U-603953, 2009 Annual Radioactive Effluent Release Report

2009 Annual Radioactive Effluent Release Report

ML101320286
Person / Time
Site:	Clinton
Issue date:	04/28/2010
From:	Kanavos M Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
U-603953
Download: ML101320286 (305)

Text

Exelkn, Nuclear Clinton Power Station 8401 Power Road Clinton, IL 61727 10CFR50.36a U-603953 April 28, 2010 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555-0001 Clinton Power Station Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Clinton Power Station 2009 Annual Radioactive Effluent Release Report In accordance with Technical Specification requirement 5.6.3, Exelon Generating Company, LLC (Exelon) is submitting the 2009 Annual Radioactive Effluent Release Report for Clinton Power Station. This report covers the period from January 1, 2009 through December 31, 2009. This report provides the results of Section 7.2 of the Offsite Dose Calculation Manual.

There are no commitments contained in this letter.

Respectfully, Mark E. Kanavos Plant Manager Clinton Power Station EET/SIS/blf Attachment cc: Regional Administrator, Region III NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency 4009L

Exeltan Nuclear January 1, 2009 - December 31, 2009 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CLINTON POWER STATION - DOCKET NUMBER 50-461 Prepared by:

Clinton Power Station

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TABLE OF CONTENTS SECTION TITLE PAGE 1 Executive Summary 5 2 Introduction 6 3 Supplemental Information 12 4 Radioactive Effluent Data 17 5 Solid Waste Disposal Information 28 6 Dose Measurements and Assessments 32 7 Meteorological Data and Dispersion Estimates 43 8 ODCM Operational Remedial Requirement Reports 103 9 Changes to Radioactive Waste Treatment Systems 104 10 New Locations for Dose Calculation and / or Environmental 105 Monitoring 11 Corrections to Data Reported in Previous Reports 108 12 Changes to the Offsite Dose Calculation Manual 109

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LIST OF TABLES TABLE NUMBER TITLE PAGE Gaseous Effluents - Summation of All Releases 17 1 1A Air Doses Due to Gaseous Releases 18 0 1B Doses to a Member of the Public Due to Radioiodines, 18 Tritium and Particulates in Gaseous Releases 2 Gaseous Effluents - Nuclides Released 19 3 Radioactive Gaseous Waste LLD Values 20 4 Waterborne Effluents - Summation of All Releases 22 5 Waterborne Effluents - Nuclides Released 23 6 Radioactive Liquid Waste LLD Values 24 7 Solid Waste and Irradiated Fuel Shipments 28 8 Maximum Offsite Doses and Dose Commitments to Members of the Public In Each Sector Calculated Doses to Members of the Public During Use of the 9 Department of Natural Resources Recreation Area in the East- 36 Southeast Sector within the CPS Site Boundary 10 Calculated Doses to Members of the Public During Use of the Road in 37 the Southeast Sector within the CPS Site Boundary 11 Calculated Doses for the Residents in the South-Southeast Sector 38 within the CPS Site Boundary 12 Calculated Doses for the Residents in the Southwest Sector within the CPS Site Boundary Calculated Doses to Members of the Public During Use of the 13 Agricultural Acreage in the South-Southwest Sector within the CPS 40 Site Boundary 14 Calculated Doses for the Residents in the West-Southwest Sector 41 within the CPS Site Boundary 15 Calculated Doses to Members of the Public During Use of Clinton 42 Lake in the Northwest Sector within the CPS Site Boundary 16 Meteorological Data Availability 44 17 Classification of Atmospheric Stability 45 18 Joint Wind Frequency Distribution by Stability Class 46

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I I LIST OF FIGURES FIGURE TITLE PAGE i' NUMBER N I CPS Airborne Effluent Release Points 7

.12 CPS Waterborne Effluents Release Pathway 8

• 3 Effluent Exposure Pathways 11 4 Areas Within the CPS Site Boundary Open to Members of the Public 35 J) p 4, ii tliI I

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SECTION 1 EXECUTIVE

SUMMARY

The Annual Radioactive Effluent Release Report is a detailed description of gaseous and liquid radioactive effluents released from Clinton Power Station [CPS] and the resulting radiation doses for the period of January 1, 2009 through December 31, 2009. This report also includes a detailed meteorological section providing weather history of the surrounding area during this period. This information is used to calculate the offsite dose to our public.

The report also includes a summary of the amounts of radioactive material contained in solid waste that is packaged and shipped to a federally approved disposal

/ burial facility offsite. Additionally, this report notifies the U.S. Nuclear Regulatory Commission [NRC] staff of changes to CPS's Offsite Dose Calculation Manual [ODCM]

and exceptions to the CPS effluent monitoring program that must be reported in accordance with ODCM Remedial Requirements 2.7.1.b and 3.9.2.b.

The Report also includes a summary of events that are to be included per ODCM Remedial Requirements.

The NRC requires that nuclear power facilities be designed, constructed, and operated in such a manner as to maintain radioactive effluent releases to unrestricted areas As Low As Reasonably Achievable [ALARA]. To ensure compliance with this criterion, the NRC has established limitations governing the release of radioactivity in effluents.

During 2009, CPS operations were well within these federally required limits.

The maximum annual radiation dose delivered to the inhabitants of the area surrounding CPS - due to radioactivity released from the station - was 1.05E-03[or 0.00105] mR [milli-Roentgen]. The radiation dose to the public in the vicinity of CPS was calculated by using the concentration of radioactive nuclides from each gaseous effluent release coupled with historical weather conditions. The dose from CPS gaseous radioactive effluents was only a small fraction of the limit for the maximum exposed member of the public. There were no liquid effluent releases in 2009. As such, there was no dose received by the public from the liquid radioactive effluent pathway.

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SECTION 2

- 'INTRODUCTION CPS is located in Harp Township, DeWitt County approximately six (6) miles east of the city of Clinton in east-central Illinois. CPS is a -1,140 megawatt gross electrical power output boiling water reactor. Initial fuel load commenced in September of 1986 with initial criticality of the reactor occurring on February 27, 1987.

Commercial operation commenced in April 1987 and the reactor reached 100% power for the first time on September 15, 1987.

CPS releases airborne effluents via two (2) gaseous effluent release points to the environment. They are the Common Station Heating, Ventilating, and Air Conditioning [HVAC] Vent and the Standby Gas Treatment System [SGTS] Vent [see Figure 1]. Each gaseous effluent release point is continuously monitored consisting of a surveillance program of periodic sampling and analysis as specified in the ODCM.

3CPS is licensed to release radioactive liquid effluents in a batch mode, however there were no radioactive liquid releases in 2009 at CPS. Each release would have been sampled and analyzed prior to release. Depending upon the amount of activity in ft* a release, liquid effluents would vary from 10 to 300 gallons per minute [GPM]. This volume is then further combined with both Plant Service Water flow [a minimum of approximately 5,000 GPM] along with Plant Circulating Water flow [0 to 567,000 GPM]

in the seal well, just prior to entering the 3.4 mile discharge flume into Lake Clinton

[see Figure 2].

II Processing and Monitoring CPS strictly controls effluents to ensure radioactivity released to the environment is maintained ALARA and does not exceed federal release limit criteria.

Effluent controls include the operation of radiation monitoring systems within the plant as well as an offsite environmental analysis program. In-plant radiation monitoring

• systems are used to provide a continuous indication of radioactivity in effluent streams.

- Some are also used to collect particulate and radioiodine samples. Radioactive effluent related samples are analyzed in a controlled laboratory environment to identify the specific concentration of those radionuclides being released. Sampling and analyses provides for a more sensitive and precise method of determining effluent composition to complement the information provided by real-time radiation monitoring

• j instruments.

• i Beyond the plant itself, a Radiological Environmental Monitoring Program

[REMP] is maintained in accordance with Federal Regulations. The purpose of the REMP program is to assess the radiological impact on the environment due to the operation of CPS. Implicit in this charter is the license requirement to trend and assess radiation exposure rates and radioactivity concentrations that may contribute to dose to the public. The program consists of two phases; pre-operational and operational.

During the pre-operational phase of the program, the baseline for the local radiation environment was established. The operational phase of the program includes the II,. objective of making confirmatory measurements to verify that the in-plant controls for the release of radioactive material are functioning as designed. Assessment of the operational impact of CPS on the environment is based on data collected since initial 1'i criticality of the reactor.

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I I Figure 1 CPS AIRBORNE EFFLUENT RELEASE POINTS I

,I I

I I'

- - __n I Release Point Height (feet)

HVAC Exhaust Vent 200 SGTS Exhaust Vent 200 I Building Height (feet)

Release Point Geometry 190 Duct 190 Pipe Release Point Area (ft 2 ) 120 2 1 Release Point Diameter (feet) 12* 1 Annual Average Flow Rate (ft 3/sec) 2,738 73 Vertical Exit Velocity (feet/sec) 33 41

• Effective 2(A/7)2 diameter

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Figure 2 CPS WATERBORNE EFFLUENTS RELEASE PATHWAY PLANT SERVICE WATER (AT LEAST 5000 GPM)

LIQUID RADWASTE DISCHARGE UNE

/

(10-60 OR 60-3 GPM)

.RADIATION MONITOR N.AiA(RKIP SETPOMK CMJAJMCiE WAED ON4 EACH WWIC ISOTrOMI ANALYSIS MN I4 ISOLATION VALVE 1TRM.O. E ON HOWi RELEA* PAI IGH REE OWRAEM OR LOW 0 COMPOSITE SAMPLER CODUEMr1 ARPRO)MITELY 20 W EVERY 60 IMS FROM 'flE DISCAGE RIJIE FOR IJONTWY ANAYSIS SEALWELL LAKE P L ANT CIRCULATING = CLINTON WATER (0-567.000 GPM) DISCHRG FUME

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Exposure Pathways A radiological exposure pathway is the vehicle by which the public may become exposed to radioactivity released from nuclear facilities. The major pathways of concern are those that could cause the highest calculated radiation dose. These pathways are determined from the type and amount of radioactivity released, the environmental transport mechanism, and how the plant environs are used (i.e.,

residence, gardens, etc.). The environmental transport mechanism includes the historical meteorological characteristics of the area that are defined by wind speed and wind direction. This information is used to evaluate how the radionuclides will be distributed within the surrounding area. The most important factor in evaluating the exposure pathway is the use of the environment by the public living around CPS.

Factors such as location of homes in the area, use of cattle for milk, and the growing of gardens for vegetable consumption are important considerations when evaluating exposure pathways. Figure 3 illustrates the effluent exposure pathways that were considered.

The radioactive gaseous effluent exposure pathways include direct radiation, deposition on plants and soil, and inhalation by animals and humans. The radioactive liquid effluent exposure pathways include fish consumption and direct exposure from Clinton Lake.

Dose Assessment Whole body radiation involves the exposure of all organs in the human body to ionizing radiation. Most naturally occurring background radiation exposures consist of whole body exposure although specific organs can receive radiation exposure from distinct radionuclides. These radionuclides enter the body through inhalation and ingestion and seek different organs depending on the nuclide. For example, radioactive iodine selectively concentrates in the thyroid, radioactive cesium collects in muscle and liver tissue, and radioactive strontium in mineralized bone.

The total dose to organs from a given radionuclide also depends on the amount of activity in the organ and the amount of time that the radionuclide remains in the body. Some radionuclides remain for very short periods of time due to their rapid radioactive decay and / or elimination rate from the body, while others may remain longer.

Radiation dose to the public in the area surrounding CPS is calculated for each release using historical weather conditions coupled with the concentrations of radioactive material present. The dose is calculated for all sixteen geographical sectors surrounding CPS and includes the location of the nearest residents, vegetable gardens producing broad leaf vegetables and dairy animals in all sectors. The calculated dose also uses the scientific concept of a "maximum exposed individual" and "standard man", and the maximum use factors for the environment, such as how much milk an average person consumes and how much air a person breathes in a year.

Section 6 contains more detailed information on dose to the public.

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Gaseous Effluents Gaseous effluent radioactivity released from CPS is classified into two (2) categories. The first category is noble gases. The second category consists of 1131, 3

1133, H , and all radionuclides in particulate form with radioactive half-lives greater than eight (8) days. Noble gases - such as xenon and krypton - are biologically and chemically non-reactive. As such, these radionuclides - specifically Kr8sm , Xe'l and Xe135 - are the major contributors to external doses. Halogens 1131 and 1133 , H3 and radionuclides in particulate form with radioactive half-lives greater than eight (8) days are the major contributors to internal doses.

Liquid Effluents Liquid effluents may originate from two (2) sources at CPS. The first is effluent from the Radioactive Waste Treatment System. This water is demineralized prior to release. Samples are taken after the tank has been allowed to adequately recirculate.

The second is from heat exchanger leaks found in closed cooling water systems that service radioactively contaminated systems. This would be considered an abnormal release. As a matter of station management commitment, CPS strives to be a zero (0) radioactive liquid release plant. The last liquid release occurred in September of 1992.

Solid Waste Shipments To reduce the radiation exposure to personnel and maintain the federally required ALARA concept, the NRC and the Department of Transportation [DOT] have established limits on the types of radioactive waste and the amount of radioactivity that may be packaged and shipped offsite for burial or disposal. To ensure that CPS is complying with these regulations, the types of waste and the radioactivity present are reported to the NRC.

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FIGURE 3 EFFLUENT EXPOSURE PATHWAYS 3I II RLEASES DILUTED BY ATMOSPHERE.

