.
Supplemental REMP samples required by commitments in the Environmental Report - Operating License Stage (ER-OLS) are also described in Table 5.0-1 and Figures 5.0-1, 5.0-2 and 5.0-3.
In addition to the required sampling program, CPS will perform supplemental periodic and long term sampling and analyses in order to better. monitor the environmental exposure pathways. These' samples will not be listed in the ODCM, however, full sample descriptions and results will be included in the Annual Radiological Environmental Operating Report.
Surface and drinking water samples are composited by ,
collecting aliquots of fixed volume at fixed time intervals. j This method of sampling is considered consistent with note (g) to CPS-TS Table 3.12-1.
5.1 INTERLABORATORY COMPARISON PROGRAM All analyses for CPS Radiological Environmental Monitoring Program are performed by Teledyne Isotopes Midwest Laboratories (TIML) located in Northbrook, Illinois.
Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs have been operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the. issuing agency but not to the participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems, l i
i Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies the range the results should fall within. Results consistently higher or lower than the known values and results outside the specified ranges indicate a need to check the instruments or procedures used.
CLtNTON-I 5-1 Rev. 2-10/86 9
. . . . . ,. ..e ..
< ~ . ..m .:_,m__ -
. u..._._.-
CPS-0DCM CPS has received results-obtained'through TIML's' participation in the environmental sample crosscheck program for milk, water, air filters and rood samples during the i !
period.1980 through October 1985'. This program has-been -l ;
conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
TIML has published results ior thermoluminescent dosimeters (TLDs) during the period 1976, 1977, 1979, 1980, and 1981 through participation in the Second, Third, Fourth and Fifth International Intercomparison of Environmental Dosimeters. I I
If the results of a determination in the EPA crosscheck I program are outside the control limits specified by the. EPA, CPS will require TIML to investigate the cause of the problem ;
and take steps to correct it. The results of this l investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report. ~
i l
i 1
CLINTON-I 5-2 Rev.2-10/86 l
~ ^~'
. - . a - - . .. ... .
. ..+ . . - - . . ,
l b CPS-0DCM Table 5.0-1 (continued)
REQUIRED NUMBER OF REPRESENTATIVE REQUIRED SAMPLING REQUIRED TYPES EXPOSURE PATHWAY SAMPLES AND AND COLLECTION AND FREQUENCY and/or SAMPLE TYPE SAMPLE LOCATIONS FREQUENCY OF ANALYSIS
- 3. WATERBORNE
- a. Surface 1 sample up- Composite sample Gamma isotopic stream over 1-month analysis 1 sample down- period monthly. J stream Composite for j l
tritium analysis f quarterly.
SECTOR CODE DISTANCE from station (miles)
ENE (upstream) CL-91 6.1 lJ SE (downstream) CL-90 0.4
- b. Ground Samples from Quarterly Gamma isotopic l 1 or 2 eources and tritium only if likely analysis .
to be affected. quarterly. l SECTOR CODE . DISTANCE from station (miles) ,
I l E CL-12 1.6* '
ESE CL-7D 2.3
- Sample location is in pump station distant from well. Well located 1.0 mile S of plant on the edge of the lake. i i
l c. Drinking 1 sample of each Composite sample I-131 analysis j over 2-week on each of 1 to 3 of the 1 nearest water ' period when composite for i supplies that I-131 analysis the dose !
could be affected is performed, calculated for by its discharge.* monthly composite the consumption ;
otherwise. of the water if I greater than 1 l mrem per year.
Composite for gross beta and gamma isotopic analysis ;
monthly.
Composi te for tritium analysis quarterly.
l CLINTON-I 5-6 Rev. 2-10/86
. i:- ......-. .u. :: - -
we .. . c. . . ..
CPS-0DCM' 4
Table 5.0-1 (continued)
J REQUIRED NUMBER (
OF . . . l REPRESENTATIVE REQUIRED SAMPLING REQUIRED TYPES j EXPOSURE PATHWAY SAMPLES AND AND COLLECTION AND FREQUENCY l and/or SAMPLE TYPE SAMPLE LOCATIONS OF ANALYSIS FREQUENCY
)i No milking animals within 8 km of the site were identified in the most i' recent annual land use survey.
1 sample from '
milking animals at a control location, 15-30 km distant and in the least prevalent wind direction.
l
, SECTOR CODE DISTANCE from station (miles)
WSW (control) CL-ll6 14 f
- b. Fish and 1 sample of three Sample in season Gamma isotopic inverte- important species or semiannually analysis on brates (such as bass, if they are not edible portions, crappie, carp,or seasonal, bluegill) in i vicinity of plant discharge. {
I SECTOR CODE DISTANCE from station (miles) l
}
E CL-19 3.4 {
1 sample of same three species in areas not in- :
fluenced by plant !
discharge. '
SECTOR CODE DISTANCE from station (miles)
S (control) CL-105 50 l
- c. Food 1 sample of each At time of harvest Gamma isotopic Products principal class analysis on of food products edible portions.
from any area that is irrigated by water in which liquid plant wastes have been dis-charged *.
- No known usage of Salt Creek water for irrigation in DeWitt, Logan, Menard, or Cass Counties. This information is checked annually as part of the land use survey.
CLINTON-I 5-8 Rev. 2-10/86
CPS-0DCM i i
Table 5.0-1 (continued)
~
i REQUIRED NUMBER OF REPRESENTATIVE REQUIhED SAMPLING REQUIRED TYPES EXPOSURE PATHWAY SAMPLES AND AND COLLECTION AND FREQUENCY and/or SAMPLE TYPE SAMPLE LOCATIONS FREQUENCY OF ANALYSIS
- c. Food Samples of 3 Monthly when Gamma isotopic Products different kinds available and I-131 (Cont.) of broad leaf analysis.
vegetation (such as lettuce, .
cabbage, and I swiss chard) I grown nearest j each of two different offsite locations of l highest pre- I dicted annual average ground-level D/Q if milk sampling is not performed.
SECTOR CODE DISTANCE from' station (miles)
NE CL-ll5 0.9 E CL-18 2.5 1 sample of each !
of the similar I broad leaf vege-tation grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed.
SECTOR CODE DISTANCE from station (miles)
SSE (Control) CL-ll4 12.5 CLINTON-I 5-9 Rev. 2-10/86
lb CPS-0DCM Table 5.0-1 (continued)- .
REQUIRED SAMPLING REQUIRED TYPES EXPOSURE PATHWAY AND COLLECTION AND FREQUENCY and/or SAMPLE TYPE FREQUENCY OF ANALYSIS i
.! ENVIRONMENTAL REPORT (OPERATING LICENSE STAGE) l TABLE 6.1-6 Rh.QUIREMENTS 1
- 1. Direct Radiation Quarterly Gamma dose, quarterly SECTOR CODE DISTANCE from station (miles)
NNE CL-2 0.7 NE CL-3 ... 0.7 CL-4' O8 i SW WSW CL-6 0.8 e' ., SE CL-7A 2.3 E CL-8 2.2
- 2. Airborne Continuous sampler Radiciodine.
4 operation with sample Cannister:
collection weekly, I-131 analysis composite quarterly. weekly.
.; Particulate Sampler i Gross beta radioactivity
, :{
l analysis following i filter changes.
- / Gamma isotopic d analysis of composite (by location, quarterly).
SECTOR CODE DISTANCE from station (miles)
W CL-1 1.8 SW CL-4 0.8 WSW CL-6 0.8 SE CL-7A 2.3 l
.]
l 1
CLINTON-I 5-10 Rev. 2-10/86 1
h _ - _ _ _ _ _ - _ - _ _ _ . - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
CPS-0DCM ;
Table 5.0-1 (continued)
REQUIRED. SAMPLING REQUIRED TYPES EXPOSURE PATHWAY AND COLLECTION AND FREQUENCY .
and/or SAMPLE TYPE FREQUENCY OF ANALYSIS
- 6. Shoreline Sediment Semiannual grab Gamma isotopic l i
sample. analysis.
S_ECTOR CODE DISTANCE from station (miles) !
ENE CL-10 5.0
- 7. Sli.me or aquatic Semiannual grab Gamma isotopic ,
vegetation sample. analysis. j (periphyton) 1 I
SECTOR CODE DISTANCE from station (miles) -
l l SE CL-7C 1.3 ENE CL-10 5.0 i j
- 8. Soil Every three years Gamma isotopic grab sample, analysis. l SECTOR CODE DISTANCE from station (miles)
W CL-1 1.8 i NNE CL-2 0.7 NE CL-3 0.7 SW CL-4 0.8 WSW CL-6 0.8 SE CL-7A 2.3-E CL-8 2.2 S CL-ll 16 E CL-94 0.6
- 9. Ground Water Biweekly 1-131 - biweekly ,
Grab Gamma isotopic analysis and Gross beta analysis -
monthly.
Tritium analysis - quarterly composite of monthly.
SECTOR CODE DISTANCE from station (miles)
E CL-12 1.6*
ESE CL-7D 2.3 l
- Sample location is in pump station distant from well. Well located 1.0 mile S of plant on edge of lake.
CLINTON-I 5-12 Rev. 2-10/86 f
C :
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CPS-0DCM FIGURE 5.0-1 i
REMP LOCATIONS WITHIN 1.5 MILES OF CPS y ~ _.
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CPS-0DCM i
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FIGURE 5.0 REMP LOCATIONS WITHIN 6 MILES OF CPS North J
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-. . . \ - _ . . . .. - . - - --:--_..---.
CPS-0DCM FIGURE 5.0-3' '
REMP LOCATIONS NITHIN'50' MILES OF CPS
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CLINTON-1 5-15 Rev. 2-10/86 l
CPS-0DCM 6.0 ADJUSTMENT'0FTHECPSODCMMETHbDOLOGY l
Consistent with the NRC Commissioners opinion on 10CFR50 Appendix I dated April 30, 1975, CPS will use environs monitoring data to improve dose calculational models and to request CPS ODCM changes on the basis of such operating I experience data. Such adjustments are recognized as being especially important for the radioiodine-milk pathway where conservative regulatory guide assumptions have been-mace. By using environs monitoring data, uncertainties associated with
. plume behavior, radiciodine chemical form, deposition and retention on forages, and milk consumption patterns may be circumvented or~ reduced.
\
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1 CLINTON-I- 6-1 Rev.2-10/86' I __- _ . . . _ _ - _ . ..__ _._. _ _ -
- _ . - . ._ 3 _ ._ _ _ _ _ . _ - _
1T1 l
CPS-0DCM 1
, r ,
7.0 ATMOSPHERIC TRANSPORT AND DISPERSION MODEL 1
7.1 Introduction l 1
The atmospheric transport and dispersion model used by i Illinois Power Company is a straight-line, !
sector-averaged Gaussian model designed to estimate I I
average relative concentrations at various receptor points. The model was developed in accordance with l routine release analysis procedures specified by i Regulatory Guide 1.111 (Revision 1 July 1977), Section i C.1.c " Constant Mean Wind Direction Models".
All meteorological and dose calculations prescribed in this manual ior long-term releases are based on meteorological data acquired onsite for the per.iod April 1975 through March 1976. This period cf record i was selected from five years of data (April 1972 through March 1977) and represents conservative dispersion conditions and highest data recovery.
Acquired meteorological data will be reviewed and X/Q values updated, if necessary, in the SE!IIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.
Even though the CPS RETS utilize historical annual average dispersion conditions in determining the Limiting Condition for Operation (LCO) for radioactive materials in gaseous effluents, annual hourly meteorological data will also be collected and summarized. This summary may either be included in the first half year SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT or retained onsite in a file that shall be provided to the NRC upon request.
The methodology utilized in calculating the undecayed, undepleted dispersion (Table 7.2-1) and deposition (Table 7.2-2) values is described in section 7.2.
Near-real time meteorological data processing is described in section 7.3. Site boundary dispersion parameters are listed in Table 7.2-5.
(
7.2 Historical Meteorological Data Processing
{
The data presented in Tables 7.2-1 and 7.2-2 are based l upon data acquired by a single onsite meteorological tower instrumented at the 10 and 60 meter heights with temperature, wind speed and wind direction sensors (see Figure 5.0-1 for tower location). Discharge l]{
point characteristics (refer to Table 7.2-4) permit ]
use of the mixed-mode dispersion model for all l calculations. Therefore, two stability wind roses, ,
elevated and ground, were developed jointly by I considering the wind data hour by hour. When the exit !
velocity to wind speed ratio indicates the release should be considered as elevated, the upper level data is used; as ground, lower level data.
CLINTON-I 7-1 Rev.2-10/86 l
1
CPS-0DCM Table 7.2-1 ANNUAL AVERAGE MIXED-MODE X/Q l April 1975 - April 1976 I
Distance Sector (meter)
N NNE NE ENE E ESE SE SSE 1.00+002 7.986-005 5.540-005 4.923-005 3.079-005 3.455-005 2.890-005 2.325-005 1.978-005 1.10+002 6.672-005 4.628-005 4.117-005 2.574-005 2.886-005 2.412-005 1.943-005 1.655-005 ;
1.20+002 5.668-005 3.931-005 3.500-005 2.188-005 2.452-005 2.048-005 1.650-005 1.408-005
{ 1.3O+002 4.883-005 3.386-005 3.017-005 1.886-005 2.112-005 1.763-005 1.422-005 1.214-005
} 1.40+002 4.256-005 2.951 005 2.631-005 1.644-005 1.840-005 1.535-005 1.239-005 1.059-005 1.50+002 3.749-005 2.599-005 2.318-005 1.449-005 1.62b005 1.353-005 1.091-005 9.336 006 1.60+002 3.331-005 2.309-005 2.062-005 1.287-005 1.440-005 1.203-005 9.700-006 8.305-006 1.70+002 2.982-005 2.067-005 1.847-005 1.153-005 1.289-005 1.078-005 8.684-006 7.442-006 1.80+002 2.688-005 1.862-005 1.665-005 1.039-005 1.162-005 9.717-006 7.827-006 6.712-006 l 1.90+002 2.437-005 1.688-005 1.511-005 9.418-006 1.053-005 8.813-006 7.096-006 6.088-006 '
2.00+002 2.221-005 1.538-005 1.377-005 8.583-006 9.598-006 8.035-006 6.467-006 5.531-006 2.10+002 2.033-005 1.408-005 1.262-005 7.859-006 8.788-006 7.360 006 5.921-006 5.085-006 2.20*002 1.870-005 1.295-005 1.160-005 7.227-006 8.080-006 6.769-006 5.445-006 4.678-006 2.3O+002 1.726-005 1.195-005 1.072-005 6.672-006 7.458-006 6.250-006 5.027-006 4.320-006 2.40+002 1.599-005 1.107-005 9.930-006 6.181-006 6.909-006 5.791-006 4.658-006 4.003-006 4 2.50+002 1.487-005 1.029-005 9.236-006 5.747 006 6.424-006 5.387-006 4.332-006 3.724-006 j 2.606002 1.391-005 9.630-006 8.641-006 5.376-006 6.017-006 5.053-006 4.059-006 3.488-006 l 2.70+002 1.304-005 9.034-006 8.106-006 5.041-006 5.650-006 4.751-006 3.814-006 3.276-006 3.80+002 1.226-005 8.495-006 7.622-006 4.739-006 5.318-006 4.477-006 3.591-006 3.084-006 2.90+002 1.155-005 8.006-006 7.183-006 4.465-006 5.016-006 4.228-006 3.389-006 2.909-006 3.00+002 1.091-005 7.560-006 6.784-006 4.216-006 4.740-006 4.000-006 3.205-006 2.750-006 3.20+002 9.779-006 6.781-006 6.084-006 3.779-006 4.258-006 3.600-006 2.881-006 2.471 006 3.40+002 8.825-006 6.122-006 5.494-006 3.411-006 3.849-006 3.260-006 2.607-006 2.235-006 3.60+002 8.011-006 5.561-006 4.990-006 3.096-006 3.500-006 2.970-006 2.373-006 2.032-006 3.80+002 7.324-006 5.086-006 4.564-006 2.830-006 3.203-006 2.722-006 2.173-006 1.860-006 4.00+002 6.756-006 4.695-006 4.210-006 2.608-006 2.953-006 2.513-006 2.005-006 1.712-006 4.20+002 6.256-006 4.350-006 3.898-006 2.412-006 2.733-006 2.329-006 t.857-006 1.583-006 4.40+002 5.813-006 4.044-006 3.622-006 2.239-006 2.538-006 2.166-006 1.725-006 1.469-006 4.60+002 5.418-006 3.771-006 3.377-006 2.086-006 2.365-006 2.021-006 1.608-006 1.367-006 4.80+002 5.064-006 3.527-006 3.157-006 1.948-006 2.210-006 1.890-006 1.504-006 1.276-006 5.00+002 4.746-006 3.307-006 2.959-006 1.824-006 2.070-006 1.773-006 1.410-006 1.194-006 5.20+002 4.459-006 3.108-006 2.780-006 1.713-006 1.944-006 1.667-006 1.325-006 1.121-006 j 5.40+002 4.198-006 2.928-006 2.619-006 1.612-006 1.830-006 1.571-006 1.247-006 1.054-006 l 5.60+002 3.961-006 2.763-006 2.471-006 1.520-006 1.726-006 1.484-OOE 1.177-006 9.938-007 5.80+002 3.745-006 2.613-006 2.337-006 1.436-006 1.631-006 1.404-006 1.113-006 9.387-007 l 6.00+002 3.547-006 2.476-006 2.214-006 1.359-006 1.544-006 1.330-006 1.055-006 8.884-007 l 6,50+002 3.119-006 2.179-006 1.948-006 1.194-006 1.357-006 1.172-006 9.282-007 7.799-007 l 7.00+002 2.773-006 1.939-006 1.734-006 1.061-006 1.204-006 1.043-006 8.261-007 6.924-007 l
7.50+002 2.494-006 1.746-006 1.563-006 9.561-007 1.079-006 9.378-007 7.440-007 6.221-007 8.05+002 2.237-006 1.568-006 1.405-006 8.591-007 9.649-007 8.413-007 6.687-007 5.577-007 j 8.50+0C2 2.056-006 1.442-006 1.293-006 7.903-007 8.843-007 7.730-007 6 154-007 . 5.124-007 i 9.00+002 1.881-006 1.321-006 1.186-006 7.243 007 8.073-007 7.076-007 5.645-007 4.692-007 3.50+002 1.729-006 1.216-006 1.092-006 6.670-007 7.407-007 6.508-007 5.204-007 4.319-007 1.00+003 1.602-006 1.128-006 1.013-006 6.186-007 6.851-007 6.022-007 4.834-007 4.004-007 1.10+003 1.379 006 9.730-007 8.750-007 5.340-007 5.881-007 5.194-007 4.189-007 3.463-007 1.20+003 1.203-000 8.516-007 7.665-007 4.679-007 5.127-007 4.546-007 3.685 007 3.042-007 1.3O+003 1.063-006 7.543-007 8i.795-007 4.149-007 4.527-007 4.026-007 3.282-007 2.705-007 1.40+003 9.537-007 6.780-007 S.110-007 3.735*007 4.066-007 3.616-007 2.966-007 2.445-007 1.50+003 8.660-007 6.169-007 5.559-007 3.404-007 3.704-007 3.287-007 2.714-007 2.238-007 1.61+003 7.892-007 5.606-007 5.053-007 3.099-007 3.370-007 2.984-007 2.482-007 2.048-007