£ II

/

ANIMALS RAEABES CLINTON POWER (MILK, MEAT) PLUME EXPOSURE STATION AND INHALATION II CONSUMED ow. nfl~%ft =

U! LIQUID RELEASES t

PEOPLEN II II CONSUMEE BY ANIMAL, ft *MSUMED BY PEOPLEL RELEASES DILUTED BY LAKE II CONSUMED BY PEOPLE

v FISH

/'

Ii II II I!

II II -- page 11 of 109--

SECTION 3 SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS The NRC requires nuclear power facilities to be designed, constructed and operated in such a way that the radioactivity in effluent releases to unrestricted areas is kept ALARA. To ensure these criteria are met, each license authorizing nuclear reactor operation includes the Offsite Dose Calculation Manual [ODCM] governing the release of radioactive effluents. The ODCM designates the limits for release of effluents, as well as the limits for doses to the general public from the release of radioactive liquids and gases. These limits are taken from Title 10 of the Code of Federal Regulations, Part 50, Appendix I (10CFR50 Appendix I), Title 10 of the Code of Federal Regulations, Part 20.1301 (10CFR20.1301) and Section 5.5.1 of our Station's Technical Specifications. Maintaining effluent releases within these operating limitations demonstrates compliance with ALARA principles. These limits are just a fraction of the dose limits established by the Environmental Protection Agency [EPA] found within Environmental Dose Standard Title 40, Code of Federal Regulations, Part 190

[40CFR190]. The EPA has established dose limits for members of the public in the vicinity of a nuclear power plant. These dose limits are:

Less than or equal to 25 mRem per year to the total body.

Less than or equal to 75 mRem per year to the thyroid.

Less than or equal to 25 mRem per year to any other organ.

Specific limit information is given below.

A. Gaseous Effluents

1. The maximum permissible concentrations for gaseous effluents shall not exceed the values provided within Section 5.5.4.g of Station Technical Specifications. To ensure these concentrations are not exceeded, dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site area boundary shall be limited to the following:

a. Noble gases Less than or equal to 500 mRem/year to the total body.

- Less than or equal to 3,000 mRem/year to the skin.

b. 1131, 1133, H3 , and all radionuclides in particulate form with radioactive half-lives greater than eight (8) days:

- Less than or equal to 1,500 mRem/year to any organ.

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2. In accordance with Title 10 of the Code of Federal Regulations, Part 50, Appendix I, (10CFR50 Appendix I) air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

a. Less than or equal to 5 mRad for gamma radiation and less than or equal to 10 mRad for beta radiation during any calendar quarter.

b. Less than or equal to 10 mRad for gamma radiation and less than or equal to 20 mRad for beta radiation during any calendar year.

3. In accordance with Title 10 of the Code of Federal Regulations, Part 50, Appendix I, (10CFR50 Appendix I), dose to a member of the public (from 113 , 1133 , H3 , and all radionuclides in particulate form with radioactive half-lives greater than eight (8) days) in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following values:

a. Less than or equal to 7.5 mRem to any organ, during any calendar quarter.

b. Less than or equal to 15 mRem to any organ, during any calendar year.

B. Liquid Effluents

1. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the values provided within Section 5.5.4.b of Station Technical Specifications for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 pCi/ml total activity.

2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to:

a. Less than or equal to 1.5 mRem to the total body and less than or equal to 5 mRem to any organ during any calendar quarter.

b. Less than or equal to 3 mRem to the total body and less than or equal to 10 mRem to any organ during any calendar year.

II. AVERAGE ENERGY The CPS ODCM limits the dose equivalent rates due to the release of fission and activation gases to less than or equal to 500 mRem per year to the total body and less than or equal to 3,000 mRem per year to the skin. These limits are based on dose calculations using actual isotopic concentrations from our effluent release streams and not based upon the gross count rate from our monitoring systems. Therefore, the average beta and gamma energies [E] for gaseous effluents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and

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Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", are not applicable.

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IIh. MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY A. Fission and Activation Gases

1. Gas samples are collected weekly and are counted on a high purity germanium detector (HPGe) for principal gamma emitters.

The HVAC and SGTS release points are continuously monitored and the average release flow rates for each release point are used to calculate the total activity released during a given time period.

2. Tritium is also collected by passing a known volume of the sample stream through a gas washer containing a known quantity of demineralized water. The collected samples are distilled and analyzed by liquid scintillation. The tritium released was calculated for each release point from the measured tritium concentration, the volume of the sample, the tritium collection efficiency, and the respective stack exhaust flow rates.

B. lodines Iodine is continuously collected on a silver zeolite cartridge filter via an isokinetic sampling assembly from each release point. Filters are normally exchanged once per week and then analyzed on an HPGe system. The average flow rates for each release point are averaged over the duration of the sampling period and these results - along with specific isotopic concentrations - are then used to determine the total activity released during the time period in question.

C. Particulates Particulates are continuously collected on a filter paper via an isokinetic sampling assembly on each release point. Filters are normally exchanged once per week and then analyzed on an HPGe system. The average flow rates for each release point are averaged over the duration of the sampling period and these results - along with specific isotopic concentrations - are then used to determine the total activity released during the time period in question.

D. Liquid Effluents Each tank of liquid radwaste is recirculated for at least two (2) tank volumes, sampled, and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling ensuring that a representative sample is obtained. Samples are then analyzed on an HPGe system and liquid release permits are generated based upon the values obtained from the isotopic analysis and the most recent values for H , gross alpha, Fe55 , Sr89 and Sr 9 °.

An aliquot based on release volume is saved and added to composite containers. The concentrations of composited isotopes and the volumes of the releases associated with these composites establish the proportional relationships that are then utilized for calculating the total activity released for these isotopes.

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IV. DESCRIPTION OF ERROR ESTIMATES Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:

ET = j[(E1 )2 + (E2 ) 2 + ...(E. )2]

where: ET = total percent error, and El...EN = percent error due to calibration standards, laboratory analysis, instruments, sample flow, etc.

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SECTION 4 RADIOACTIVE EFFLUENT DATA TABLE 1 GASEOUS EFFLUENTS - Summation Of All Releases Data Period: 01 January 2009- 31 December 2009 Continuous Mixed Mode Units Quarter Quarter Quarter Quarter Est.

Total 1 2 3 4 Error, %

A. Fission & Activation Gases

1. Total Release Ci O.OOE+01 0.OOE+01 O.OOE+01 O.OOE+01 30

2. Average release rate for period iCi/sec 0.00E+01 0.00E+01 0.00E+01 O.00E+01

3. Percent of ODCM Limit B. lodines

1. Total Iodine-131 Ci 6.325E-05 2.658E-05 2.795E-05 1.102E-05 31

2. Average release rate for period iCi/sec 8.133E-06 3.381E-06 3.516E-06 1.386E-06

3. Percent of ODCM Limit C. Particulates

1. Particulates half-lives>8 with Ci 1.756E05 2.169E-05 2.897E-05 3.788E-05 24 half-lives >8 days

2. Average release rate for period iCi/sec 2.258E-06 2.759E-06 3.644E-06 4.766E-06

3. Percent of ODCM Limit

4. Gross alpha radioactivity Ci 6.40E-07 1.042E-06 1.523E-08 1.761 E-08 D. Tritium

1. Total Release Ci 1.102E+01 1.367E+01 1.813E+01 6.597E+00 21

2. Average release rate for Deriod gCi/sec I 1.417E+00 1.738E+00 2.281 E+00 8.299E-01 ODCM LimitO/

• Applicable limits are expressed in terms of dose. See Tables 1A and 1B of this report.

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TABLE 1A Air Doses Due to Gaseous Releases Doses per Quarter Type of ODCM 1 st  % of 2 nd  % of 3rd  % of 4th  % of Radiation Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Gamma 5 mRad 0.00E+01 0.00E+01 0.OOE+01 0.OOE+01 0.00E+01 0.OOE+01 0.00E+01 0.OOE+01 Beta 10 mRad 0.OOE+01 0.00E+01 0.OOE+01 0.00E+01 0.00E+01 0.OOE+01 0.OOE+01 0.00E+01 Doses per Year Type of ODOM Year  % of Limit Radiation Limit Gamma 10 mRad 0.00E+01 0.OOE+01 Beta 20 mRad 0.OOE+01 0.00E+01 TABLE 1B Doses to a Member of the Public Due to Radioiodines, Tritium, and Particulates in Gaseous Releases Doses per Quarter Type of ODCM Quarter  % of Quarter  % of Quarter  % of Quarter  % of Organ Limit 1 Limit 2 Limit 3 Limit 4 Limit Bone 7.5 1.94E-05 2.59E-04 2.35E-05 3.13E-04 3.13E-05 4.17E-04 1.94E-05 2.59E-04 Liver 7.5 2.31E-04 3.07E-03 2.85E-04 3.80E-03 3.78E-04 5.04E-03 1.38E-04 1.84E-03 TBody 7.5 2.31 E-04 3.08E-03 2.86E-04 3.81 E-03 3.79E-04 5.06E-03 1.53E-04 2.04E-03 Thyroid 7.5 5.18E-04 6.91E-03 4.06E-04 5.41E-03 5.06E-04 6.75E-03 1.92E-04 2.56E-03 Kidney 7.5 2.31E-04 3.09E-03 2.86E-04 3.81E-03 3.79E-04 5.05E-03 1.38E-04 1.84E-03 Lung 7.5 2.30E-04 3.07E-03 2.85E-04 3.80E-03 3.78E-04 5.05E-03 1.38E-04 1.84E-03 GI LLI 7.5 2.33E-04 3.11E-03 2.89E-04 3.85E-03 3.83E-04 5.11E-03 1.45E-04 1.93E-03 Doses per Year Type of ODCM Year  % of Organ Limit Limit Bone 15 9.36E-05 6.24E-04 Liver 15 1.03E-03 6.88E-03 TBody 15 1.05E-03 6.99E-03 Thyroid 15 1.62E-03 1.08E-02 Kidney 15 1.03E-03 6.89E-03 Lung 15 1.03E-03 6.88E-03 GI LLI 15 1.05E-03 7.OOE-03

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TABLE 2 CLINTON POWER STATION GASEOUS EFFLUENTS - Nuclides Released YEAR: 2009 Mixed Mode Release X Elevated Release IContinuous Mode t X Ground-Level Release Batch Mode Units Quarter Quarter Quarter Quarter A. Fission Gases 1[2] 2[21 3[2] 4[2]

Total for Period Ci 0.OOE+01 O.OOE+01 0.OOE+01 0.OOE+01 B. lodines [1]

1131 Ci 6.32E-05 2.66E-05 2.80E-05 1.10E-05 1133 Ci 2.42E-05 O.OOE+01 2.32E-05 6.35E-05 Total for Period Ci 8.75E-05 2.66E-05 5.12E-05 7.45E-05 C. Particulates [1]

Cob° Ci O.OOE+01 0.OOE+01 0.OOE+01 4.94E-06 y9M Ci 5.49E-03 2.38E-02 2.73E-02 1.49E-02 Mo99 Ci 0.OOE+01 1.81 E-06 0.OOE+01 O.OOE+01 Sr89 Ci 1.76E-05 2.17E-05 2.90E+05 1.80E-05 Mn5 4 Ci O.OOE+01 O.OOE+01 0.OOE+01 1.49E-05 Tc99m Ci O.OOE+01 2.71 E-05 0.OOE+01 O.OOE+01 Gross Alpha Ci 6.40E-07 1.04E-06 1.52E-08 1.76E-08 Total for Period Ci 5.51 E-03 2.39E-02 2.73E-02 1.49E-02 D. Tritium [1]

Total for Period Ci 1.10E+01 1.37E+01 1.81 E+01 6.60E+00 (1] Ten (10) times the values found in 10CFR20 Appendix B, Table 2, Column 1 are used for all Effluent Concentration Limit [ECL] calculations. For dissolved and entrained noble gases, the concentration is limited to 2.OOE-04 pCi/cc total activity.

[2] The lower the value of the actual sample activity - with respect to background activity - the greater the counting error. Proportionally, large errors are reported for the various components of CPS gaseous effluents because of their consistent low sample activity.

An entry of O.OOE+01 indicates that the Minimum Detectable Activity (MDA) concentration of the radionuclide was below the LLD value listed in Table 6.

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TABLE 3 RADIOACTIVE GASEOUS WASTE LLD VALUES TYPE OF ACTIVITY Lower Limit of Detection ANALYSIS (LLD) a (gCi/cc)

Principal Gamma Emitters,

[Noble Gases] b,c <1.00E-04 H3c _<1.00E-06 1131 d *<1.OOE-12 1133 d *<1.00E-10 Principal Gamma Emitters,

[Particulates] b,e <1.00E-11 Sr8 9 , Sr9° *<1 .OOE-1 1 Gross Alpha f *<1.00E-1 1 Table 3 Notations aThe Lower Limit of Detection (LLD) as defined for purposes of these specifications, as an "a priori" determination of the smallest concentration of radioactive material in a sample that will yield a net count - above system background -

that will be detected with a 95% probability and with a low (5%) probability of incorrectly concluding that a blank observation represents a "real" signal.

For a particular measurement system, this may include radiochemical separation:

4.66 sb LLD =

E *V *2.22 x 106 . Y *e -AAt

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Table 3 Notations (continued)

Where:

LLD is the "a priori" lower limit of detection as defined above, as pCi per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, in counts per minute (cpm),

E is the counting efficiency, in counts per disintegration, V is the sample size in units of mass or volume, 2.22E+06 is the number of disintegrations per minute (dpm) per microcurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec- 1 )

and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation.