-5 3
- 7.986 x 10 sec/m CLINTON-I 7-6 Rev.2-10/86 i
._ _ _ .._ u.u . __
CPS-0DCM Table 7.2-1 (Continued)
ANNUAL AVERAGE MIXED-MODE X/Q April 1975 - April 1976 Distance Sector (meter)
N NNE NE ENE E ESE SE SSE 1.80+003 6.724-007 4.820-007 4.347-007 2.673-007 2.903-007 2.561-007 2.157-007 1.782-007 2.00+003 5.816-007 4.187-007 3.779-007 2.330-007 2.526-007 2.220-007 1.893-007 1.566-007 2.204003 5.104-007 3.690-007 3.334-007 2.059-007 2.230-007 1.953-007 1.684-007 1.395-007 2.41+003 4.496-007 3.265-007 2.954-007 1.828-007 1.976-007 1.726-007 1.505-007 1.'47-007 2.60+003 4.065-007 2.963-007 2.683-007 1.663-007 1.795-007 1.563-007 1.375-007 1.140-007 2.80+003 3.677-007 2.689-007 2.438-007 1.513-007 1.632-007 1.417-007 1.258-007 1.043-007 3.00+003 3.349-007 2.458-007 2.231'007 1.386-007 1.493-007 1.293-007 1.157-007 9.598-008
- 3. 2 't +003 3.046-007 2.243-007 2.038-007 1.268-007 1.364-007 1.179-007 1.063-007 8.817-008 3.60+003 2.620-007 1.940-007 1.766-007 1.101-007 1.182-007 1.017-007 9.283-008 7.702-008
_ 4.02+003 2.258-007 1.601-007 1.533-007 9.571-008 1.026-007 8.790-008 8.115-008 6.735-008 4.40+003 2.003-007 1.497-007 1.368-007 8.551-008 9.156-008 7.816-008 7.277-008 6.040-008 4.83+003 1.770-007 1.328-007 1.215-007 7.606-008 8.135-008 6.917-008 6.495-008 5.391-008 5.00+003 1.689-007 1.269-007 1.162-007 7.278-008 7.780-008 6.605-008 6.221-008 5.163-008 5.20+003 1.603-007 1.206-007 1.105-007 6.926-008 7.401-008 6.273-008 5.927-008 4.919-008 5.63+003 1.442-007 1.088-007 9.975-008 6.261-008 6.684-008 5.645-008 5.368-008 4.455-008 6.00+003 1.325-007 1.003-007 9.198-008 5.780-008 6.167-008 5.193-008 4.962-008 4.118-008 6.44+003 1.207-007 9.154-008 8.403-008 5.287-008 5.638-008 4.731-008 4.544-008 3.772-008 7.24+003 1.032-007 7.861-008 7.221-008 4.554-008 4.851-008 4.048-008 3.919-008 3.253-008 7.50+003 9.856-008 7.513-008 6.902 008 4.356-008 4.640-008 3.864-008 3.750-008 3.112-008 8.05+003 8.979-008 6.859-008 6.303-008 3.984-008 4.241-008 3.520-008 3.431-008 2.847-008 9.50+003 8.350-008 6.390-008 5.873-008 3.716-008 3.955-008 3.273-008 3.201-008 2.656-000 9.00+003 7.742-008 5.935-008 5.455-008 3.455-008 3.677-008 3.034-008 2.976-008 2.470-008 9.50+003 7.209-008 5.534-008 5.087-008 3.226-008 3.432-008 2.824-008 2.778-008 2.306-008 1.00+004 6.737-008 5.179-008 4.761-008 3.022-008 3.215-008 2.638-008 2.603-008 2.160-008 1.21+004 5.257-008 4.062-008 3.733-008 2.378-008 2.530-008 2.055-008 2.046-008 1.699-008 1.40+004 4.326-008 3.355-008 3.082-008 1.969-008 2.095-008 1.688-008 1.691-008 1.405-008 1.61+004 3.604-008 2.805-008 2.575-008 1.649-008 1.755-008 1.404-008 1.414-008 1.176-008 1.80+004 3.113-008 2.429-008 2.229 008 1.430-008 1.523-008 1.211-008 1.225-008 1.019-008 2.00+004 2.713-008 2.122-008 1.946 008 1.251-008 1.333-008 1.054-008 1.070-008 8.901-009 2.20+004 2.396-008 1.878-008 1.722-008 1.109-008 1.182-008 9.295-009 9.463-009 7.879-009 2.41+004 2.124-008 1.668-008 1.528-008 9.853-009 1.051-008 8.227-009 8.400-009 6.957-009 2.60+004 t.928-008 1.517-008 1.390-008 8.968-009 9.573-009 7.464-009 7.637-009 6.364-009 2.80+004 1.752-008 1.380-008 1.264-008 8.164-009 8.720 009 6.773-009 6.945-009 5.790-009 3.22+004 1.462-008 1.156-008 1.058-008 6.843-009 7.318-009 5.644-009 5.810-009 4.847-009 3.40+004 1.362-008 1.078-008 9.864-009 6.385-009 6.831-009 5.254-009 5.416-009 4.521-009 4.02+004 1.096-008 8.703-009 7.963-009 5.161-009 5.532-009 4.221-009 4.369-009 3.650-009 4.20+004 1.038-008 8.242-009 7.542-009 4.890-009 5.243-009 3.993-009 4.137-009 3.457-009 4.83+004 8.678-009 6.911-009 6.326-009 4.103-009 4.406-009 3.337-009 3.466-009 2.899-009 5.00+004 8.297-009 6.612-009 6.053-009 3.927-009 4.218-009 3.190-009 3.3'16-009 2.774-009 5.63+004 7.124-009 5.689-009 5.209-009 3.381-009 3.636-009 2.737-009 2.852-009 2.388-009 5.80+004 6.862-009 5.483-009 5.021-009 3.259-009 3.506-009 2.636-009 2.748-009 2.301-009 6.00+004 6.571-009 5.254-009 4.812-009 3.123-009 3.361-009 2.524-009 2.633-009 2.205-009 6.44+004 6.007-009 4.808-009 4.405-009 2.859-009 3.079-009 2.306-009 2.409-009 2.018-009 7.24+004 5.169-009 4.145-009 3.799-009 2.466-009 2.660-009 1.984-009 2.076-009 1.741-009 7.50+004 4.943-009 3.967-009 3.636-009 2.360-009 2.547-009 1.897-009 1.986-009 1.666-009 8.05+004 4.520-009 3.631-009 3.330-009 2.161-009 2.334-009 1.734-009 1.817-009 1.525-009 8.50+004 4.215-009 3.389-009 3.109-009 2.018-009 2.180-009 1.617-009 1.696-009 1.424-009 9.00+004 3.920-009 3.154-009 2.894-009 1.878-009 2.031-009 1.503-009 1.578-009 1.325-009 9.50+004 3.659-009 2.947-009 2.705-009 1.755-009 1.899-009 1.403-009 1.474-009 1.238-009 1.00+005 3.428-009 2.763-009 2.537 009 1.646-009 1.782-009 f.314-009 1.382-009 1.161-009 CLETON-1 7-7 Rev.2-10/86
m _ .. ._._, _ _ _ _ _ ' ~
CPS-0DCM- .
i
' Table 71i-1 (Continued)
ANNUAL AVERAGE MIXED-MODE X/Q
-April 1975 - April 1976 Distance Sector (meter) l 5 SSW SW WSW W WNW NW NNW 1.00+002 2.190-005 1.673-005 3.393-005 3.522-005 3.390-005 2.578-005 3.755-005 5.162-005 1.10+002 1;833-005 1.399-005 2.838-005 2.947-005 2.836-005 2.156-005. 3.142-005 4.315-005 '1 1.20+002 1.560-005 1.190 005 2.414-005 2.507-005 2.411-005 1.834-005 2.673-005 3.668-005 l 1.3O+002 1.345-005 1.026-005 2.081-005 2.162-005 2.079-005 1.581-005 2.305-005 3.161-005 I 1.40+002 1.174-005 8.945-006 1.815-005 1.887-005 1.813-005 1.379-005 2-011-005 . 2.756 005 !
1.50+002 1.035-005 7.882-006 1.600-005 1.663-005 1.598-005 1.216-005 1.772-005 2.429-005 1.60+002 9.203-006 7.006-0Q6 1.423-005 1.478-005 1.421-005 1.081-005 1.576-005 2.159-005 1,70+002 ~8.245-006 6.275-006 1.274-005 1.324-005 1.272 005 9.685-006 1.411-005 1.933-005 1.80+002 7.434-006 5.656-006 1.149-005 1.193-005 1.147-005 8.734-006 1.272 005 1.743-005 1.90+002 6.743-006 5.129-006. 1.042-005 1.062-005 1.040-005 7.922-006 1.154-005 1.580-005-2.00+002 *6.147-006 4.675-006- 9.503-006 9.862-006 9.480-006 7.224-006 1.051-005 1.440-005 2.10+002 .5.630-006 4.281-006 8.704-006 9.032-006 8.681-006 6.618-006 9.628-006 1.319-005 '
2.20+002 5.178-006 3.937-006 S.006-006 8.306-006' 7.984-006. 6.088-006 8.854-006 1.213-005 2.3O+002 4.781-006 3.635-006 7.393-006 7.669-006 7.371-006 5.623 006 8.174-006 1.120-005 2.40+002 4.430-006 3.368-006 6.850-006 7.105-006 6.829-006 5.211-006 7.572-006 1.038-005 2.50+002 4.119-006 3.132-006 6.370-006 6.606-006 6.349-006 4.846-006 7.038-006 9.648-006.