The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori(after the fact) limit for a particular measurement.

bThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr8 z, Kr88 , Xe 133 , Xe 3 m, Xe, and Xe 138 in noble gas 54 59 65 99 releases and Mn , Fe , Co05, C060, Zn , Mo , 1131, Cs , Cs13 7 , Ce 141 , and Ce 1 4 4 in 134 iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable - together with those of the above nuclides - shall also be analyzed and reported in the Radioactive Effluent Release Report.

C Weekly grab sample and analysis dContinuous charcoal sample analyzed weekly e

Continuous particulate sample analyzed weekly fComposite particulate sample analyzed monthly gComposite particulate sample analyzed quarterly

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TABLE 4 WATERBORNE EFFLUENTS - Summation Of Ali Releases Data Period: 01 January 2009 through 31 December 2009 There were zero (0) liquid radwaste releases from CPS in 2009.

/

Est.

Units Quarter Quarter Quarter Quarter I

w A. Fission & Activation Products 1 2 3 4 Total Error, %

1. Total Release Ci 0.00E+01 0.00E+01 0.00E+01 0.00E+01 N/A Average diluted

2. concentration during gCi/ml 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 period I_1_1 3.Percent of ODM N/A N/A N/A N/A Limit B. Tritium

1. Total Release Ci 0.00E+01 0.00E+01 0.00E+01 0.00E+01 N/A Average diluted

2. concentration during gCi/ml 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 period I _III 3.Percent of ODM N/A N/A N/A N/A Limit IIII C. Dissolved and Entrained Gases

1. Total Release Ci 0.00E+01 0.00E+01 0.00E+01 0.00E+01 N/A Average diluted

2. concentration during gCi/ml 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 period 3.Percent of ODM N/A N/A N/A N/A Limit D. Gross Alpha Radioactivity Gross alpha 0.OOE+011 0.OOE+011 0.OOE+01 0.OOE+011 N/A radioactivity [ oo ,ooo looo oooo, E. Volume of Waste I I Released (prior to Liters 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 N/A Dilution) I F. Volum e of dilution i . . . N water used during period Liters 0.00E+01 0.00E+01 0.00E+01 0.00E+01 N/A

-- page 22 of 109 --

TABLE 5 WATERBORNE EFFLUENTS - Nuclides Released [1]

Data Period: 01 January 2009 - 31 December 2009 All Modes There were zero ( ) liquid radwaste releases from CPS in 2009.

I Continuous Mode I I Batch Mode I X Nuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 A. Tritium IH Ci O.OOE+01 O.OOE+01 0.00E+01 0.00E.01 I B. Fission and Activation Products Sr 89 Ci 0.OOE+01 0.OOE+01 0.00E+01 0.OOE+01 Sr 90 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Cs134 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Cs 137 Ci 0.OOE+01 0.OOE+01 0.00E+01 0.OOE+01 1131 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 CoW- Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Co 60 Ci 0.OOE+01 0.OOE+01 O.OOE+01 0.OOE+01 Fe 59 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Zn 65 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Mn54 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Cr5 l Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Zr/Nb 95 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Mo99 Ci 0.OOE+01 0.OOE+01 0.00E+01 0.OOE+01 Tc-99m Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Ba/La 14 ° Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Ce141 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Ce 144 Ci 0.OOE+01 0.OOE+01 0.00E+01 0.OOE+01 Total Ci O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 C. Dissolved and Entrained Noble Gases Xe 13 3 Ci 0.OOE+01 0.OOE+01 0.00E+01] 0.OOE+01 Xe 1 35 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Total Ci I O.OOE+01 I O.OOE+01 I O.OOE+01 I O.OOE+01 I

[E] A value corresponding to ten times the values found in 10CFR20 Appendix B, Table 2, Column 2 is used for all Effluent Concentration Limit (ECL) calculations.

For dissolved and entrained noble gases, the concentration is limited to 2.OOE-04 pCi/ml total activity.

-- page 23 of 109 --

TABLE 6 RADIOACTIVE LIQUID WASTE LLD VALUES TYPE OF ACTIVITY ANALYSIS Lower Limit of Detection (LLD) a (, Ci/ml)

Principal Gamma Emitters b _<5.00E-07 1131 _<1.00E-06 Dissolved and Entrained Gases (Gamma <1.0.E-05 Emitters) c H3 *<1.00E-05 Gross Alpha *1.00E-07 Sr8 9 , Sr 9° <5.OOE-08 Fe"5 -<1.00E-06 Table 6 Notations a

The Lower Limit of Detection (LLD) as defined for purposes of these specifications, as an "a priori" determination of the smallest concentration of radioactive material in a sample that will yield a net count - above system background -

that will be detected with a 95% probability and with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, this may include radiochemical separation:

4.66 sb LLD =

E

• V *2.22 x 106

• Y

• e-'At Where:

LLD is the "a priori" lower limit of detection as defined above, as pCi per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, in counts per minute (cpm),

-- page 24 of 109 --

Table 6 Notations (continued)

E is the counting efficiency, as counts per disintegration, V is the sample size in units of-mass or volume, 2.22E+06 is the number of disintegrations per minute (dpm) per microcurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec- 1 )

and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and Xt should be used in the calculation.

The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact, MDA) limit for a particular measurement.

b The principal gamma emitters for which the LLD requirement applies include the following radionuclides: Mn5 4 , Fe 59 , Co 58 , CO0, Zn65 , Mo9 9 , Cs' 3 4 , Cs137, Ce 4 1 , and Ce144 shall also be measured, but with an LLD of 5.OE-06. This list does not mean that only these nuclides are detected and reported. Other gamma peaks that are measurable - together with those of the above nuclides - shall also be analyzed and reported in the Radioactive Effluent Release Report.

cDissolved and entrained gases are: Xe 133 3 , Xe' 35 , Xe 138 , Kr 5, Kr88785r and Kr88

-- page 25 of 109 --

BATCH RELEASES There were zero (0.0) liquid radwaste releases from CPS in 2009.

A. Batch Liquid Releases: 2009

1. Number of batch releases: 0

2. Total time period for batch releases: N/A

3. Maximum time period for batch release: N/A

4. Average time period for batch release: N/A

5. Minimum time period for batch release: N/A

6. Average stream flow during periods of release: N/A

7. Total waste volume: N/A

8. Total dilution volume: N/A B. Batch Gaseous Releases: 2009

1. Number of batch releases: 0

2. Total time period for batch releases: N/A

3. Maximum time period for batch release: N/A

4. Average time period for batch release N/A

5. Minimum time period for batch release: N/A

-- page 26 of 109 --

ABNORMAL RELEASES Information concerning abnormal radioactive liquid and gaseous releases is presented below for the year 2009. There were no abnormal or unplanned liquid or gaseous releases from CPS in 2009.

Liquid Releases:

Number of Abnormal Liquid Releases: Zero (0)

Activity Released [Ci]

Nuclides Activity [Ci]

N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 Total 0.0 Gaseous Releases:

Number of Abnormal Gaseous Releases: Zero (0)

Activity Released [Ci]

Nuclides Activity [Ci]

N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 Total 0.0

-- page 27 of 109 --

SECTION 5 SOLID WASTE DISPOSAL INFORMATION During this reporting period - 01 January 2009 through 31 December 2009 - there were Fourteen (14) radioactive waste shipments and zero (0) irradiated fuel shipments from CPS. In addition, the CPS ODCM requires reporting of the following information for solid waste shipped offsite during the above reporting period:

1. Container volume:

3 Class A Waste: 1.61 E+04 ft3 / Class B Waste: 0.0 ft3 / Class C Waste: 0.0 ft This total includes Dry Active Waste (DAW), resins, filter sludges and evaporator bottoms.

2. Total curie quantity: Class A Waste was 505 curies and Class B Waste was 0.0 curies (determined by dose-to-curie and sample concentration methodology estimates) and Class C Waste was 0.0 curies in 2009.

3. Principal radionuclides: See A.2 for listing of measured radionuclides.

4. Source of waste and processing employed: Resins, filter sludges and evaporator bottoms dewatered or solidified in cement and non-compacted dry active waste.

5. Type of container: Type A, Type B and Strong Tight Container.

6. Solidification agent or absorbent: None.

-- page 28 of 109 --

Table 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal: [NOT irradiated fuel]

A.1. Type of Waste Units January - June July - December Est. Total A.I.TypeofWaste Unit2009 2009 Error, %

Spent resins, filter ft3 1.56E+03 314.2

a. sludges, evaporator ___ _ _.. ... . -. :25 bottoms, etc. Ci 500 2.64 Dry compactable ftW 1.15E+04 2.72E+03

b. waste, contaminated ________....... . 25 equipment, etc. Ci 0.2 1.43 Irradiated ft 0 0

c. components, control 25 rods, etc. Ci 0 0 ft_ 0.0 0.0

d. Other Wastes 25 Ci 0.0 0.0

• Total curie quantity and principal radionuclides were determined by measurements.

A.2. Estimate of major nuclide composition (by type of waste)

1. Spent resins, filters, evaporator bottoms, etc.

Waste Nuclide  % Percent Class Name Abundance A Mn 3.66 18.4 W

• FeT

' 77.39 389 Co W 17.27 86.8

_____ Zn 6 0.73 3.65 Other .95 4.8

2. Dry compactable waste, contaminated equipment, etc.

Waste Nuclide  % Percent Class Name Abundance A Mn 2 3.55 0.058 55 F 80.53 1.31

.Co 14.65 0.238

____ Zn 65 0.72 0.012

7i;>** Other 0.56 9.08E-3

-- page 29 of 109 --

Table 7

3. Irradiated Components Waste Nuclide  % Percent Class Name Abundance A Mn54 0.0 0.0 Fe 0.0 0.0

__WCo 0.0 0.0

___,_" _____Zn _ 0.0 0.0 Other 0.0 0.0 Waste Nuclide  % Percent Class Name Abundance B Mn54 0.0 0.0

____ _ Fe5 0.0 0.0 Co 0.0 0.0 Zn 65 0.0 0.0

__ __ ., Other 0.0 0.0 Waste Nuclide  %/Percent C re Class Name Abundance C C Cr-51 0.0 0.0 Fe-55 0.0 0.0 Co-60 0.0 0.0 Ni-63 0.0 0.0 Zr-95 0.0 0.0 Nb-95 0.0 0.0 Sn-119m 0.0 0.0 Sb-125 0.0 0.0 Other 0.0 0.0

-- page 30 of 109 --

Table 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS [continued]

A.3. Solid Waste Disposition January - June 2009 Number of Shipments Mode of Transportation Destination 1 Hittman Transport Barnwell Processing Facility 3 Hittman Transport Clive Disposal Facility (Containerized) 7 Hittman Transport Duratek/Bear Creek July - December 2009 Number of Shipments Mode of Transportation Destination 2 Hittman Transport Duratek/Bear Creek 1 Hittman Transport Duratek/Gallaher Road facility B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A N/A N/A

-- page 31 of 109 --

SECTION 6 DOSE MEASUREMENTS AND ASSESSMENTS This section of the Annual Effluent Release Report provides the dose received by receptors around CPS from gaseous and liquid effluents. The dose to the receptor that, would have received the highest dose in each sector (defined as the Critical Receptor for that sector) is listed within this report. This section also provides the dose to individuals who were inside the Site Boundary. This section also summarizes CPS's compliance with the requirements found within 49CFR190.

The assumptions used in determining dose values are as follows:

• All receptors within a five (5) mile radius are included in the Annual Land Use Census. This Annual Census determines what dose pathways are present as well as the distance of each receptor from the site.

• The annual average meteorological data for 2009 was used in conjunction with the Annual Land Use Census to determine the dose to each receptor within five (5) miles.

• The doses for each receptor from each sector were determined using methodologies given in the ODCM.

• The activity used in these assessments is the total activity released by CPS for the year 2009 including radionuclides with half-lives less than eight (8) days and when dose pathway factors were available.

• The occupancy factor was taken into consideration by calculating the dose to individuals using areas inside the Site Boundary in non-residential areas. The occupancy factor is determined by dividing the number of hour[s] of occupancy per year (taken from the ODCM) and dividing that value by the total number of hour[s]

per year.

• Dose to individuals using areas inside the Site Boundary (that are not residences) was calculated using the Ground Plane and Inhalation pathways.

-- page 32 of 109 --

TABLE 8 MAXIMUM OFFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC IN EACH SECTOR Data Period: 01 January 2009 - 31 December 2009 This table illustrates the dose that a member from the public would most likely be exposed to from radioactive effluents in each sector from CPS. These values represent the maximum dose likely to expose a member of the public in each sector.