2.60+002 3.850-006 2,932-006 5.957-006 6.169-006 5.933-006 4.529-006 6.573-006 9.016-006 2.70+002 3.608-006 2.751-006 5.585-006 5.777-006 5.559-006 4.243-006 6.155-006 6.449 006 2.80+002 3.389-006 2.587 006 5.248-006 5.423-006 5.221-006 3.985-006 5.777-004 7.935-006 2.90+002 3.191-006 2.439-006 4.943-006 5.102-006 4.915-006 3.752-006 5.435-006 7.471-006 3.00+002 3.010-006 2.305-006 4.666-006 4.810-006 4.637-006 3.539-006 5.124-006 7.048-006 3.20+002 2.695-006 2.069-006 4.179-006 4.301-006 4.150-006 3.168-006 4.580-006 6.309-006 3.40+002 2.429-006 1.870-006 3.769-006 3.872-006 3.740-006 2.855-006 4.123-006 5.685-006 3.60+002 2.202-006 1.701-006 3.419-006 3.508-006 3.391-006 2.589-006 3.734-006 '5.155-006 3.80+002 2.010-006 1.557-006 3.12t-006 3.197-006 3.095-006 2.364-006 3.405-006 4.707-006 4.00+002 1.848-006 1.437-006 2.868-006 2.935-006 2.847-006 2.177-006 3.128-006 4.337 006 4.20+002 1.705-006 1.331-006 2.647-006 2.706-006 2.629-006 2.012-006 2.886-006 4.011-006 4.40+002 1.580 006 1.237-006 2.452-006 2.504-006 2.437-006 1.867 006 2.672-006 3.723-006 4.60+002 1.469-006 1.154-006 2.278-006 2.325-006 2.266-006 1.738-006 2.483-006 3.467-006 4.80+002 1.369-006 1.079-006 2.124-006 2.165-006 2.114-006 1.622-006 2.315-006 3.238-006 5.00+002 1.281-006 1.012-006 1.985-006 2.022-006 1.978-006 1.518-006 2.164-006 3.033-006 I 5.20+002 1.201-006 9.020-007 1.860-006 1.894-006 1.855-006 1.425-006 2.028-006 2.848-006 5.40+002 1.128-006 8.972-007 1.748-006 1.778-006 1.744-006 1.341-006 f.905-OO6 2.680-006 5.60+002 1.063-006 8.474-007 1.646-006 1.673-006 1.644-006 1.264-006 1.794-006 2.527-006 5.80+002 1.003-006 8.018-007 1.553-006 1.577-006 1.552-006 1.194-006 1.693-006 2.388-006 I 6.00+002 9.488-007 7.601-007 1.468-006 1.490-006 1.468-006 1.130-006 1.600-006 2.261 006 I 6.50+002 8.318-007 6.698-007 1.285-006- 1.303-006 1.287-006 '9.922-007 1.402-006 1.986-006 7.00+002 7.378-007 5.965-007 1.139-006 1.154-006' 1.142-006 8.816-007 1.243-006 1.765*006 7.50+002 6.622-007 5.372 007 1.021-006 1.037-006 1.026-006. 7.932-007 1.115-006 1.587-006 8.05+002 5.932-007 4.825-007 9.140-007 9.295-007 9.193-007 7.120-007 9.987-007 1.424-006 8.50+002 5.445-007 4.438-007 8.384-007 8.536-007 8.439-007 6.546 007 9.163 007 1.309-006 9.00+002 4.981-007 4.067-007 7.662-007 7.811-007 7.717-007 5.996-007 8.375-007 1.198-006 9.50+002 4.580-007 3.745-007 7.037-007 7.182 007 7.091-007 5.518-007 7.692-007 1.101-006 1.00+003 4.247-007 3.476-007 6.515-007 6.658-007 6.567-007 5.119-007 7.124-007 1.021-006 1.10+003 3.660-007 3.003-007 5.603-007 5.734-007 5.646-007 4.414-007 6.119-007 8.786-007 l 1.20+003 3.203-007 2 . 6'J 3-007 4.894-007 5.015-007 4.928-007 3.863 007 5.337-007 7.676-007 I 1.3O+003 2.840-007 2.,38-007 4.331-007 4.443-007 4.357-007 3.423-007 4.715-007 6.789-007 1.40+003 2.564-007 2.109-007 3.901-007 4.007-007 3.918-007 3.083-007 4.241-007 6.101-007 1.50+003 2.347-007 1.928-007 3.564-007 3.665-007 3.574-007 2.814-007 3.871-007 5.553-007 1.61+003 2.148-007 1.761-007 3.253 007 3.349-007 3.256-007 2.565-007 3.529-007 5.049-007 1
l l
1 CLINTON-I 7-8 Rev.2-10/86 l 1
l.
l
E- .- . _ . . . _ _ . _ _ _ _ 1 _.2 _ m l CPS-0DCM l
Table 7.2-1 (Continued) l l ANNUAL AVERAGE MIXED-MODE X/Q l April 1975 - April 1976 l
l l
- Distance Sector (meter)
S SSW SW WSW W WNW NW NNW 1.80+003 1.867-007 1.529-007 2.816-007 2.903-007 2.810-007 2.217-007 3.049-007 4.343-007 2.00+003 1.638-007 1.342-007 2.462-007 2.541-007 2.449-007 1.935-007 2.660-007 3.774-007 2.20+003 1.457-007 1.195-007 2.182-007 2.254-007 2.165-007 1.713-007 2.353-007 3.327-007 l 2.41+003 1.301-007 1.068-007 1.941-007 2.006-007 1.922-007 1.522-007 2.090-007 2.944-007 i
3.60+003 1.188-007 9.776-008 1.769-007 1.828-007 1.748-007 1.385-007 1.902-007 2.671-007 2.80+003 1.086-007 8.952-008 1.612-007 1.666-007 1.590-007 1.262-007 1.731-007 2.425-007 3.00+003 9.980-008 8.248-008 1.478-007 1.528-007 1.457-007 1.157-007 1.587-007 2.216-007 3.22+003 9.158-008 7.589-008 1.353-007 1.399-007 1.332-007 1.059-007 1.452-007 2.023-007 I 3.60+003 7.986-008 6.648-008 1.176-007 1.216-007 1.156-007 9.198-008 1.261-007 1.749-007 4.02+003 6.970-008 5.834-008 1.023 007 1.058-007 1,005-007 8.003-008 1.097-007 1.515-007 4.40+003 6.243-008 5.247-008 9.145-008 9.452-008 8.978-008 7.154-008 9.801-008 1.349-007 4.83+003 5.566-008 4.696-008 8.135-008 8.407-008 7.984-008 6.368-008 8.721-008 1.197 007 5.00+003 5.329-008 4.503-008 7.783-008 8.043-008 7.638-008 6.094-008 8.345-008 1.144-007 i 5.20+003 5.075-008 4.295-008 7.407-008 7.653-008 7.267-008 5.801-008 7.943-008 1.087-007 I 5.63+003 4.593-008 3.899-008 6.693-008 6.916-008 6.567-008 5.246-008 7.181-008 9.802-008 ;
I 3.00+003 4.244-008 3.610-008 6.178-008 6.382-008 6.061-008 4.845-008 6.631-008 9.032-008 j l 3.446003 3.885-008 3.312-008 5.649-008 5.836-008 5.542-008 4.433-008 6.068-000 8.245-008 l 7.24+003 3.348-008 2.864-008 4.561-008 5.022-008 4.771-008 3.821-008 5.228-008 7.078-008 l
i 7.50+003 3.203-008 2.743-008 4.648-008 4.802-008 4.563-008 3.656-008 5.002-008 6.764-008 8.05+003 2.930-008 2.513-008 4.248-008 4.389-008 4.171-008 3.345-008 4.576-008 6.175-008 8.50+003 2.733-008 2.347-008 3.960-008 4.092-008 3.889-008 3.121-008 4.269-008 5.751-008
(
9.00+003 2.542-008 2.185-008 3.680-008 3.803-008 3.616-008 2.903-008 3.971-008 5.341-008 9.50+003 2.373-008 2.042-008 3.433-008 3.549-008 3.374-008 2.711-008 3.708-008 4.980-008
- 1.00+004 2.223 008 1.915-008 3.214-008 3.323-008 3.160-008 2.541-008 3.475-008 4.660-008 l 1.21+004 1.748-008 1.510-008 2.523-008 2.611-008 2.485-008 2.003-008 2.738-008 3.653 008 l 1.40+004 1.446-008 1.251-008 2.084-008 2.160-008 2.056-008 1.660-008 2.270-008 3.016-008 l
1.61+004 t.211-008 1.048-008 1.741-008 1.807-008 1.720-008 1.392-008 1.903-008 2.520-008 i.80+004 1.049-008 9.090-009 1.507-008 1.566-008 1.491-008 1.209-008 1.652-008 2.182-008 2.00+004 9.172-009 7.948-009 1.316-008 1.370-008 1.303-008 1.059-008 1.446-008 1.906-008 l 2.20+004 8.122-009 7.039-009 1.164-008 1.213-008 1.154-008 9.390 009 1.282-008 1.687-008 2.41+004 7.216-009 6.254-009 1.033-008 1.079-008 1.025-008 8.355-009 1.140-008 1.498-008 2.60+004 6.566-009 5.690-009 9.384-009 9.817-009 9.327-009 7.612-009 1.039-008 1.362-008 2.80+004 5.975-009 5.177-009 8.530-009 8.939-009 8.487-009 6.936-009 9.461-009 1.239-008 3.22+004 5.006-009 4.336-009 7.131-009 7.497-009 7.109-009 5.824-009 7.940-009 1.038-008 3.40+004 4.670-009 4.044-009 6.646-009 6.998-009 6.631-009 5.438-009 7.412-009 9.681-009 4.02+004 3.773-009 3.265-009 5.355-009 5.664-009 5.356-009 4.407-009 6.000-009 7.820-009 4.20+004 3.575-009 3.092-009 5.069-009 5.368-009 5.072-009 4.178-009 5.686-009 7.407-009 4.83+004 3.000-009 2.592-009 4.243-009 4.511-009 4.253-009 3.514-009 4.776-009 6.214-009 9.00+004 2.871-009 2.480-009 4.058-009 4.318 009 4.069-009 3.365-009 4.572-009 5.946-009 9.63+004 2.472-009 2.133-009 3.486-009 3.723-009 3.501-009 2.902-009 3.940-009 5.119-009 5.80+004 2.383-009 2.056-009 3.359-009 3.590-009 3.374-009 2.799-009 3.798 009 4.934-009 6.00+004 2.284-009 1.970-009 3.217-009 3.442-009 3.233-009 2.684-009 3.641-009 4.729-009 b.44+004 2.091-009 1.803-009 2.941-009 3.154-009 2.959-009 2.460-009 3.335-009 4.329-009 7.24+004 1.804-009 1.554-009 2.532-009 2.726-009 2.551-009 2.126-009 2.879-009 3.735-009 7.50+004 1.727-009 1.487-009 2.422-009 2.610-009 2.441-009 2.036-009 2.756-009 3.575-009 8.05+004 1.581-009 1.361-009 2.215-009 2.393-009 2.234-009 1.866-009 2.525-009 3.274-009 8.50+004 1.477-009 1.270-009 2.066-009 2.236-009 2.086-009 1.744-009 2.358-009 3.057-009 9.00+004 1.375-009 1.182-009 1.922-009 2.084-009 1.941-009 1.625-009 2.196-009 2.846-009 9.50+004 1.285-009 1.104-009 1.794-009 1.949-009 1.814-009 1.520-009 2.053-009 2.660-009 1.00+005 1.205-009 1.035-009 1.682-009 1.830-009 1.701-009 1.426-009 1.926-009 2.495-009 CLINTON-1 7-9 Rev.2-10/86
CPS.-0DCM Table 7.2-2' i
ANNUAL AVERAGE MIXED-MODE D/Q j April 1975 - April 1976 Distance Sector (meter)
N NNE NE ENE E ESE SE SSE 1.00+002 2.908-007 2.224-007 1.887-007 1.152-007 1.418-007 1.524-007 1.002-007 7.533 003 1.10+002 2 562-007' t.960-007 1.663-007 1.015-007 1.250-007 1.343-007 8.837-008 6.641-008 1.20+002 2.283-007 1.746-007 1.482-007 9.049-008 1.113-007 1.197-007 7.876-008 5.920-008 1.3O+002 2.053-007 1.571-007 t.334-007 8.141-008 1.001-007 1.076-007 7.087-008 5.327-008 1.40+002 1.861-007 1.424-007 1.210-007 7.383-008 9.078-008 9.759-008~ 6.428-008 4.832 008 1.50+002 1.699-007 1.300-007 1.105-007 6.742-008 8.286-008 8.908 008 5.871-008 4.414-008 1.60+002 1.560-007 1.194-007 1.015-007 6.194-008 7.610-008 8.181-008 5.395-008 4.057-008 1.70+002 1.440-007 1.102-007 9.380-008 5.721-008 7.025-008 7.553-008 4.984 008 3.749-008 1.80+002 1.335-007 1.022-007 8.707-008 5.310-008 6.516-008 7.007-008 4.627-008 3.481-008 1.90+002 1.244-007 9.522-008 8.118-008 4.949-008 6.070-008 6.527-008 4.314-008 3.246-008 2.00+002 1.163-007 8.906-008 7.600-008 4.632*008 5.677-008 6.105-008 4.040-008 3.041-008 2.10+002 1.085-007 8.314-006 7.101-008 4.326-008 5.299 ooc 5.699-008 3.775-008 2.843-008 2.20+002 1.016-007 7.786 008 6.657-008 4.055-008 4.963-008 5.338-008 3.539-008 2.666-008 2.3O+002 9.547-008 7.315-008 6.260 008 3.812-008 4.663 008 5.015-008 3.329-008 2.509-008 2.40+002 8.992-008 6.892 008 5.904-008 3.594-008 4.393 008 4.725 008 3.140-008 2.367-008 2.50+002 8.491-008 6.510-008 5.583-008 3.397-008 4.149-008 4.463-008 2.969-00; 2.240-008 2.60+002 8.037-008 6.163-008 5.292-008 3.219 008 3.928-008 4.226-008 2.815-008 2.125-008 2.70+002 7.625-008 5.849-008 5.028-008 3.057-008 3.727-008 4.011-008 2.675-008 2.020-008 2.80+002 7.248 008 5.562-008 4.788-008 2.910-008 3.544-008 3.814-008 2.548-008 1.925-008 2.90+002 6.903-008 5.299-008 4.568-008 2.775-008 3.377-008 3.634-008 2.432-008 1.838-008 3.00+002 6.587-008 5.058-008 4.367-008 2.G51-008 3.223-008 3.469-008 2.325-008 1.759-008 3.20+002 5.988-008 4.601-008 3.979-008 2.415-008 2.931-008 3.156-008 2.120-008. 1.605-008 3.40+002 5.477-008 4.210-008 3.649-008 2.213-008 2.682-008 2.888-008 1.945-008 1.474-008 3.60+002 5.036-008 3.873-008 3.365-008 2.039-008 2.468-008 2.658-008 1.795-008 1.362-008 3.80+002 4.653-008 3.581-008 3.118-008 1.888-008 2.281-008 2.458-008 1.664-008 1.264-008 4.00+002 4.318 008 3.325-008 2.902-008 1.756-008 2.118-008 2.283-008 j 1.550-008 1.179 008 1 4.20+002 4.022-008 3.100-008 2.712-008 1.640-008 1.975-008 2.128-008 1.450-008 1.104-008 4.40+002 3.761-008 l 2.901-008 2.544-008 1.537-008 1.848 008 1.992-008 1.361-008 1.038-008 f 4.60+002 3.528-008 2.723-008 2.394-008 1.446-008 1.735-008 1.870-008 1.282-008 9.794-009 4.80+002 l
'3.319-008 2.564-008 2.260-008 1.364-008 1.633-008 1.762-008 1.212 008 9.271-009 j 5.00+002 3.131-008 2.422-008 2.140-008 1.290-008 1.542-008 1.664-008 1.149-008 8.803-009 I 5.20+002 2.948 008 2.281-008 2.018-008 1.216 008 1.453-008 1.5E8 OO8 1.085-008 8.318-009 5.40+002 2.782-008 2.153-008 1.908-008 1.150-008 f.372-008 1.481-008 1.027-008 7.879-009 5.60+002 2.630-008 2.038-008 1.808-008 1.089-008 1.298-008 1.401-008 9.737-009 7.480-009 5.80+002 2.493-008 1.932-008 1.716-008 1.033-009 1.231-008 1.329-008 9.256-009 7.116-009 6.00+002 2.367 008 1.835-008 1.633-008 9.826 009 1.169-008 1.263-008 8.815-009 6.783-009 6.50+002 2.094-008 1.627-008 1.452-008 8.731-009 1.037-008 f.120-008 7.867-009 6.066-009 7.00+002 1.872-008 1.456-008 1.304-008 7.833-009 9.279 009 1.004*008 7.091-009 5.480-009 7.50+002 1.683-008 1.311-008 1.176-008 7.063-009 8.356-009 9.045-009 6.418-009 4.969-009 8.05+002 1.510-008 1.178-008 1.060-008 6.359-009 7.514-009 8.138-009 5.805 009 4.503-009 8.50+002 1 389-008 1.085-008 9.776-009 5.864-009 6.920-009 7.500-009 5.374-009 4.175-009' 9.00+002 1.273-008 9.958-009 8.992-009 5.391-009 6.354-009 6.891-009 4.963-009 '3,862 009 9.5C+002 1.173-008 9.188-009 8.313-009 4.981-009 5.865-009 6.365-009 4.608 009 3.593-009 l 1.00+003 1.085-008 8.516-009 7.721-009 4.625-009 5.438-009 5.907-009 4.299-009 3.358-009 1.10+003 9.263-009 7.283-009 6.616-009 3.962-009 4.654-009 5'.060-009 3.705-009' 2.900-009 1.20+003 8.021-009 6.319-009 5.751-009 3.443-009 4.040'009 4.397-009 3.739 009 2.540-009 1.3O+003 7.030-009 5.548-009 5.059-009 3.028-009 3.550-009 3.867 009 2.867-009 2.253-009 1.40+003 6.224-009 4.922-009 4.497-009 2.691-009 3.152-009 3.437-009 2.564 009 2.019-009 1.50+003 5.559-009 4.406-009 4.033-009 2.414-009 2.823-009 3.082-009 2.314-009 1.826-009 1.61+003 4.957-009 3.938-009 3.613-009 2.162-009 2.526-009 2.761 009 2.088 009 1.651-009
- 2.908 x 10 m
-2 CLINTON-I 7-10 Rev.2-10/86
\
_ . . ._ .n _ _ . _ _ _ . m ._ -
1 CPS-0DCM i Table 7.2-2 (Continued)
ANNUAL AVERAGE MIXED-MODE D/Q April 1975 - April 1976 i
l Distance Sector (meter) l l I N NNE NE ENE E ESE SE SSE 1.80+003 4.136-009 3.300-009 3.038-009 1.818-009 2.119-009 2.322-009 1.778-009 1.413-009 1 2.00+003 3.493-009 2.801-009 2.589-009 1.549-009 1.802-009 1.979-009 1.537-009 1.226-009 l 2.20+003 2.970-009 2.387-009 2.211-009 1.323-009 1.537-009 1.691-009 f.322-009 1.057-009 l 2.41+003 2.537-009 2.045-009 1.897-009 1.135-009 1.318-009 1.452-009 1.143-009 9.160-010 t 2.60+003 2.238-003 1.807-009 1.680-009 1.005-009 1.166-009 1.286-009 1.018-009 8.177-010 !
2.80+003 1.975-009 1.599-009 1.488-009 8.909-010 1.032-009 1.140 009 9.083-010 7.308-010 -
3.00+003 1.758-009 1.427-009 1.330-009 7.963-010 9.219-010 1.019-009 8.172-010 6.588-010 J 3.22+003 ?.561-009 1.268-009 1.184-009 7.089-010 8.199-010 9.071-010 7.296-010 5.889-010 J 3.60+003 1.292-009 1.052-009 9.837-010 5.892-010 6.805-010 7.538-010 6.095-010 4.930-010 1 4.02+003 1.071-009 8.740-010 8.189 010 4.906-010 5.658-010 6.275-010 5.101-010 4.135-010 4.40+003 9.212-010 7.532-010 7.068-010 4.235-010 4.879-010 5.416-010 4.423 010 3.592-010 4.83+003 7.884-010 6.456-010 6.069-010 3.637-010 4.185-010 4.650-010 3.816-010 3.105-010 5.00+003 7.434-010 6.092-010 5.730-010 3.434-010 3.950-010 4.391-010 3.610-010 2.940 010 5.20+003 6.938-010 5.689-010 5.354-010 3.209-010 3.689-010 4.102-010 3.377-010 2.752-010 5.63+003 6.027-010 4.948-010 4.663-010 2.794-010 3.209-010 3.571-010 2.948-010 2.404-010 6.00+003 5.393-010 4.431-010 4.180-010 2.505-010 2.875-010 3.200-010 2.648-010 2.161-010 6.44+003 4.765-010 3.919-010 3.702-010 2.218-010 2.543-010 2.832-010 2.350-010 f.920-010 I I 7.24+003 3.882-010 3.197-010 3.025-010 1.812-010 2.075-010 2.313-010 1.925-010 1.574-010 ]
! 7.50+003 3.658-010 3.013-010 2.852-010 1,708-010 1.956-010 2.180-010 1.815-010 1.485-010 8.05+003 3.247-010 2.675-010 2.533-010 1.517-010 1.736-010 1.935-010 1.612-010 1.319-010 8.50+003 2.959-010 2.438 010 2.309-010 1.383-010 1.582-010 1.764-010 1.469-010 1.203-010 j 9.00+003 2.686-010 2.214 010 2.098-010 1.296-010 1.437-010 1.601-010 1.334-010 1.093-010 9.50+00J 2.451-010 2.020-010 1.915-010 1.147-010 1.311-010 1.461-010 1.218-010 9.981-011 1.00+004 2.247-010 1.852-010 1.757-010 1.052-010 1.202-010 1.340-010 1.117-010 9.158-011 1.21+004 1.645-010 1.356-010 1.288-010 7.708-011 8.795-011 9.804-011 8.180-011 6.712-011 I 1.40+004 1.286-010 1.060-010 1.008-010 6.034-011 6.876-011 7.665-011 6.398-011 5.254 011 !