RECEPTOR INFORMATION AIRBORNE EFFLUENT DOSE WATERBORNE Iodine and Particulates Noble Gases (mRad) EFFLUENT DOSE (mRem) (mRem) [1]

Sector Distance Pathways Organ Age Organ Total Body Gamma Beta Organ Total (miles) Body N 0.9 GP, I, M, V Th A 1.05E-03 7.15E-04 O.OOE+01 O.OOE+01 0.00E+010.O0E+01 NNE 3.0 GP, I, M, V Th C 4.75E-04 4.00E-04 0.00E+01 0.00E+01 NE 4.3 GP, I, V Th A 1.59E-04 1.37E-04 O.OOE+01 O.OOE+01 ENE 2.7 GP, I, V Th T 2.53E-04 2.12E-04 O.OOE+01 0.OOE+01 E 1.0 GP, I, M, V Th A 7.31 E-04 4.60E-04 0.OOE+01 0.OOE+01 ESE 3.3 GP, I, V Th A 3.OOE-04 2.32E-04 O.OOE+01 0.OOE+01 SE 2.4 GP, I, V Th C 5.61 E-04 4.48E-04 O.OOE+01 0.OOE+01 SSE 2.7 GP, I, V Th C 3.11E-04 2.61 E-04 O.OOE+01 0.OOE+01 S 4.1 GP, I, M, V Th A 1.55E-04 1.33E-04 0.OOE+01 O.OOE+01 SSW 2.9 GP, I Th A 6.03E-05 5.87E-05 O.OOE+01 O.OOE+01 SW 0.7 GP, I, M Th A 3.75E-04 3.25E-04 O.OOE+01 O.OOE+01 WSW 2.3 GP, I, V Th A 2.56E-04 2.10E-04 0.OOE+01 0.OOE+01 W 2.0 GP, I, V Th A 2.71 E-04 2.24E-04 0.OOE+01 0.OOE+01 WNW 1.6 GP, I Th A 1.OOE-04 9.75E-05 O.OOE+01 O.OOE+01 NW 2.3 GP, I, V Th T 3.45E-04 3.02E-04 O.OOE+01 O.OOE+01 NNW 1.3 GP, I, M, V Th A 6.33E-04 4.78E-04 0.OOE+01 O.OOE+01 Key for Table 8 GP = Ground Plane V = Vegetables A = Adult I= Inhalation Th = Thyroid T = Teen M Cows Meat I= Infant C = Child All doses were within all regulatory limits, including limits from 40CFR1 90.

[1] There were zero ( ) liquid radwaste releases from CPS in 2008.

-- page 33 of 109 --

COMPLIANCE WITH 40CFR190 REQUIREMENTS Thermoluminescent dosimeters [TLD] are stationed around CPS to measure the ambient gamma radiation field. Monitoring stations are placed near the site boundary and approximately five (5) miles from the reactor, in locations representing the sixteen (16) compass sectors. Other locations are chosen to measure the radiation field at places of special interest such as nearby residences, meeting places and population centers. Control sites are located further than ten (10) miles from the site, in areas that should not be affected by plant operations. The results from the TLDs are reported in the Annual Radiological Environmental Monitoring Report [REMP]. The results from this effort indicated no excess dose to offsite areas.

Additionally, NUREG-0543, METHODS FOR DEMONSTRATING LWR COMPLIANCE WITH THE EPA URANIUM FUEL CYCLE STANDARD (40 CFR PART 190) states in section IV, "As long as a nuclear plant site operates at a level below the Appendix I reporting requirements, no extra analysis is required to demonstrate compliance with 40 CFR Part 190." The organ and whole body doses reported in Table 8 are determined using 10 CFR 50 Appendix I methodology. The doses reported are well below the limits of Appendix I.

DOSE TO MEMBERS OF THE PUBLIC WITHIN THE SITE BOUNDARY CPS Offsite Dose Calculation Manual section 7.2 requires that the Radioactive Effluent Release Report include an assessment of the radiation doses from radioactive liquids and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY. Within the CPS site boundary there are seven areas that are open to members of the public as identified by CPS ODCM Table 3.4-4 (see Figure 4):

The Department of Natural Resources Recreation Area at 1.287 kilometers (0.8 miles) in the ESE sector A road at 0.495 kilometers (0.3 miles) in the SE sector A residence at 2.736 kilometers (1.7 miles) in the SSE sector A residence at 1.219 kilometers (0.8 miles) in the SW sector Agricultural acreage at 1.372 kilometers (0.9 miles) in the SSW sector A residence at 2.414 kilometers (1.5 miles) in the WSW sector A portion of Clinton Lake at 0.335 kilometers (0.2 miles) in the NW sector At all of the above locations, the plume, inhalation and ground-plane exposure pathways are used for dose calculations. The 2009 Annual Land Use Census identified no other exposure pathways. All dose calculations were performed using the methodology contained in the CPS ODCM.

-- page 34 of 109 --

FIGURE 4 AREAS WITHIN THE CPS SITE BOUNDARY OPEN TO MEMBERS OF THE PUBLIC

-- page 35 of 109 --

TABLE 9 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE DEPARTMENT OF NATURAL RESOURCES RECREATION AREA IN THE EAST-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.00E+01 mRem/year Skin Dose Rate (Noble Gases) O.OOE+01 mRem/year Gamma Air Dose 0.OOE+01 mRad Beta Air Dose 0.OOE+01 mRad Total Body Dose (Particulates) 2.77E-04 mRem Skin Dose (Particulates) [1] 1.91E-05 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Adult Thyroid 2.84E-04 mRem Adult Thyroid NA mRem Child Thyroid NA mRem Infant Thyroid NA mRem

-- page 36 of 109 --

TABLE 10 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE ROAD IN THE SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.00E+01 mRem/year Skin Dose Rate (Noble Gases) 0.00E+01 mRem/year Gamma Gamma":......

Air Air Dose ,, ",

Dose 0.00E+01 mRad Beta Air Dose 0.00E+01 mRad Total Body Dose (Particulates) 6.46E-04 mRem Skin Dose (Particulates) ["1 4.22E-05 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Teen Thyroid 6.68E-04 mRem Adult Thyroid 6.59E-04 mRem Child Thyroid 6.01 E-04 mRem Infant Thyroid 3.69E-04 mRem

-- page 37 of 109 --

TABLE 11 CALCULATED DOSES FOR THE RESIDENTS IN THE SOUTH-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.OOE+01 mRem/year Skin Dose Rate (Noble Gases) 0.OOE+01 mRem/year Gamma Air Dose 0.OOE+01 mRad Beta Air Dose 0.OOE+01 mRad Total Body Dose (Particulates) 8.77E-05 mRem Skin Dose (Particulates) [1 2.41E-06 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Teen Thyroid 9.14E-05 mRem Adult Thyroid 9.01E-05 mRem Child Thyroid N/A [2] mRem Infant Thyroid N/A [2] mRem

[2] No receptors of this age at this location

-- page 38 of 109 --

TABLE 12 CALCULATED DOSES FOR THE RESIDENTS IN THE SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.00E+01 mRem/year Skin Dose Rate (Noble Gases) 0.00E+01 mRem/year Gamma Air Dose 0.OOE+01 mRad Beta Air Dose 0.OOE+01 mRad Total Body Dose (Particulates) 2.48E-04 mRem Skin Dose (Particulates) [ 1.09E-05 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Adult Thyroid 2.55E-04 mRem Teen Thyroid N/A [2] mRem Child Thyroid N/A [2] mRem Infant Thyroid N/A [2] mRem

[2] No receptors of this age at this location

-- page 39 of 109 --

TABLE 13 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE AGRICULTURAL ACREAGE IN THE SOUTH-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.OOE+01 mRem/year Skin Dose Rate (Noble Gases) 0.00E+01 mRem/year F"

Gamma Air Dose 0.00E+01 m Rad Beta Air Dose 0.OOE+01 m Rad Total Body Dose (Particulates) 1.27E-04 mRem Skin Dose (Particulates) i'l 6.70E-06 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Adult Thyroid 1.30E-04 mRem Teen Thyroid N/A [2] mRem Child Thyroid N/A [2] mRem Infant Thyroid N/A [2] mRem

[2] Dose calculated only for the age groups likely to be in the field.

-- page 40 of 109 --

TABLE 14 CALCULATED DOSES FOR THE RESIDENTS IN THE WEST-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.00E+01 mRem/year Skin Dose Rate (Noble Gases) 0.OOE+01 mRem/year Gamma Air Dose 0.OOE+01 mRad Beta Air Dose 0.00E+01 mRad Total Body Dose (Particulates) 8.74E-05 mRem Skin Dose (Particulates) [1] 2.58E-06 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Adult Thyroid 8.99E-05 mRem Teen Thyroid N/A [2] mRem Child Thyroid N/A [2] mRem Infant Thyroid N/A [2] mRem

[2] No receptors of this age at this location

-- page 41 of 109 --

TABLE 15 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF CLINTON LAKE IN THE NORTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2009 - 31 December 2009 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 0.OOE+01 mRem/year Skin Dose Rate (Noble Gases) 0.00E+01 mRem/year Gamma A Airi r.,, D s ,

Dose .

0.00E+01*0 m*:, d. ,

mRad Beta Air Dose 0.OOE+01 mRad Total Body Dose (Particulates) 7.41E-04 mRem Skin Dose (Particulates) ["1 2.50E-05 mRem

[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) and tritium in gaseous effluents.

Highest Organ Dose by Age Group:

Adult Thyroid 7.62E-04 mRem Teen Thyroid N/A [2] mRem Child Thyroid N/A [2] mRem Infant Thyroid N/A [2] mRem

-- page 42 of 109 --

SECTION 7 METEOROLOGICAL DATA AND DISPERSION ESTIMATES On 13 April 1972, the meteorological monitoring program commenced at the Clinton Power Station site. The meteorological system consists of a tower 199 feet high with two (2) levels of instrumentation at the 10-meter and 60-meter elevations. A combined cup and vane sensor measures wind direction and wind speed[s] at the 10-meter and 60-meter levels. An aspirated dual temperature sensor senses the temperatures at these levels. One-half of the dual sensors at each elevation are used for ambient temperature while the other half is used to provide a differential temperature between the 10-meter and 60-meter levels.

Meteorological monitoring instruments have been placed on the Clinton Power Station microwave tower at the 10-meter level to serve as a backup to the primary meteorological tower.

Clinton Power Station meteorological data is transmitted to the Main Control Room [MCR] via a dedicated communication link. Once the signals are received at the MCR, they are then converted to a 4 to 20 milliamp signal and fed individually to a microprocessor and chart recorders. The microprocessor is part of the Clinton Power Station Radiation Monitoring System [RMS]. Meteorological data is available via the microprocessors in the Main Control Room and the Technical Support Center [TSC].

Dispersion modeling for effluents for normal operation of Clinton Power Station is a straight-line, sector-averaged Gaussian plume model designed to estimate average relative concentration at various receptor points. The model was developed in accordance with routine release analysis procedures specified in Regulatory Guide 1.111. For joint frequency input data, periods of calm are distributed in accordance with a directional distribution. For hourly input data, periods of calm are the previous hour's wind direction. Periods of calm are assigned a wind speed value of half the specified instrument threshold value. Reference Table 18 for more detailed information on meteorology and dispersion data.

-- page 43 of 109 --

TABLE 16 METEOROLOGICAL DATA AVAILABILITY Data Period: 01 January 2009 - 31 December 2009 PERCENT OF VALID PARAMETER HOURS PARAMETER Quarter 1 Quarter 2 Quarter 3 Quarter 4

1. Wind Speed _

a. 10-Meter sensor 99.9% 99.9% 100.0% 99.9%

b. 60 Meter sensor 98.3% 99.9% 100.0% 99.9%

2. Wind Direction a, 10-Meter sensor 99.9% 97.8% 100.0% 99.9%

b, 60 Meter sensor 99.9% 97.3% 100.0% 99.9%

3. Temperature a, 10-Meter sensor 99.8% 99.3% 100.0% 99.9%

b, 60 Meter sensor 99.8% 97.6% 100.0% 99.9%

c. Temperature Difference (10m-60m) 99.8% 97.6% 100.0% 99.9%

4. Percent of hours for which valid 10-meter Wind Speed, Wind Direction, and Delta Temperature were available 99.8% 97.6% 100.0% 99.9%

5. Percent of hours for which valid 60-meter Wind Speed, Wind Direction, and Delta Temperature were available 98.2% 97.0% 100.0% 99.9%

Clinton Power Station was able to achieve 99.5% Meteorological Recoverable Data during 2009 exceeding the minimum criteria of 90% as delineated within Regulatory Guide 1.23.

-- page 44 of 109 --

TABLE 17 CLASSIFICATION OF ATMOSPHERIC STABILITY Stability Classification Pasquill Category Defining Conditions Extremely unstable A ------ <AT <-1.042 Moderately unstable B -1.042 <AT< -0.933 Slightly unstable C -0.933 <AT< -0.823 Neutral D -0.823 <AT< -0.274 Slightly stable E -0.274 <AT< 0.823 Moderately stable F 0.823 <AT< 2.195 Extremely stable G 2.195 <AT< ------

AT = temperature difference in degrees Fahrenheit per 100 feet

-- page 45 of 109 --

TABLE 18 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Reporting Period:' 01 January 2009 through 31 December 2009 The following table contains the joint wind frequency tables for CPS. The tables are segregated by sensor elevation and calendar quarter. All tabled values are in hours.

-- page 46 of 109 --

TABLE 18 (continued)

JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January - March 2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 8 0 0 11 NNE 0 0 4 8 0 0 12 NE 0 0 7 2 0 0 9 ENE 0 3 0 0 0 0 3 E 0 1 1 0 0 0 2 ESE 0 6 1 0 0 0 7 SE 0 5 7 0 0 0 12 SSE 0 0 3 2 0 0 5 S 0 4 7 2 0 0 13 SSW 0 1 3 7 0 0 11 SW 0 0 0 2 0 0 2 WSW 1 0 1 4 0 0 6 W 0 2 2 5 0 3 12 WNW 0 1 5 26 0 0 32 NW 0 1 3 2 0 0 6 NNW 0 0 3 0 0 0 3 Total 1 25 49 68 0 3 146 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 47 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total

!I N 3 8 NNE 3 5 II NE 6 16 ENE 0 2 E 0 4 ESE 0 1 SE 1 7 SSE 4 7 S 6 10 SSW 3 6 SW 2 3 WSW 1 6 W 2 7 WNW 12 21 NW 4 13 II, NNW Total 1 25 35 49 2

3 122 6

Variable Direction: 1 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

,I!