1.61+0C4 1.020-010 8.415-011 8.013-011 4.794-011 5.457-011 6.083-011 5.080-011 4.175-011 j t.80+004 8.475-011 6.990-011 6.663-011 3.985-011 4.532-011 5.052-011 4.221-011 3.471-011 l l
2.00+004 /7.117-011 5.871-011 5.601-011 3.350-011 3.805-011 4.242-011 3.546-011 2.918-011 l 2.20+004 6.043-011 4.987-011 4.767-011 2.849-011 3.231-011 3.603-011 3.015-011 2.483 011 2.41+004 5.154-011 4.254-011 4.075-011 2.434-011 2.756-011 3.073-011 2.574 011 2.122-011 2.60+004 4.538-011 3.747-011 3.595-011 2.147-011 2.427-011 2.706-011 2.269-011 1.872-011 i 2.80+004 3.997-011 3.302-011 3.173-011 1.094-011 2.138-011 2.384-011 2.001-011 1.652-011 3.22+004 3.144-011 2.600-011 2.508-011 1.496-011 1.683-011 1.876-011 1.580-011 1.306-011 3.40+004 2.858-011 2.366-011 2.286-011 1 362-011 1.530-011 1.706-011 1.439-011 1.191-011 4.02+004 2.136-011 1.772-011 1.722-011 1.025-011 1.145-011 1.277-011 1.083-011 8.986-012 4.20+004 1.983-011 1.647-011 1.603-011 9.533-012 1.064-011 1.186-011 1.007-011 8.366-012 4.83+004 1.564 011 1.303-011 1.274-011 7.564 012 8.399-012 9.352-012 7.985-012 6.648-012 5.00+004 1.474-011 1.230-011 1.203-011 7.143-012 7.921-012 8.815-012 7.537-012 6.279-012 I s 5.63+004 1.194-011 9.999-012 9.829-012 5.828-012 6.428-012 7.145-012 6.149 012 5.137-012 l 5.80+004 1.134-011 9.510-012 9.358-012 5.547-012 6.109-012 6.788-012 5.851-012 4.892-012 6.00+004 1.069-011 8.977-012 8.843-012 5.241-012 5.762-012 6.398-012 5.526-012 4.624 012 6.44+004 9.462-012 7.975-012 7.875-012 4.663-012 5.108-012 5.662-012 4.911-012 4.118-012 7.24+004 7.704-012 6.534-012 6.466-012 3.827-012 4.167-012 4.604-012 4.019*012 3.381-012 j 7.50+004 7.223-012 6.136-012 6.069-012 3.593-012 3.909-012 4.315-012 3.771-012 3.176-012 l l 8.05+004 6.351-012 5.414-012 5.351-012 3.169-012 3.441-012 3.791-012 3.321-012 2.802-012 i 8.50+004 5.750-012 4.918-012 4.856-012 2.877-012 3.119-012 3.429-012 3.010-012 2.544-012 9.00+004 5.190-012 4.453-012 4.394-012 2.604 012 2.817-012 3.091-012 2.719-012 2.303-012 9.50+004 4.714 012 4.060-012 4.003-012 2.372-012 2.562-012 2.803-012 2.472-012 2.097-012 l 1.00+005 4.308-012 3.724-012 3.668-012 2.175-012 2.343-012 2.557-012 2.261-012 1.921-012 CLINTON-I 7-11 Rev.2-10/86
. .. . . . . . . . . . = - -.: .- - - . .
CPS-0DCM r Table 7.2-2 (Continued) l 1
ANNUAL AVERAGE MIXED-h0DE D'/Q April 1975 - April 1976 Distance Sector (meter)
S SSW SW WSW W WNW NW NNW 1.00+002 6.278-008 5.487-008 9.005-008 6.174-008 6.643-008 6.293-008 7.809-008 1.473-007 1 10+002 5.533-008 4.838-008 7.937-008 5.443-008 5.856-008 5.548-008 6.882-008 1.298 007 1.20+002 4.930-008 4.313-008 7.073-008 4.852-008 5.221-008 4.946-008 6.132-008 1.157-007 1.3O+002 4.435-008 3.882-008 6.363-008 4.366-008 4.698-008 4.452-008 5.515-008 1.040 007 1.40+002 4.021-008 3.523*008 5.771-008 3.960-008 4.262-008 4.039-008 5.000-008 9.430-008 1.50+002 3.671-008 3.219-008 5.270-003 3.617-008 3.893-008 3.690-008 4.564-008 8.608-008 1.60+002 3.372-008 2.960-008 1.841-008 3.324-008 3.579-008 3.393-008 4.192-008 7.905-008 1.70+002 3.114-008 2.737-008 4.472-008 3.072-008 3.307-008 3.136-008 3.870 008 7.298-008 1.80+002 2.890-008 2.542-008 4.150-008 2.852-008 3.071-008 2.913-008 3.591 008 6.769-008 1.90+002 2.693-008 2.372-008 3.868-008 2.659-008 2.864-008 2.717-008 3.345 008 6.306-008 2.00+002 2.520-008 2.224-008 3.620-008 2.490-008 2.682-008 2.546-008 3.129-008 5.898-008 2.10+002 2.353-008 2.080-008 3.381-008 2.327-008 2.507-008 2.380-008 2.921-008 5.505-008 2.20+002 2.205-008 1.952-008 3.169-008 2.182-008 2.351-008 2.233-008 2.736-008 5.156-008 2.3O+002 2.072-008 1.837-008 2.979-008 2.052-008 2.212-008 2.101-008 2.571-008 4.844-008 2.40+002 1.953-008 1.735-008 2.808-008 1.936-008 2.087-008 1.983-008 2.422-008 4.564-008 2.50+002 1.846-008 1.643-008 2.654-008 1.831-008 1.974-008 1.877-008 2.288-008 4.310-008 2.60+002 1.749-008 1.559-008 2.515-008 1.736-008 1.872-008 1.781-008 2.167-008 4.081-008 2.70+002 1.661-008 1.484-008 2.389-008 1.650-008 1.780-008 1.694-008 2.056-008 3.873-008 2.80+002 1.5e0-008 1.415-CO8 2.273-008 1.571-008 1.696-008 1.615-008 1.956-008 3.683-008 2.90+002 1.506-008 1.352-008 2.168-008 1.500-008 1.619-008 1.542-008 1.863-008 3.509-008 3.00+002 1.439-008 1.295-008 2.071-008 1.434-008 1.549-008 1.476-008 1.779-008 3.349-008 3.20+002 1.310-008 1.183-008 1.887-008 1.307-008 1.413-008 1.347-008 1.618-008 3.046-008 1 3.40+002 1.201-008 1.088-008 1.729-008 1.199-008 1.296-008 1.238-008 1.481-008 2.788-008 j 3.60+002 1.106-008 1.006 008 1.593-008 1.107-008 1.197-008 1.143-008 1.363-008 2.565-008 i 3.80+002 1.024-008 9.349-009 1.475-008 1.026-008 1.110-008 1.062-008 1.261-008 2.372-008 ,
4.00+002 9.523-009 8.729-009 1.372-008 9.554-009 1.034-008 9.901-009 1.171-008 2.202-008 4.20+002 8.892-009 8.184-009 1.281 008 8.934-009 9.676-009 9.272-009 1.092-008 2.053 008 4.40+002 8.334-009 7.703-009 1.200-008 8.386-009 9.086-009 8.716-009 1.022-008 1.921-008 4.60+002 7.837-009 7.275-009 1.129-008 7.899-009 8.562-009 8.223-009 9.597-009 1.804-008 4.80+002 7.394-009 a 494-OO9 1.065-008 7.464-009 8.094-009 7.782-009 9.039-009 1.699-008 1 5.Ov+002 6.996-Oct ' 453-00^ 1.008-008 7.073-009 7.675-009 7.386-009 8.539-009 1.604-008 5.20+002 6.598-000 6.'93-009 1 9.500-009 6.676-009 7.244-009 6.975-009 8.044-009 1.511-008 5.4C+002 6.237-009 5.866-009 8.97P-OO9 6.316-009 6.853-009 6.603-009 7.596-009 1.426-008 5.60+002 5.909-009 5.570-009 8.504-009 5.989-009 6.499-009 6.264-009 7.189-009 1.350-008 5.80+002 5.611-009 5.299-009 8.072-009 5.691-009 6.175-009 5.955-009 6.818-009 1.280-008 l 6.00+002 5.338-009 5.051-009 7.677-009 5.418-009 5.879-009 5.672-009 6.479-009 1.216-008 l 6.50+002 4.749-009 4.516-009 6.824-009 4.831-009 5.239-009 5.062-009 5.747-009 1.078-008 I 7.00+002 4.268-009 4.078-009 6.126-009 4.350-009 4.716-009 4.561-009 5.147-009 9.644-009 7 0+002 3.855-005 3.693-009 5.526-009 3.933-009 4.261-009 4.124-009 4.637-009 8.683-009 8 i+002 3.479-009 3.341 009 4.978-009 3.553-009 3.846-009 3.725-009 4.171-009 7.805-009
- 8. )+002 3.214-009 3.094-009 4.593-009 3.286-009 3.553-009 3.444-009 3.843-009 7.187-009 9.00+002 2.962-009 2.857-009 4.226-009 3.031-009 3.274-009 3.176-009 3.531-009 6.597-009 9.50+002 2.745-009 2.653-009 3.908-009 2.811-009 3.033-009 2.944-009 3.260-009 6.087-009 1.00+003 2.555-009 2.474-009 3.632-009 2.620-009 2.822-009 2.742-009 3.025-009 5.642-009 1.10+003 2.198-009 2.130-009 3.116-009 2.256-009 2.424-009 2.356-009 2.590-009 4.82h009 1.20+003 1.918-009 1.860-009 2.712-009 1.971-009 2.112-009 2.054-009 2.251-009 4.189-009 1.3O+003 1.695-009 1.644-009 2.389-009 1.743-009 1.863-009 1.812-009 1.979-009 3.679-009 1.40+003 1.514-009 1.469-009 2.127-009 1.557-009 1.660 009 1.616-009 1.759-009 3.265-009 1.50+003 1.364-009 1.324-009 1.911-009 1.405-009 1.493-009 1.454-009 1.578-009 2.924-009 1.61+003 1.229-009 1.192-009 1.715-009 1.267-009 1.341-009 1.307-009 1.413-009 2.616-009 CLINTON-1 7-12 Rev.2-10/86 l
w_____
_ .u.-
C?S-0DCM
. Table 7. 2-2 (Continueci)
ANNUAL AVERAGE MIXED-MODE D/Q April 1975 - April 1976 Distance Sector (meter)