-- page 48 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 0 5 NNE 1 0 6 NE 3 1 12 ENE 0 0 3 E 0 0 6 ESE 0 0 5 SE 1 0 8 SSE 2 0 13 S 9 1 16 SSW 3 2 9 SW 3 0 7 WSW 1 0 3 W 2 0 9 WNW 16 1 26 NW 6 3 18 NNW 2 0 8 Total 2 30 57 53 8 4 154 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 49 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Neutral - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 17 37 16 0 73 NNE 16 21 15 4 58 NE 14 30 35 1 80 ENE 11 9 0 0 20 E 12 7 0 0 20 ESE 20 23 0 0 43 SE 28 35 12 0 76 SSE 9 56 16 5 88 S 9 21 37 4 75 SSW 7 13 18 7 47 SW 5 10 7 1 24 WSW 6 13 6 2 31 W 8 23 13 21 66 WNW 11 28 60 35 138 NW 23 45 48 13 131 NNW 20 45 14 1 81 Total 17 216 416 297 94 11 1051 Variable Direction: 2 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 50 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 6 1 17 NNE 3 2 2 8 NE 8 5 0 13 ENE 11 3 0 16 E 1 0 15 ESE 26 4 0 35 SE 10 21 3 36 SSE 11 29 5 48 S 11 31 23 70 SSW 6 29 19 57 SW 5 16 3 26 WSW 7 8 1 19 W 12 21 9 45 WNW 13 26 7 49 NW 20 6 0 26 NNW 4 7 0 12 Total 27 167 215 73 10 0 492 Variable Direction: 1 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 51 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 NNE 2 4 NE 9 11 ENE 8 12 E 2 6 ESE 2 3 SE 3 5 SSE 14 18 S 9 15 SSW 5 8 SW 10 13 WSW 4 8 W 13 16 WNW 6 7 NW 2 7 NNW 0 0 Total 21 89 23 0 0 0 133 Variable Directior 0 Hours of calm in this stability class: 2 Hours of missing stability measurements in all stability class: 4

-- page 52 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 NNE 2 2 I NE ENE 11 1

12 1

I E ESE 0

0 1

1 SE 4 7 SSE 2 4

~1I S 10 12 SSW 7 8 I SW 1 2 WSW 2 2 II W 0 0 WNW 0 0 NW 0 0 NNW 0 0 Total 10 40 0 52 ItI Variable Direction: 0 Hours of calm in this stability class: 0 I Hours of missing stability measurements in all stability class: 4 V3

-- page 53 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

.Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 2 1 6 0 9 NNE 0 1 0 9 3 0 13 NE 0 0 1 5 2 1 9 ENE 0 1 1 0 0 0 2 E 0 2 3 0 0 0 5 ESE 0 4 5 0 0 0 9 SE 0 2 2 5 0 0 9 SSE 0 0 3 0 2 0 5 S 0 3 3 7 0 0 13 SSW 0 1 2 5 4 0 12 SW 0 0 0 0 1 0 1 WSW 1 0 0 2 3 0 6 W 0 2 2 1 3 3 11 WNW 0 1 2 13 17 0 33 NW 0 1 2 2 1 0 6 NNW 0 0 1 2 0 0 3 Total 1 18 29 52 42 4 146 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 54 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 8 NNE 5 NE 16 ENE 2 E 6 ESE 1 SE 7 SSE 8 S 11 SSW 4 SW 3 WSW 6 W 8 WNW 19 NW 14 NNW 5 Total 0 18 30 30 34 11 123 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 55 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 4 NNE 1 6 NE 1 11 ENE 0 3 E 0 4 ESE 0 8 SE 2 9 SSE 2 12 S 7 16 SSW 2 8 SW 2 7 WSW 0 4 W 2 8 WNW 12 28 NW 5 16 NNW 1 8 Total 1 17 41 39 39 15 152 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 56 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Neutral - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 11 12 36 7 0 66 NNE 1 9 14 19 8 4 55 NE 0 7 11 24 19 14 75 ENE 0 0 8 15 1 1 25 E 1 1 8 9 0 0 19 ESE 0 1 18 13 11 0 43 SE 0 6 27 29 20 1 83 SSE 5 5 12 39 20 16 97 S 0 2 7 18 26 16 69 SSW 0 2 6 11 14 5 38 SW 0 4 2 11 5 2 24 WSW 0 3 4 10 5 4 26 W 1 4 12 15 9 29. 70 WNW 1 5 11 27 45 40 129 NW 1 9 19 45 41 12 127 NNW 1 10 27 27 8 0 73 Total 11 79 198 348 239 144 1019 Variable Direction: 1 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 57 of 109 --

• Clinton Power Station Period of Record: January - March 2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 5 10 1 0 18 NNE 1 0 1 1 2 0 5 NE 0 1 3 8 0 0 12 ENE 0 0 6 8 0 0 14 3 E 2 0 3 10 0 0 15 ESE 0 4 13 18 0 0 35 3 SE 0 1 9 10 11 2 33 SSE 0 1 5 27 12 6 51 1 0 1 5 23 12 26 67 SSW 1 0 2 20 24 13 60 SW 0 2 2 14 8 0 26 WSW 0 4 5 9 1 1 20 W 0 3 6 16 8 2 35 WNW 2 1 6 32 14 0 55 NW 2 2 16 9 0 0 29 3 NNW 1 2 5 10 0 0 18 Total 9 24 92 225 93 50 493 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4 I

-- page 58 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 0 1 0 0 2 NNE 0 0 0 1 0 0 1 NE 0 0 3 1 0 0 4 ENE 0 1 3 6 0 0 10 E 0 0 4 3 0 0 7 ESE 2 0 5 0 0 0 7 SE 2 2 4 0 1 0 9 SSE 0 0 2 1 2 0 5 S 0 0 1 15 3 0 19 SSW 0 0 2 8 4 0 14 SW 1 0 1 6 0 0 8 WSW 1 2 5 2 1 0 11 W 0 3 3 5 0 0 11 WNW 0 0 8 7 0 0 15 NW 0 0 4 4 0 0 8 NNW 0 0 1 3 0 0 4 Total 7 8 46 63 11 0 135 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 59 of 109 --

Clinton Power Station Period of Record: January - March 2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 NNE 0 NE 2 ENE 7 E 2 ESE 5 SE 1 SSE 1 S 8 SSW SW 6 WSW 4 W 3 WNW 2 NW 0 NNW 0 Total 1 7 24 17 3 0 52 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 4

-- page 60 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 3 NNE 4 2 7 NE 3 1 6 ENE 2 0 2 E 12 0 14 ESE 7 0 9 SE 1 2 8 SSE 4 0 7 S 3 0 4 SSW 2 2 5 SW 1 4 6 WSW 1 2 4 W 3 2 5 WNW 3 22 32 NW 0 6 6 NNW 0 0 0 Total 0 17 46 46 9 .0 118 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 61 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 1 0 0O 0 4 NNE 0 4 5 0 0 0 9 NE 0 5 7 0 0 0 12 ENE 0 2 4 0 0 0 6 E 0 0 2 0 0 0 2 ESE 0 2 1 0 0 0 3 SE 0 2 2 0 0 0 4 SSE 0 2 4 1 0 0 7 S 2 1 4 0 0 0 7 SSW 0 0 1 4 4 1 10 SW 0 1 2 1 0 0 4 WSW 0 0 6 3 0 0 9 W 0 2 7 2 0 0 11 WNW 0 2 10 7 3 0 22 NW 0 2 4 7 0 0 13 NNW 0 0 1 0 0 0 1 Total 2 28 61 25 7 1 124 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 62 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 5 NNE 2 11 NE 3 13 ENE 1 4 E 2 7 ESE 1 1 SE 4 11 SSE 2 5 S 3 10 SSW 4 18 SW 14 18 WSW 12 18 W 5. 12 WNW 7 25 NW 4 9 NNW 1 4 Total 5 61 67 30 8 0 171 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 63 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Neutral - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 17 7 2 7 0 34 NNE 1 14 20 5 5 2 47 NE 0 29 27 7 1 0 64 ENE 2 10 17 7 0 0 36 E 5 14 24 1 0 0 44 ESE 2 26 10 0 0 0 38 SE 4 17 9 3 0 0 33 SSE 8 27 18 2 0 0 55 S 6 19 16 18 9 0 68.

SSW 3 14 24 15 2 0 58 SW 2 16 23 8 0 0 49 WSW 5 12 11 4 0 0 32 W 1 11 17 11 0 0 40 WNW 4 11 12 24 4 0 55 NW 0 24 32 24 3. 0 83 NNW 1 23 19 18 4 0 65 Total 45 284 286 149 35 2 801 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 64 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Slightly Stable - 60 m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 13 11 3 29 NNE 14 15 2 33 NE 30 21 0 55 ENE 16 7 0 30 E 28 17 1 55 ESE 30 1 1 39 SE 24 8 1 39 SSE 17 7 1 27 S 34 43 18 102 SSW 16 27 15 61 SW 15 10 2 32 WSW 7 6 1 18 W 9 11 3 25 WNW 22 10 3 36 NW 23 8 2 35 NNW 12 11 2 25 0

Total 59 310 213 55 4 0 641 Variable Direction: 0 Hours of calm in this stability class: 2 Hours of missing stability measurements in all stability class: 52

-- page 65 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 N 6 3 9 0 0 0 0 NNE 2 2 4 0 0 0 0 NE 10 14 24 0 0 0 0 ENE 9 6 15 0 0 0 0 E 4 4 8 0 0 0 0 ESE 7 4 11 0 0 0 0 SE 2 4 6 0 0 0 0 SSE 3 3 6 1 0 0 0 S 3 4 8 1 0 0 0 SSW 3 5 9 0 0 0 0 SW 4 11 15 6 0 0 0 WSW 9 11 26 4 0 0 0 W 10 2 16 0 0 0 0 WNW 3 5 8 3 0 0 0 NW 2 8 13 0 0 0 0 NNW 4 2 6 Total 81 88 15 0 0 0 184 Variable Direction 0 Hours of calm in this stability class: 1 Hours of missing stability measurements in all stability class: 52

-- page 66 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 NNE 3 10 NE 15 20 ENE 1 6 E 1 3 ESE 1 2 SE 3 7 SSE 1 2 S 0 0 SSW 1 2 SW 3 3 WSW 2 4 W 2 3 WNW 4 8 NW 8 16 NNW 0 2 Total 42 46 1 0 0 0 89 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 67 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 NNE 0 6 NE 0 5 ENE 0 4 E 2 13 ESE 1 10 SE 2 8 SSE 0 7 S 0 4 SSW 1 5 SW 2 6 WSW 2 4 W 1 5 WNW 20 31 NW 5 5 NNW 1 1 Total 0 9 21 47 37 3 117 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 68 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 1 1 0 0 3 NNE 0 1 2 2 0 0 5 NE 0 1 8 3 0 0 12 ENE 0 1 5 1 1 0 8 E 0 0 1 2 1 0 4 ESE 0 1 1 2 0 0 4 SE 0 1 3 1 0 0 5 SSE 0 1 3 2 1i 0 7 S 1 0 1 2 0 0 4 SSW 0 0 0 6 1 3 10 SW 0 1 0 1 0 2. 4 WSW 0 0 4 4 3 0 11 W 0 0 2 1 1 1 5 WNW 0 1 11 3 5 4 24 NW 0 1 2 7 2 0 12 NNW 0 1 0 1 3 0 5 Total 1 11 44 39 18 10 123 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 69 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 3 NNE 5 0 8 NE 4 2 12 ENE 1 2 7 E 2 3 9 ESE 0 2 3 SE 4 1 8 SSE 4 6 S 1 2 8 SSW 1 5 19 SW 4 3 10 WSW 4 15 22 W 3 3 14 WNW 10 3 27 NW 2 4 12 NNW 0 1 3 Total 4 42 47 47 21 10 171 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 70 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Neutral - 60im-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 6 10 4 1 8 30 NNE 1 4 11 6 3 5 30 NE 1 9 16 27 7 5 65 ENE 0 4 10 15 10 5 44 E 0 9 5 14 18 1 47 ESE 0 7 15 15 2 1 40 SE 1 12 13 4 4 0 34 SSE 4 11 17 15 6 0 53 S 1 17 9 10 10 15 62 SSW 1 10 8 17 10 9 55 SW 2 12 18 17 7 0 56 WSW 3 6 9 15 5 0 38 W 0 4 19 10 8 0 41 WNW 3 6 9 8 20 5 51 NW 1 9 15 20 16 3 64 NNW 0 9 36 21 18 3 87 Total 19 135 220 218 145 60 797 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 71 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 10 12 1 0 26 NNE 12 13 2 0 34 NE 10 20 2 0 35 ENE 7 22 4 0 35 E 11 29 7 0 51 ESE 16 19 3 2 43 SE 28 5 5 0 47 SSE 17 7 1 0 28 S 19 43 11 11 85 SSW 7 37 10 16 71 SW 8 15 3 0 32 WSW 8 6 4 0 22 W 12 14 1 0 28 WNW 10 13 3 2 30 NW 16 9 3 0 33 NNW 17 12 3 0 35 Total 9 48 208 276 63 31 635 Variable Direction: 0 Hours of calm in this stability class: 1 Hours of missing stability measurements in all stability class: 52

-- page 72 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Moderately Stable - 60]m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 10 NNE 2 1 9 NE 4 1 7 ENE 5 4 11 E 15 3 19 ESE 7 2 12 SE 6 0 9 SSE 11 3 17 S 0 1 1 SSW 1 4 6 SW 1 5 10 WSW 7 7 18 W 7 13 22 WNW 8 2 13 NW 3 4 12 NNW 5 4 9 Total 10 33 83 56 3 0 185 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 73 of 109 --

Clinton Power Station Period of Record: April - June 2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 2 0 0 0 N 1 0 3 2 0 0 0 NNE 1 0 3 7 2 0 0 NE 0 0 9 7 5 0 0 ENE 0 0 12 E 1 0 2 2 0 0 5 ESE 0 2 5 1 0 0 8 SE 0 3 1 0 0 0 4 SSE 0 2 0 2 0 0 4 S 0 0 1 0 0 0 1 SSW 0 1 1 0 0 0 2 SW 0 0 0 1 0 0 1 WSW 0 1 1 4 0 0 6 W 0 2 0 1 0 7 WNW 0 1 1 1 0 0 3 NW 1 5 8 3 0 0 17 NNW 0 1 1 2 0 0 4 Total 4 20 41 23 1 0 89 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 52

-- page 74 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 1 7 0 0 0 N 0 8 7 0 0 0 NNE 0 3 10 NE 0 2 6 1 0 0 9 ENE 0 5 4 0 0 0 9 E 0 1 3 0 0 0 4 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 2 1 0 0 0 3 SSW 0 2 0 0 0 0 2 SW 0 1 3 1 0 0 5 WSW 0 1 0 1 0 0 2 W 0 2 3 2 0 0 7 WNW 0 0 6 3 4 0. 13 NW 0 1 15 0 0 0 16 NNW 0 0 3 0 0 0 3 Total 0 22 58 8 4 0 92 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 75 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 3 5 NNE 6 2 8 NE 13 5 19 ENE 8 3 11 E 7 0 7 ESE 5 0 5 SE 3 1 4 SSE 1 0 1 S 4 5 9 SSW 5 3 9 SW 2 5 12 WSW 2 0 6 W 1 4 5 WNW 8 5 14 NW 10 14 24 NNW 3 3 6 Total 0 80 53 11 I 0 145 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 76 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 3 4 NNE 11 4 15 NE 14 6 22 ENE 14 2 16 E 8 0 10 ESE 6 0 6 SE 5 1 7 SSE 7 4 11 S 10 4 14 SSW 6 6 16 SW 4 9 i6 WSW 7 5 15 W 6 3 9 WNW 8 2 13 NW 12 11 23 NNW 7 1 8 Total 4 126 61 13 1 0 205 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 77 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Neutral - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 24 4 0 0 0 31 NNE 4 23 8 0 0 0 35 NE 3 48 15 0 0 0 66 ENE 7 43 2 0 0 0 52 E 10 25 8 0 0 0 43 ESE 8 26 3 0 0 0 37 SE 10 11 1 0 0 0 22 SSE 5 22 20 0 0 0 47 S 5 15 12 0 0 0 32 SSW 2 13 25 7 0 0 47 SW 4 19 16 2 0 0 41 WSW 5 12 16 1 0 0 34 W 1 12 7 3 0 0 23 WNW 3 28 21 3 2 0 57 NW 7 33 27 4 1 0 72 NNW 1 23 9 0 0 0 33 Total 78 377 194 20 3 0 672 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 78of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 N 5 25 30 3 0 0 0 NNE 7 11 21 4 0 0 0 NE 14 37 55 3 0 0 0 ENE 12 24 39 3 0 0 0 E 12 16 31 0 0 0 0 ESE 10 27 37 2 0 0 0 SE 12 40 54 3 0 0 0 SSE 9 49 61 8 0 0 0 S 4 29 41 28 2 0 0 SSW 6 33 69 8 0 0 0 SW 2 17 27 WSW 7 15 6 2 0 0 30 W 9 19 2 3 0 0 33 WNW 7 25 2 4 0 0 38 NW 3 27 3 2 0 0 35 NNW 2 24 5 0 0 0 31 Total 121 418 80 13 0 0 632 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 79 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 8 11 NNE 11 21 33 NE 15 69 84 ENE 16 6 22 E 8 2 10 ESE 2 2 4 SE 1 0 1 SSE 1 1 2 S 2 2 4 SSW 2 10 13 SW 8 3 12 WSW 9 8 17 W 9 4 13 WNW 8 9 17 NW 7 11 18 NNW 5 3 8 Total 107 159 3 0 0 0 269 Variable Direction: 0 Hours of calm in this stability class: 1 Hours of missing stability measurements in all stability class: 0

-- page 80 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 0 7 NNE 24 17 41 NE 30 82 112 ENE 5 0 5 E 4 0 4 ESE 4 0 4 SE 0 0 0 SSE 0 0 0 S 0 0 0 SSW 0 2 2 SW 1 0 1 WSW 2 0 2 W 3 0 3 WNW 3 1 4 NW 2 2 4 NNW 3 0 3 Total 88 104 0 0 0 0 192 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 81 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 9 NNE 10 10 NE 4 4 ENE 9 14 E 2 4 ESE 1 2 SE 0 0 SSE 0 0 S 3 3 SSW 2 2 SW 1 5 WSW 1 2 W 3 5 WNW 2 15 NW 6 14 NNW 2 3 Total 0 0 50 34 4 4 92 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 82 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 5 1 0 0 7 NNE 0 2 6 0 0 0 8 NE 0 3 8 0 0 0 11 ENE 0 2 10 2 1 0 15 E 0 4 5 3 0 0 12 ESE 0 3 1 0 0 0 4 SE 0 2 2 0 0 0 4 SSE 0 0 0 0 0 0 0 S 0 1 5 4 0 0 10 SSW 0 1 6 1 0 0 8 SW 0 1 6 4 2 0 13 WSW 0 0 2 4 0 0 6 W 0 0 4 1 0 0 5 WNW 0 2 9 1 0 1 13 NW 0 6 10 7 0 0 23 NNW 0 1 2 3 0 0 6 Total 0 29 81 31 3 1 145 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 83 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 4 NNE 9 12 NE 5 17 ENE 11 22 E 8 12 ESE 3 7 SE 0 5 SSE 6 14 S 4 15 SSW 3 13 SW 10 18 WSW 3 13 W 3 8 WNW 3 13 NW 9 22 NNW 8 10 Total 1 73 87 34 8 2 205 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 84 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Neutral - 60m-10m Di Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 8 18 3 0 0 29 NNE 0 13 12 1 0 0 26 NE 2 21 24 8 3 0 58 ENE 0 19 22 10 0 0 51 E 2 12 26 11 0 0 51 ESE 3 17 18 9 0 0 47 SE 3 7 8 4 0 0 22 SSE 2 13 16 16 2 0 49 S 1 14 6 11 2 1 35 SSW 1 10 7 22 7 0 47 SW 0 8 13 12 1 0 34 WSW 2 8 13 14 0 0 37 W 0 8 9 3 2 0 22 WNW 1 10 23 11 5 3 53 NW 4 21 27 15 4 1 72 NNW 0 8 21 10 0 0 39 Total 21 197 263 160 26 5 672 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 85 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 18 2 27 NNE 3 11 2 19 NE 13 14 10 41 ENE 6 20 10 38 E 7 21 13 44 ESE 4 15 11 32 SE 11 37 5 56 SSE 14 32 21 67 S 13 18 20 52 SSW 4 15 35 62 SW 4 16 12 32 WSW 5 12 7 27 W 5 8 7 21 WNW 2 23 5 38 NW 14 20 3 41 NNW 3 22 9 35 Total 17 115 302 172 25 1 632 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 86 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 5 5 2 0 0 12 NNE 0 2 9 5 0 0 16 NE 0 7 18 16 2 0 43 ENE 2 4 21 39 0 0 66 E 0 2 15 4 0 0 21 ESE 0 1 5 2 0 0 8 SE 0 3 2 0 0 0 5 SSE 2 4 2 0 0 0 8 S 0 2 1 0 0 0 3 SSW 1 3 2 7 0 0 13 SW 0 3 4 4 0 0 11 WSW 0 1 4 1 0 0 6 W 1 3 15 3 0 0 22 WNW 1 1 11 2 0 0 15 NW 1 3 4 1 0 0 9 NNW 2 2 7 1 0 0 12 Total 10 46 125 87 2 0 270 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 0

-- page 87 of 109 --

Clinton Power Station Period of Record: July - September 2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed,(in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 1 NNE 12 0 14 NE 8 12 25 ENE 12 35 51 E 42 18 66 ESE 6 0 11 U SE 2 0 7 SSE 1 0 4 S 0 0 1 SSW 0 1 1 II SW WSW 1

1 0

0 2

2 W 1 0 1 WNW 2 0 2 NW 0 0 1 NNW 2 0 3 Total 5 27 91 66 0 192 Variable Direction: 0 I Hours of calm in this stability Hours of missing stability class:

measurements in all stability class:

0 0

I

'I

-- page 88 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total 0 2 15 4 0 0 21 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 89 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 NNE 2 NE 1 ENE 4 E 0 ESE 4 SE 4 SSE 0 S 10 SSW 4 SW 3 WSW 5 W 15 WNW 12 NW 4 NNW 0 Total 0 17 35 17 3 0 72 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 90 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 2 NNE 1 4 NE 1 2 ENE 2 2 E 0 0 ESE 0 5 SE 1 7 SSE 1 4 S 7 15 SSW 11 14 SW 7 17 WSW 5 11 W 2 10 WNW 1 8 NW 4 7 NNW 0 0 Total 0 37 45 25 1 0 108 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 91 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Neutral - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 32 21 2 0 0 57 NNE 20 21 4 0 0 47 NE 29 21 13 0 0 65 ENE 18 34 25 0 0 79 E 22 27 7 0 0 60 ESE 25 49 6 0 0 86 SE 46 30 1 0 0 80 SSE 40 57 4 0 0 104 S 8 41 10 0 0 61 SSW 16 37 35 2 0 91 SW 17 31 20 2 0 75 WSW 11 39 53 3 3 112 W 14 27 50 11 9 114 WNW 16 38 33 5 0 95 NW 16 31 22 0 0 70 NNW 17 27 8 0 0 53 Total 43 347 531 293 23 12 1249 Variable Direction: 0 Hours of calm in this stability class: 2 Hours of missing stability measurements in all stability class: 2

-- page 92 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 3 0 4 NNE 2 3 2 8 NE 1 18 11 30 ENE 4 4 1 9 E 3 20 0 24 ESE 11 15 6 32 SE 7 30 9 46 SSE 7 55 30 93 S 1 55 65 121 SSW 4 14 50 72 SW 2 11 25 43 WSW 1 10 20 34 W 2 7 10 25 WNW 0 14 10 30 NW 0 13 8 21 NNW 0 5 4 9 Total 46 277 251 -25 2 0 601 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page93 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 1 1 0 0 0 0 N 2 0 0 0 0 NNE 3 3 6 2 0 0 0 NE 2 2 6 0 0 0 0 ENE 3 4 7 0 0 0 0 E 8 4 12 0 0 0 0 ESE 0 6 6 0 0 0 0 SE 1 4 5 0 0 0 0 SSE 0 4 4 3 0 0 0 S 2 13 18 3 0 0 0 SSW 1 3 7 0 0 0 0 SW 2 0 2 0 0 0 0 WSW 0 4 4 0 0 0 0 W 5 0 5 0 0 0 0 WNW 3 1 4 1 0 0 0 NW 6 9 16 0 0 0 0 NNW 1 2 3 Total 38 60 9 0 0 0 107 Variable Direction: 0 Hours of calm in this stability class: 3 Hours of missing stability measurements in all stability class: 2

-- page 94 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 10 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 0 0 N

3 0 0 0 0 5 NNE 4 0 0 0 0 11 NE 4 0 0 0 0 6 ENE 1 0 0 0 0 1 E

0 0 0 0 0 0 ESE 1 0 0 0 0 4 SE 1 0 0 0 0 2 SSE 0 0 0 0 0 1 S

0 0 0 0 0 2 SSW 0 0 0 0 0 1 SW 0 0 0 0 0 0 WSW 1 0 0 0 0 2 W

0 0 0 0 0 3 WNW 1 0 0 0 0 3 NW 0 0 0 0 0 2 NNW Total 27 16 0 0 0 0 43 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 95 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Extremely Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N

NNE NE ENE ESE ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total 0 0 10 9 2 0 21 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 96 of 109 --

Clinton Power. Station Period of Record: October - December2009 Stability Class - Moderately Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 NNE 3 NE 1 ENE 4 E 0 ESE 4 SE 4 SSE 0 S 6 SSW 8 SW 3 WSW 5 W 12 WNW 14 NW 4 NNW 1 Total 0 4 32 24 10 2 72 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 97 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Slightly Unstable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 NNE 2 NE 3 ENE 2 E 1 ESE 5 SE 6 SSE 3 S 17 SSW 12 SW 19 WSW 9 W 11 WNW 9 NW 6 NNW 1 Total 0 22 32 34 20 0 108 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 98 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Neutral - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 33 17 2 0 59 NNE 5 30 11 0 0 46 NE 5 15 19 11 2 53 U