S SSW SW WSW W WNW NW NNW .j 1.80+003 f.045-009 1.013-009 1.448-009 1.078-009 f.134-009 1.107-009 1.189-009 2.195-009 2.00+003 9.014-010 8.731-010 1.240-009 9.313-010 9.728-010 9.506-010 1.014-009 1.866-009 2.20+003 7.748-010 7.494-010 1.062-009 8.010-010 8.333-0 T 8.146-010 8.666-010 1.592-009 2.41+003 6.695-010 6.466-010 9.139-010 6.926-010 7.174-0f0 7.016-010 7.442-010 1.365-009 2.60+003 5.963-010 5.752-010 8.112-010 6.171-010 6.369-010 6.232-010 6.594-010 1.208-009 2.80+003 5.317-010 5.121-010 7.206-010 5.505-0f0 5.660-010 5.540-010 5.847-010 1.069-009 3.00+003 4.783-010 4.600-0f0 6.459-010 4.954-010 5.074-010 4.970 010 5.232-010 9.551-010 3.22+003 4.271-010 4.107-010 5.757-010 4.425-010 4.524-010 4.433-010 4.658-010 8.497-010 3.60+003 3.569-010 3.430-010 4.796-010 3.699-010 3.770-010 3.697-010 3.873-010 7.058-010 l 4.02+003 2.989-010 2.870-010 4.003-010 3.098-010 3.148-010 3.389 Tto 3.227-010 5.873-010 i
4.40+003 2.593-010 2.488-010 3.462-010 2.688-0f0 2.724-010 2.675-010 2.787-010 5.067-010 l
4.83+003 2.238-010 2.147-010 2.980-010 2.321-010 2.345-010 2.305-010 2.395-010 4.350-010 5.00+003 2.118-010 2.031-010 2.817-010 2.197-010 2.217-010 2.179-010 2.262-010 4.107-010 5.20+003 1.981-010 1.900-010 2.633-010 2.055-010 2.073-010 2.038-010 2.114-010 3.836-010 ;
5.63+003 1.728-010 1.659-010 2.294-010 1.794-010 1.807-010 1.778-010 1.840-010 3.338-010 f 6.00+003 1.552-010 1.490-010 2.058-010 1.611-010 1.622-010 1.596-010 1.649-010 2.990-010 6.44+003 1.377-010 1.323-010 1.824-010 1.430-010 1.438-010 1.416-010 1.460-010 2.646-010 7.24+003 1.127-010 1.084-010 1.491-010 1.172-010 1.177-010 1.160-010 1.193-010 2.160-010 7.50+003 1.063-010 1.023-010 1.406-010 1.105-010 1.110-010 1.094-010 1.124-010 2.036-010 8.05*oO3 9.443-011 9.092-011 1.249-010 9.814-011 9.860-011 9.721-011 9.983-011 1.808-010 8.50+003 8.612-011 8.296-011 1.139-010 8.950-011 8.993-011 8.869-011 9.101-011 1.649-010 9.00+003 7.823-011 7.541-011 1.034-010 8.130-011 8.170-011 8.090-011 8.264-011 1.497-010 9.50+003 7.143-011 6.890-011 9.444-011 7.423 011 7.461-011 7.363-011 7.544-011 1.367-010 1.00+004 6.553-011 6.324-011 8.663-011 6.810-011 6.846-011 6.757-011 6.918-011 1.254-010 1.21+004 4.801-011 4.646-011 6.348-011 4.991-011 5.021-01, 4.962 011 5.066-011 9.184 011 1 1.40+004 3.757-011 3.643-011 4.969-011 3.908-011 3.934-011 3.890-011 3.963-011 7.186-011 1.61+004 2.985-011 2.900-011 3.948-011 3.105-011 3.128-011 3.095-011 3.147-01t 5.708-011 1.80+004 2.481-011 2.414-011 3.282-011 2.581-011 2.602-011 2.576-011 2.615-011 4.744-011 2.00+004 2.085-011 2.032-011 2.758-011 2.170-011 2.188-011 2.168 011 2.197-011 3.986-011 2.20+004 1.772-011 1.733-011 2.346-011 f.846-011 1.863-011 1.848-011 1.866-011 3.387-011 2.41+004 1.513-011 1.484-011 2.004-011 1.577-011 1.594-011 1.582-011 1.593-011 2.591-011 2.60+004 1.333-011 1.311-011 1.767-011 1.391-011 1.407-011 1.398-011 1.403-011 2.80+004 1.175-011 2.548-011 1.159-011 1.558-011 1.227-011 1.242-011 1.235-011 1.236-01t 2.245-011 3.22+004 9.273-012 9.200-012 f.230-011 9.698-012 9.834-012 3.40+004 9.795-012 9.748-012 1.770-011 8.444-012 8.401-012 1.120-011 8.839-012 8.969-012 8.941-012 8.872-012 1.610-011 4.02+004 6.343-012 6.365-012 8.411-012 6.659-012 6.774-012 6.770-012 6.659-012 4.20+004 1.207-011 5.899-012 5.933-012 7.222-012 6.198-012 6.310 012 6.311-012 6.194-012 1.122-011 4.83+004 4.672-012 4.735-012 6.191 012 4.926 012 5.029 012 5.043-012 4.917-012 5.00+004 8.877-012 4.410-012 4.478-012 5.841-012 4.655 012 4.756-012 4.772-012 4.6#7-012 8.378-012 5.63+004 3.595-012 3.677 012 4.755-012 5.20+004 3.421-012 3.809-012 3.900-012 3.924-012 3.797-012 6.815-012 3.505-Oi2 4.522-012 3.628-012 3.717 012 3.742-012 3.616-012 6.482-012 6.00+004 3.231-012 3.317-012 4.268-012 3.431-012 3.518-012 3.544-012 3.4t9-012 6.44+004 6.118-Ot2 2.872-012 2.961-012 3.788-012 3.059-012 3.142-012 3.171-012 3.050-012 7.24+004 2.441 012 5.434-012 2.354-012 3.093-012 2.518-012 2.594-012 2.626-012 2.521-012 4 452-012 7.50+004 2.212-012 2.293-012 2.901 012 2.366-012 2.439-012 2.471-012 2.372-012 8.05+004 1.952-012 2.026-012 4.182-012 2.552 012 2.091-012 2.157-012 2.189 012 2.104-012 3.691-012 8.50+004 1.773-012 1.841 012 2.311-012 1.901-012 9.00+004 1.605-012 1.963 012 1.994-J12 1.919 012 3.353 012 1.668 012 2.086 012 1.723-012 1.781-012 1.812-012 1.746-012 3.036-012 9.50+004 1.463 012 1.521-012 1.895-012 1.572-012 1.628-012 1.658-012 1.600-012 1.00+005 1.341-012 1.395-012 2.768-012 f.731-012 1.444-012 1.496-012 1.526-012 1.476-012 2.538-012 CLINTON-I 7-13 Rev.2-10/86
Release Point Diameter (m) 3.77* 0.44 l Annual Average Flow Rate (m3/sec) 111.71 1.89 l
Vertical Exit Velocity (m/sec) 10.02 12.49 j' "Erf ective 2(A/ n) ciameter CLINTON-I 7-15 Rev.2-10/86 i
. . ~- _ .- .Z i._: . _. .
m..__._ _
CPS-0DCM TABLE 7.2-5 SITE BOUNDARY DISPERSION AND DEPOSITION PARAMETERS Sector Distance Release Point XTQ Release Point D7Q (mile / meter) (sec/m )3 (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 WSW 2.1/3414 1.307E-7 1.307E-7 4.053E-10 4.053E-10 W 1.4/2256 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~. 5 78E- 9 1.578E-9 LNW l.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 Inhalation 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 N No milking cows within 5 mile radius of CPS
- 3.11.2.3 Goat Milk N No milking goats within 5 mile radius of CPS
- 3.11.2.3 Cow Meat N No meat animals identified in annual census **
3.11.2.3 Vegetation N Notes
- Assumes a milking animal resides at a distar.ce of 4.5 miles from CPS in the worst case sector as stated on page 30 of NUREG-0133.
- Assumes a cow meat animal is located at a distance of 4.5 miles from CPS in the worst case sector.
CLINTON-I 7-16 Rev.2-10/86
. . . .a .x -. L _ .- . 2.. , , . ~ .
CPS-ODCM 7.3 Concurrent Meteorological Data Processing Meteorological data is acquired and processed through a model which utilizes bi-level hourly meteorological tower data or single level joint frequency data to perform the required analysis. Three distinct release modes are treated: elevated, ground and mixed. A set of five output arrays are generated for each dose receptor location as follows:
Relative undecayed, undepleted plume concentration (X/Q)
Relative decayed and depleted radiciodine and i particulate concentration (D2DPXQ) i Relative decayed noble gas concentration (DlXQ)
Relative particulate and radiciodine deposition (D/Q)
Standard deviations of the undecayed, undepleted plume concentrations Since the Regulatory Guide 1.111 depletion and deposition curves are defined only within the range encompassing 100 to 200,000 meters, analysis results are not considered valid outside this range. The following sections describe the calculations performed by the transport and dispersion model for a one hour time interval.
7.3.1 Determination of Pasquill Stability Class The Pasquill Stability Class is determined by categorizing the temperature gradient, AT, into one of several ranges between I
-0.900 and 0.900 C/ meter according to the following equation:
aT=T U
-T t , *C/ meter (5) l H
U
-N L CLINTON-I 7-17 Rev.2-10/86
~
.. . . _ . . . v : b._
1 l
CPS-00CM l 1
l with the requi ement that I
- is restricted to-values I < (3) z (0 3).
7.3.6 Calculation of Momentum Plume Rise ]
1 For elevated or mixed-mode releases only, the amount of plume rise due to the initial vertical momentum of the exhausted effluent, AH, is calculated. For Pasquill stability l classes A,B,C and D, oH is calculated per section 7.3.6.1; for classes E,F and G, 1 section 7.3.6.2 is used.