ENE 2 16 26 24 17 87

'1 E ESE 5

9 12 11 13 33 15 34 3

6 48 96

'I SE 18 33 29 5 1 87

~Ii SSE 9 30 50 12 0 102 S 6 11 41 7 6 71 SSW 5 18 26 29 4 83

[U SW WSW 8 19 20 23 26 17 3 72 I

10 45 6 107 W 8 21 29 36 23 119 I

WNW 7 13 29 28 8 86 NW 9 23 32 12 2 79 NNW 4 19 26 7 0 56 Total 16 116 324 430 284 81 1251 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 99 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Slightly Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 1 0 0 4 NNE 1 0 0 1 0 0 2 NE 0 1 5 12 8 0 26 ENE 0 1 3 8 2 0 14 E 0 1 2 2 0 0 5 ESE 0 2 20 10 1 1 34 SE 1 8 21 15 2 0 47 SSE 0 3 18 46 10 1 78 S 0 4 32 78 11 0 125 SSW 0. 2 13 52 21 0 88 SW 1 4 7 34 8 0 54 WSW 0 1. 4 19 3 1 28 W 0 2 7 13 4 2 28 WNW 0 2 7 13 3 3 28 NW 0 1 12 9 1 0 23 NNW 0 1 7 9 0 0 17 Total 3 34 160 322 74 8 601 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 100 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Moderately Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 1 5 NNE 1 2 5 NE 2 0 3 ENE 0 0 2 E 5 3 8 ESE 10 2 13 SE 4 0 5 SSE 0 1 4 S 4 2 6 SSW 4 16 25 SW 1 1 2 WSW 1 0 1 W 3 2 6 WNW 1 1 4 NW 3 7 13 NNW 3 2 8 Total 4 14 44 40 8 0 110 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 101 of 109 --

Clinton Power Station Period of Record: October - December2009 Stability Class - Extremely Stable - 60m-10m Delta-T (F)

Winds Measured at 60 Meters Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 1 0 N 0 1 0 0 2 1 1 0 NNE 0 0 0 2 NE 0 0 2 5 0 0 7 ENE 0 0 3 7 0 0 10 E 0 0 1 3 0 0 4 ESE 0 0 1 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 2 0 0 0 2 SSW 1 0 5 0 0 0 6 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 1 0 0 0 1 WNW 0 2 1 0 0 0 3 NW 0 2 0 0 0 0 2 NNW 0 0 3 0 0 0 3 Total 1 6 21 15 0 0 43 Variable Direction: 0 Hours of calm in this stability class: 0 Hours of missing stability measurements in all stability class: 2

-- page 102 of 109 --

SECTION 8 ODCM OPERATIONAL REMEDIAL REQUIREMENT REPORTS In accordance with CPS ODCM section[s] 2.7.1 and 3.9.2, INOPERABLE radioactive liquid and gaseous effluent monitoring instrumentation channels remaining in an INOPERABLE condition for greater than 30 days shall be reported in the Annual Radioactive Effluent Release Report.

During the course of 2009, there was one (1) instance when either a radioactive liquid or gaseous effluent instrumentation channel[s] was INOPERABLE for greater than any 30 day period. Further; there were two (2) occurrences where Surveillance Requirements were not met. All events are documented below.

ORIX-PRO12, HVAC Vent Hi Range Monitor was declared inoperable on 13 June 2009

@ 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> due to spiking / abnormal behavior on Channel 3 [Noble Gas]. ORIX-PRO12, HVAC Vent Hi Range Monitor was returned to service and made OPERABLE on 25 August 2009 @ 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />.

During the period of inoperability, the station complied with ODCM Table 3.9.2.1 Remedial Requirement (11) which states:

a. Initiate the preplanned alternate method of monitoring the appropriate parameter(s).

b. Instrument Inoperability does not preclude changing mode.

Since the monitor was also inoperable for greater than 30 days, ODCM 3.9.2 remedial requirement (b) also applies which requires:

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels Operable, comply with the remedial requirements specified in table 3.9.2-1. Restore the inoperable instrumentation to operable status within 30 days and if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 why this inoperability was not corrected in a timely manner.

The inoperable monitor and subsequent troubleshooting efforts were documented in Issue Report[s]; #941030, #946085, #945156 and #945195. To' summarize; the inoperable condition was the result of the Digital to Analog (D/A) board in ORIXPRO12 and was discovered to be contributing towards the channel spikes on Channel 3 during the troubleshooting. As a result of obsolete D/A boards, troubleshooting and parts acquisition were not completed within 30 days.

Contrary to the requirements of ODCM 3.4.1.2, Table 3.4-1 (B) (3) for the monthly gross alpha analysis and the quarterly Sr-89 and Sr-90 analysis, Clinton was unable to include the results from the September monthly alpha analysis surveillance because one (1) Stand-by Gas Treatment System [SGTS] particulate filter had been misplaced.

This subsequently impacted the second surveillance; the 3 rd Quarter Sr-89 and Sr-90 composite analysis lacking the missing SGTS particulate filter.

In accordance with ODCM 1.3.2, a failure to perform a surveillance requirement within the specified time interval shall be a failure to meet the Operation Requirement (OR).

The Remedial Requirement is to immediately restore the release rates to within the above limits. At no time was the release rates above the limits specified. This event was captured in Issue Report #984220.

-- page 103 of 109 --

SECTION 9 CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS In accordance with Section 7.2 of the CPS ODCM, licensee-initiated changes to the liquid, gaseous or solid radioactive waste treatment systems shall be reported in the Annual Radioactive Effluent Release Report.

The Process Control Program (PCP) for radioactive wastes is controlled by Radioactive Wastes procedure, RW-AA-100, with revision (7) as the last revision. No Changes were made in the procedure in 2009.

There were no permanent changes to the Solid Radioactive Waste Treatment System during the course of the 2009 reporting period.

-- page 104 of 109 --

SECTION 10 NEW LOCATIONS FOR DOSE CALCULATION AND / OR ENVIRONMENTAL MONITORING The following is a summary of the 2009 Annual Land Use Census. It shows changes in locations for dose calculations and / or environmental monitoring identified by the Annual Land Use Census. The distance of the receptor is being listed in the report in lieu of the name of the resident. This is being done to maintain and respect the privacy of the residents.

1.0 Nearest Residence The nearest residents identified in each of the sixteen (16) sectors are shown below. An asterisk notes any changes from the previous year below (*)

2009 2008 SECTOR RESIDENT AGE GROUP RESIDENT AGE GROUP (miles) (miles)

N 0.9 A 0.9 A NNE 1.0 C, A 1.0 C, A NE 1.3 A 1.3 A

• ENE 1.7 C, A 1.8 C, A E 1.0 A 1.0 A ESE 3.2 A 3.2 A SE 2.4 C, T, A 2.4 C, T, A SSE 1.7 T, A 1.8 T, A S 3.0 A 3.0 A SSW 2.9 A 2.9 A SW 0.7 A 0.7 A WSW 1.6 A 1.6 A W 1.2 C, A 1.2 C, A WNW 1.6 A 1.6 A NW 1.6 A 1.6 A NNW 1.2 A 1.7 A (I)nfant (C)hild (T)een (A)dult

-- page 105 of 109 --

SECTION 10 (continued) 2.0 Broadleaf Garden Census Eighty-three (83) gardens within a three (3) mile radius were located in the sixteen (16) geographical sectors surrounding CPS. Fourteen (14) gardens contained broad leaf vegetation, which were specifically identified for this report. Although other crops were identified within these areas, they are not addressed as part of this report.

The nearest gardens identified in each of the sixteen (16) geographical sectors are shown below. An asterisk notes any changes from the previous year below (*).

2009 2008 SECTOR GARDENS AGE GROUPS GARDENS AGE GROUPS (miles) (miles)

N 0.9 A 0.9 A NNE 3.0 C, T, A 3.0 A NE 4.2 A 2.1 A ENE 2.6 T, A 2.6 A E 1.0 A 1.0 A ESE 3.2 A 3.2 T, A SE 2.4 C, T, A > 5 C, T, A SSE 2.7 C, A > 5 C, A S 3.96 A 3.0 A SSW > 5 > 5 SW >5 >5 WSW 2.3 A 2.3 A W 2.0 A 2.0 A WNW >5 1.6 NW 2.4 T, A 2.8 C, T, A NNW 1.2 A 1.3 A (I)nfant (C)hild (T)een (A)dult

-- page 106 of 109 --

SECTION 10 (continued) 3.0 Milking Animal Census Milking animals within the sixteen (16) geographical sectors were located within five (5) miles surrounding CPS. These milking animals were either used for the nursing of their offspring or used for meat production for their own personal use and sold commercially. There were no residents that milked their animals for human consumption.

Milking animals were specifically identified for this report. Although other livestock were identified within these areas, they are not addressed as part of this report.

The nearest milking animals identified in each of the sixteen (16) geographical sectors are shown below. An asterisk notes any changes from the previous year below

(*).

2009 MILKING AGE 2008 MILKING AGE SECTOR ANIMALS (miles) GROUPS ANIMALS (miles) GROUPS N 0.9 A 0.9 A NNE 2.87 C/T/A 2.3 C/T/A NE >5 >5 ENE > 5 > 5 E 1.0 A 1.0 A ESE > 5 > 5 SE >5 >5 SSE > 5 > 5 S 4.1 A 4.1 A SSW >5 3.4 A SW >5 3.6 A WSW 3.32 A 2.8 A W >5 >5 WNW >5 >5 NW >5 >5 NNW 1.2 A 1.3 A (I)nfant (C)hild (T)een (A)dult

-- page 107 of 109 --

SECTION 11 CORRECTIONS TO DATA REPORTED IN PREVIOUS REPORTS There were no administrative changes identified in 2009 against previously submitted Annual Radioactive Effluent Release Report[s] resulting in an errata data submittal to the Commission.

-- page 108 of 109 --

SECTION 12 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The Offsite Dose Calculation Manual (ODCM) was revised in 2009 to incorporate administrative changes and new format into corporate style procedure.

Licensee initiated changes to the ODCM are still performed in accordance with Technical Specification 5.5.1, Offsite Dose Calculation Manual (ODCM) and are still reviewed and approved in accordance with 10CFR50.59. The entire ODCM is included in Procedure CY-CL-1 70-301 to facilitate this administrative change.

Revision (22) of the ODCM is included in this submittal.

-- page 109 of 109 --

CY-CL-170-301 Exelokn Revision 22 Page 1 of 195 Nuclear CLINTON POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL Docket No. 50-461 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 2 of 195 Table of Contents Section Title Page 1.0 PREFACE ,-,

1.1 Definitions i-I I 1.2 General Operation Requirements 1-4 1.3 General Surveillance Requirements 1-5 1.4 Effluent Concentration Limit (ECL) 1-6 Calculation Requirements 2.0 LIQUID EFFLUENTS i 2.1 Introduction 2-1 2.2 Liquid Radwaste Discharge Process 2-1 Radiation Monitoring (PRM) System 2.3 10CFR20 Release Rate Limits 2-1

.2.3.1 Liquid Effluent Concentration 2-2 Operation and Surveillance Requirements 2..3.2 Liquid Radwaste Discharge PRM 2-6

• Setpoints 2.3.3 Plant Service Water Effluent 2-11 PRM Setpoints U 2.3.4 Shutdown Service Water (SX)' 2-12 Effluent PRM Setpoints I 2.3.5 Fuel Pool Heat Exchanger Service 2-12 Water Effluent PRM Setpoints 2.3.6 Component Cooling Water PRM 2-12 SetpOints 3 I

CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 3 of 195 Table of Contents Section Title Page 2.0 2.4 10CFR50, Appendix I Release Rate Limits 2-13 2.4.1 10CFR50, Appendix I Release Rate 2-13 Limits - Operation and Surveillance Requirements 2.4.2 Discussion 2-14 2.5 Liquid Radwaste Treatment System 2-24 2.5.1 Liquid Radwaste Treatment System - Operation and 2-24 Surveillance Requirements 2.5.2 Temporary Liquid Radwaste 2-25 Hold-up'Tanks 2.6 Doses From Other Significant Liquid Effluent Pathways 2-25 2.7 Radioactive Liquid Effluent Monitoring 2-26 Instrumentation 2.7.1 Radioactive Liquid Effluent 2-26 Monitoring Instrumentation-Operation and Surveillance Requirements 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 3.2.2 SGTS Stack Process Radiation 3-2 Monitoring (PRM) System CLINTON--UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 a

Page 4 of 195 Table of Contents Section Title Page 3.0 3.3 Main Condenser Off-Gas, Monitoring System 3-3 3.3..1 Pre-Treatment Air Ejector 3-3 n

.Off-Gas Process Radiation Monitor (PRM) g 3.3.2 Post-Treatment Air Ejector 3-4 Off-Gas Process Radiation Monitor (PRM) I 3.4 10CFR20 Release Rate Limits 3-4 3.4.1 10CFR20 Release Rate Limits Operation and Surveillance

- 3-5 I Requirements 3 3.4.2 Dose Rate-Due to Noble Gases 3-9 3.4.3 Dose Rate.Due to Radioiodines,

'Particulates and Tritium 3-9 3 3.5 10CFR50, Appendix I Release Rate Limits 3-14 3 3.5!.1 Noble Gas Dose - Operation and 3-14

.Surveillance Requirements 1 3.5.2 Iodine-131, Iodine-133, Tritium, 3-15 and Radionuclides in Particulate Form - Operations and Surveillance Requirements I