7.3.6.1 AH For Pasquill Class A,B,C and D' H is calculated using both equations (17) and (18) and the minimum value is selected for-use. In addition, when the vertical exit l velocity, EXITV, is less than 1.5 times the l horizontal windspeed, STACWS, a downwash l correction is subtracted from equation (17) per equation (19).
l AH1= 1.44(STACD)(EXITV/STACWS) /3 (17)
(X/STACD)1/3-DOWNWASH, meter aH2 = 3.0 (STACD)(EXITV/STACWS), meter (18)
DOWNWASH = 3.0(STACD)(1.5-EXITV/STACWS), meter (19) where !
STACD = Internal release point stack diameter
= 3.77 meters (HVAC Exhaust Stack)
= 0.44 meters (SGTS Exhaust Stack) l EXITV = Stack exit velocity, meter /second i All other parameters are as defined previously.
7.3.6.2 oH For Pascuill Class E,F and G 1
aH is determined by selecting the minimum value calculated by equations (17) and (18) above and equations (20) and (21) below:
l AH3 = 4.0 ((0.5(EXITV)(STACD)) /S)b, meter (20) j aH4 = 1.5 [(0.5(EXITV)(STACD)) /STACWS]1/3(g)-1/6 , (21) meter l
CLINTON-I 7-21 Rev.2-10/86
- - .. . w2 z. -
CPS-0DCM S*J Value X C DPSF 5 X < 10'0 0 X 2100 C=1 calculated 6 X <100 0 X >100 C=8 calculated 7 X 7100 0 X 2100 C = 29 calculated 8 X <100 0 X >100 C = 50 calculated 10 al'1 X 0 12 X <100 0 X >100 C = 15 calculated 14 X 7 120 0 X 2120, C = 36 .- calculated 15 all X 0 16 X <210 0 X >210 C = 57 calculated ,
18 X 72900 0 X >2900 C = 22 calculated 21 X 726,000 0 X 226,000 C = 43 calculated 24 all X 0 DPSF is calculated using the value for C and equations (24), (25), and (26):
Y DPSF = 10 /(0.392699X) (25)
Y = A(C) + A(C+1)d + A(C+2)d2 + A'(C+3)d3 (26) l
+ A(C+4)d0 + A(C+5)d5 + A(C+6)d6 CLINTON-1 7-26 Rev.2-10/86
CLINTON POWER STATION SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT February 27, 1987 - June 30, 1987 ATTACHMENT B SOLIDIFICATION VENDOR PROCEDURE / DOCUMENT APPROVAL
l f
l ATTACHMENT B-PROCEDURE / DOCUMENT APPROVAL COVER SHEET
- 1) Document Approval Cov're Sheet
- 2) FRG Meeting Minutes; June 15, 1987 i
i
~ * ' ~ \ .
. ATTACHME:NT B,,,
<.? . -
/1 CLASS CODE: SNQD1
( CPS No.1913.03F001 (Rev. 1)
SOLIDIFICATION VENDOR PROCEDURE / DOCUMENT APPROVAL COVER SHEET TITLE: Process Control Program ATI Transportable Volume Reduction System TVR III for -
Clinton Power Station
' Illinois Power Company Rev. 3 MAINTENANCE DEPARTMENT .......... .
/
Signatur Date CHEMISTRY GROTIP.................. b Signacure' p ' --- / [//5/f 7
~
e Date TECHNICAL DEPARTMENT ............ #/
/
S igna tur e- Date
^
NUCLEAR STATION f ENGINEERING DEPARTMENT........... .cf A /6 . R~f
. . ._- Signaturf. 2 _ ] Dpte RADIATION PROTECTION DEPARTMENT . / /
I Signature Date 7
/7(WA / /a QUALITY ASSURANCE DEPARTMENT .... / S-/S - 7 7 Signature Date RADWASTE GR0UP................... /b/
Sig
[ ~e/ / / t - /i'- 6 7 Date FACILITY REVIEW GROUP............ )V ._ . /6-/F4~7 Signature Date Page 1 of 1 a.
.\
\ -
' , . FACILITY REVIEW GROUP MEETING _ MINUTES.87-164 -
?) . 06/15/87
~
4:00 p.m. ~
DISTRIBUTION: W. C. Gerstner, B-13 -
D. P. Hall, V-275 E. J. Corrigan, V-923/R. E. Campbell NRC Site Resident Office, V-690 J. W. Wilson, T-31 .
J. G. Cook, T-31 T. J. Camilleri, T-31
' R. F. Schaller, T-31 E. A. Schweitzer, T-31 R. W. Morgenstern, T-31 .-
J. D. Palmer, T-31 ~- "
D. W. Hillyer, T-31 S. H.. Daniel, T-31 -
L. O. Clark, T-31 R. S. Richey, T-31 .
C. H. Mathews, V-130A R. P. Bichel, T-31 W. M. Clark, T-31 '
F. L. Wolking, T-31 -
P. D. Yocum, T-31 -
, J. R. Hays, T-31
). M. A. Vhnderdvde, .-}l'.
R. E. Crapo, T-31 L. R. Rippy, T-31 M. P. Hedges, T-31 -
R. F. Orthen, T-31 -
R. B. Bedford, T-31 ~~.
R. A. Hoem, T-31 ~
D. R. Vincent, V-130D M. A. Kaczor, V-920 -
J. F. Palchak, T-31 J. F. Hampton, V-928 'i P. G. Breezeel V-920 P. E. Walberg, V-920 T. E. Feriozzi/W. T. Donovan, T-31
. Compliance, T-31 3, . -
SPECIAL MIETING ,
Date Distributed 06/24/87 r
s u,. mm _ _ _ - - - . . .
. l
. . , . .. . . ,... .. .a . . . e..
_.. ,. FACILITY REVIEW GROUP MvETING'. ' ' '
. . '87-164 . .!
-f'N' ' '
6/15/87 ~
4:00 p.m.
Members Present:
- J. G,.. Cook.(Assistant Manager - CPS / Chairman)
T. J. Camilleri (Assistant Manager --Maintenance)
R. F. Schaller (Assistant Manager - Operations)
R. W. Morgenstern (Technical) .
E. A. Schweitzer (Nuclear)
Members Absent:
J. D. Palmer (C&I)
- D. W. Hillyer (Radiation..Protecti*n) o . j S. H. Daniel (Chemistry) - -!
Others.Present: -
~ ~-
.c '
. ;l L. O. Davis (Compliance) . ,
SUMMARY
l 1 Plant Modification was approved. , _
! 1 Process Control Program procedure was recommended f6r approval.
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FRG Meg.~87-16'4 ~ ' '
June 16, 1987' ~
.u ' -l P. age 2 . I The Chairman (J. G. Cook) opened this meeting to~c.onsider one plant modification and one Process Control Program procedure. A poll was conducted to ensure a quorum was present. . .
Since a quorum existed, no attempt was made to reach any other FRG -
representatives.
NOTE: All approvals and recommendations for approval indicate no unreviewed safety questions existed.
The first item.of. discussion was the fo'llowing plant modification.
Copies.were passed out at the meeting. Time was allowed f6r all to "
review. It was reviewed for an unreviewed. safety guestion. .
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l SA-7 .
l The service air compressors have been run with their automatic unloading capability disabled for an indeterminately long period, because they unloaded and loaded too often in the system engineer's judgment (approximately 1 change / minute). This configuration, which is (i
documented on temporary modification 86-97, uses more power and imposes -
i more wear on the inlet and by7 ass throttling valves, but avoids the l
r' repeated valve stroking and the torsional, vibrational, thermal, and I (,,T/ other transients associated with repeated loading and unloadings, and is capable of maintaining essentially constant pressure.
This modification: 1) Accepted'the current configurat' ion for permunent ;
use. (
Reference:
Temporary modification 86-97); and 27 Installed SPST y switches in series between the lifted leads and terminal 13 of relay- .
i 8CR, which would allow switching between the two modes of operation. .
Approved.
I The following Process Co,ntrol Program procedure was discussed next.
l Copies were passed out at the meeting. Time was allowed for all to It was reviewed for an unreviewed safety question. '
review.
Process Control Program Transportable Volume Reduction System TVR III, Rev. 3 -
Scope of Revision: The Process Control Program (PCP) procedure provides ~f I a method by which radioactive waste solidification is controlled and l assured. The process Control Program Procedure is being changed to- "
allow Clinton Power Station Chemistry. group the flexibility to determine the specific analytical details, of their procedures, for radwaste ,
processing. Requirements to obtain samples prior to flushin have been -
removed where possible. A calculation to correct for added lushwater has been placed in the concentrates Rortion of the PCP. Minor changes to allow Associated Technologies' operators flexibility to determine ;)
operational details of their procedures has also been made.
R. Schaller (Assistant Manager - Operations) explained this procedure to e
the committee.
Recommended for approval.
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June 16, 1987 .
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j R. Morgenstern (Technical) requested that a 10:00 a.m. special meeting be scheduled tomorrow to consider one temporary. modification and one l plant modification. The Chairman (J. G. Cook) agreed to this and requested that'L. Davis (Cc=pliance)'to schedule a meeting for this q r time. -
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l The Chairman adjourned this meeting.
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- Perrormed by: l-t l .
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1 U-601018 L30-87 (08-28 )-L 1A.120
/LLINDIS POWER OOMPANY IP CLINTON POWER STATION, P.o. BOX 678. CLINTON. ILLINots 61727 August 28, 1987 10CFR50.36a FRICnITY ROUMNG
,[ .pd._._pt mL Docket No. 50-461 4/q) .. _f
- o n i
l A. B. Davis <
Regional Administrator & l- --
Region III d[g U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
)
Subject:
Clinton Power Station Semiannual Radioactive Effluent Release Report
Dear Sir:
Attached is the Semiannual Radioactive Effluent Release Report for Clinton Power Station for the period February 27 - June 30, 1987 This submittal is provided in accordance with the requirements of section 6.9.1.7 of the Clinton Power Station Technical Specifications.
If you have any questions or require additional information, please contact me.
Sincerely yours, F. A. Sp enbe , III Manager - Licinsing and Jafety SFB/ckc Attachment cc: Director of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington D.C. 20555 NRC Resident Office B. L. Siegel, NRC Clinton Licensing Project Manager W
TAUG 311987 /q 64 T t\t
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