3.5.3 Noble Gas Air Dose Equations 3-16 3 3.5.4 Radioiodines, Particulates and 3-17

... . Tritium Dose Equations 3.6 Gaseous Radwaste (Offgas Treatment 3-25 3.6.1 Gaseous Radwaste (Offgas 3-25 Treatment) System - Operation and Surveillance Requirements H I

CLINTON -- UNIT #1 12/09 Rev.22 -

f

CY-CL-170-301 Revision 22 Page 5 of 195 Table of Contents Section Title Page 3.0 .3.7 Ventilation Exhaust Treatment 3-26 3.7.1 Venitilation Exhaust Treatment 3-26 System - Operation and Surveillance Requirements 3.7.2 Gaseous Effluent Dose 3-27 Projection Calculations 3.8 Effluent Monitor Setpoint Calculations 3-27 3.8.1 Total Body Dose Rate Setpoint 3-28 38:82 Skin Dose Rate Setpoint 3-29 3.9 Radioactive Gaseous Monitoring 3-30 Instrumentation 3.9.1 .Offgas Radiation Monitoring 3-30 Instrumentation - Operation and Surveillance Requirements 3.9.2 Radioactive Gaseous Effluent 3-37 Monitoring Instrumentation -

Operation and Surveillance Requirements 4.0 COMPLIANCE WITH 40CFRI90 4-1 4.1 Total Dose- Operation and Surveillance 4-1 Requirements 4.l.a Remedial Requirement 4-1 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5-1 5.1 Monitoring Program - Operation and 5-2 Surveillance Requirements 5.2 Land Use Census'- Operation and 5-21 Surveillance Requirements CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 6 of 195 Table of Contents Section Title Page 5.0 5.3 Interlaboratory Comparison Program 5-22

.5.3.1 Interlaboratory Comparison 5-23 Program - Operation and Surveillance Requirements 6.0 BASES FOR OPERATION,,AND SURVEILLANCE 6-1 REQUIREMENTS 6.1 General.Operation and Surveillance 6-1 Requirements 6.2 Monitoring Instrumentation 6-2 6.3 Radioactive Effluents 6-3 6.3.1 Liquid Effluents 6-3 6.3.2 Gaseous Effluents 6-5 6.3.3 Total Dose 6-9 6.4 Radiological Environmental Monitoring 6-10 7.0 REPORTING REQUIREMENTS 7-1 7.1 Annual Radiological Environmental 7-1 Operating Report 7.2 . Radioactive Effluent Release 7-2 Report 8.0 ADJUSTMENT OF THE CPS ODCM METHODOLOGY 8-1 9.0 ATMOSPHERIC TRANSPORT AND DISPERSION MODEL 9-1 9.1 Introduction 9-1 CLINTON ---UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 7 of 195 Table of Contents Section Title Page 9.0 9.2 Concurrent Meteorological. Data Processing 9-1 9.2.1 Determination of Pasquill 9-2 Stability Class 9.2.2 Calculation of Stack Height 9-3 Wind Speed 9.2.3 Determination of Release Mode 9-3 and -the Entrainment Coefficient 9.2.4 Calculation of Vertical Standard 9-4

Deviation 9.2.5 .Calculation of~the Building Wake 9-5 Correction 9.2.6 Calculation of Momentum Plume 9-5 Rise 9.2.7 Calculation of Effective Plume 9-6 Height 9.2.8 Determination of Affected 9-7 Sectors.

9..2. 9 Calculation of Depletion and 9-8 Deposition Factors 9.2. 10 Ground Level X/Q, D2DPXQ, DIXQ, 9-10 D/Q Analysis 9.2.11 Elevated X/Q, D2DPXQ, DlXQ, D/Q 9-11 Analysis CLINTON -- UNIT #1 Rev.22 -

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CY-CL-1 70-301 Revision 22 Page 8 of 195 Table of Contents Section Title Page .

1.1-1 Surveillance Frequency Notation 1-6 2.3-1 Radioactive Liquid Waste Sampling and Analysis 2-3 Program 2.4-1 Adult IngestionDose Commitment Factors - Aij 2-16 I 2.4-2 Bioaccumulation Factors - BFi '2-:18 1 2.4-3 Adult Ingestion Dose Factors - DFi 2-19 2.7-1 Radioactive Liquid EffluentMonitoring Instrumentation

- 2-27 I

2.7-2 Radioactive Liquid Effluent Monitoring Instrumentation. Surveillance Requirements.

2-30 I

3.4-1 Radioactive Gaseous-Waste Sampling and Analysis ý3-6 Program 3.4-2 Dose Factors for Noble Gases and Daughters 3-11 3.4-3 Inhalation Pathway Dose Rate Factors (Child) - 3-12 P..

3.4-4 Location-of Members of the Public Within the 3-13 I CPS Site Boundary and Their Associated Occupancy Factors ... .

3.9.1-1 Offgas Radiation Monitoring Instrumentation 3-31 3.9.1-2 Offgas Radiation Monitoring Instrumentation Surveillance Requirements 3-35 I

3.9.2-1 Radioactive Gaseous Effluent Monitoring 3-38 Instrumentation .

3.9.2-2 Radioactive Gaseous Effluent Monitoring 3-40 Instrumentation Surveillance Requirements I 3.5-1 Inhalation Dose Factors for Infant- (DFAi)a 3-44 3.5-2 Inhalation Dose Factors for Child-(DFAi)a 3-45 3.5-3 Inhalation Dose Factors for Teen- (DFAi)a 3-46 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-1 70-301 Revision 22 Page 9 of 195 Table of Contents Section Title Page 3.5-4 Inhalation Dose Factors for Adult-(DFAi)a 3-47 3.5-5 Ground Plane Dose Factors-DFGi 3-48 3.5-6 Ingestion Dose Factors for Infant- (DFLi)a 3-49 3.5-7 Ingestion Dose Factors for Child--(DFLi)a 3-50 3.5-8 Ingestion Dose Factors for Teen- (DFLi)a 3-51 3:.5-9 Ingestion Dose Factors for.:Adult-(DFLi)a 3-52 3.5-10 Input Parameters'for Calculating RCija 3-53 3.5-11 Input Parameters for Calculating RMija 3-54 3.5-12 Input Parameters for Calculating RVija 3-55 35 -13 Inhalation Pathway. Factors=ý--R~ijaI (INFANT) 3-56 3.5-14 Inhalation Pathway Factors - Rija (CHILD) 3-57 3.5-15 Inhalation Pathway Factors - RIija (TEEN) 3-58 3.5-16 Inhalation Pathway Factors - Rija (ADULT) 3-59 3.5-17 Cow Milk Pathway Factors - RCija (INFANT) 3-60 3.5-18 Cow Milk Pathway Factors - RCija (CHILD) 3-61 3.5719 Cow Milk Pathway Factors - RCija (TEEN) 3-62:

3.5-20 Cow Milk Pathway Factors,- RCija (ADULT) 3-63 3.5-21 Goat Milk Pathway Factors - RCija (INFANT) 3-64 3.5-22 Goat Milk Pathway Factors - RCija (CHILD) 3-65 3.5-23 Goat MilkPathway Factors - RCija (TEEN) 3-66 3.5-24 Goat Milk Pathway Factors -RCija (ADULT) 3-67 3.5-25 Meat Pathway Factors RMija (CHILD) 3-68 3.5-26 Meat Pathway Factors RMija (TEEN) 3-69 3.5-27 Meat Pathway Factors RMija (ADULT) 3-70 CLINTON -- UNIT #1 Rev.22'-

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CY-CL-170-301 Revision 22 Page 10 of 195 Table of Contents Section Title Page 3.5-28 Vegetation Pathway Factors - RVija (CHILD) . 3-71 3.5-29 Vegetation Pathway Factors - RVija (TEEN) 3-72 3.5-30 Vegetation Pathway Factors 7 RVija (ADULT) 373 3.5-31 Ground Plane Pathway Factors. - R G 3-74 5.1-1 Radiological Environmental Monitoring Program. 5-4_

5.1-2 Reporting Levels for Radioactivity 5-17 Concentrations in Environmental Samples 5.1-3 Detection Capabilities for Environmental'Sample 5-18 Analysis Lower Limit of Detection (LLD) 9.2-1 cY Values 974 9.2-2 Wind Direction Tables 9-7 9.2-3 DPF Depletion Factors 9-8 9.2-4 DPSF Deposition Factors 9-9 9.2-5 Gaseous Effluent Release Point Characteristics 9-13 CLINTON -- ,UNIT #1 *Rev.22 -

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CY-CL-170-301 Revision 22 Page 11 of 195 2.1-1 Unrestricted Area Boundary for Liquid Effluents 2-10 2.5-1 Liquid Radwaste Treatment System 2-21 2.5-.2 Shutdown and Fuel Pool Heat Exchanger, Service 2-22 Water Effluent Monitors 2.5-3 Solid Radwaste System Simplified Flow Diagram 2-23 3.1-1 CPS Site Boundary For Gaseous Effluents 3-42 3.3-1 Main Condenser Off-Gas Treatment System 3-43 5.0-1 REMP'Locations Within 1 Mile of CPS 5-24 5.0-2 REMP Location.1-2 Miles From CPS.. 5-25 5-.0-3 REMP Location 2-5 Miles From CPS 5-26 5.0-4 REMP Locations Greater than 5 Miles From CPS 5-27 CLINTON -- UNIT #1 Rev.22 -

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Revision 22 Page 12 of 195 I

1.0 GENERAL INFORMATION I PREFACE The Clinton'Power Station..OFFSITE DOSE CALCULATION MANUAL it (CPS-ODCM) provides the methodologies and parameters to be used by AmerGen Energy Company LLC to assure compliance with.. the radioactive effluent dose.,limitations I

stated in 10CFR20, 10CFR50 Appendix A (General Design Criteria 60 and, 64), 10CFR50 Appendix -I, and 40CFRl90.

I The CPS-ODCM was prepared based on guidance provided. in NUREG-0133, PREPARATION-OF RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR NUCLEAR POWER PLANTS (October 1978), and NUREG70473, RADIOLOGICAL EFFLUENT I

TECHNICAL SPECIFICATIONS FOR BOILINGWATER-REACTORS

• (Draft 7, to Revision.3). This manual along with. station procedures will be'used by:CPS personnel to demonstrate I

compliance with the above referenced Federal Regulations.

Changes to the CPS-ODCM shall be provided in the I

RADIOACTIVE EFFLUENT RELEASE REPORT.

1.1 Definitions I

,The following terms are defined so that uniform interpretation of requirements of this manual may be achieved. The defined terms appear in capitalized type I

and shall be applicable throughout this manual.

g I

I I

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CY-CL-170-301 Revision 22 Page 13 of 195 CHANNEL CALIBRATION 1.1.1 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire, channel, including the required sensor, alarm, display,' and trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibratiOn* of the remaining

'adjustable devices in the channel. The CHANNEL CALIBRATION.may be performed by means of any series of sequential, overlapping or total: channel steps so that the entire channel is calibrated.

CHANNEL CHECK 1.1.2 A CHANNEL CHECK shall be the qiqalitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent'instrument-channels measuring the same parameter:..

CHANNEL FUNCTIONAL TEST 1.1.3 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated, or actual, signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping or total channel steps so that the entire channel is tested.

FREQUENCY NOTATION 1.1.4 The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined in Table 1.1-1.

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Revision 22 Page 14 of 195 GASEOUS RADWASTE TREATMENT SYSTEM 1.1.5 A GASEOUS RADWASTE TREATMENT SYSTEM is any system, designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF THE PUBLIC 1.1.6 An individual in a controlled or unrestricted area.

However, an individual is not a member of the public during any period in which the individual receives an occupational dose..

1.1.7 MODE A MODE shall correspond to any one inclusive combination of mode switch position,, average reactor coolant temperature, and.,reactor vessel head bolt tensioning specified in Technical Specification Table 1.1-1 with fuel in the reactor yessel. .

OPERABLE - OPERABILITY 1.1.8 A system, subsystem, division, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, division', component or device to perform its specified safety function(s) are also capable function(s). of performing their related support REMEDIAL REQUIREMENT 1.1.9 REMEDIAL REQUIREMENT shall be that part of a requirement which prescribes remedial measures required under designated conditions.

SITE BOUNDARY 1.1.10 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

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CY-CL-170-301 Revision 22 Page 15 of 195 SOURCE CHECK 1.1.11 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

UNRESTRICTED AREA 1.1.12 An UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.

VENTILATION EXHAUST TREATMENT SYSTEM 1.1.13 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing'iodines or particul-ates from the gaseous exhaust stream prior to'the release to:the environment. -Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not consIdered to -be VENTILATION EXHAUST TREATMENT SYSTEM components.

The following systems are designated VENTILATION EXHAUST TREATMENT SYSTEMS:

-1) Machine Shop HVAC (VJ)

2) Laboratory HVAC (VL)

3) Drywell Purge (VQ)-

4) Radwaste7Bldg. HVAC (VW)

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Revision 22 Page 16 of 195 1.1.14 The MCR ARPR LAN is the means whereby data is transmitted.

from the ARPR monitors to the central collection equipment!. Terminal !HI3-P870 is normally the..Master Terminal. Terminals lHl3-P864 and the terminal::in the TSC may also be used to fulfill MCR ARPR LAN related I functions if the conditions stated in the appropriate sections of the ODCM are met. . 1 The communication requirements for the MCR ARPR LAN will be satisfied if communication is verified at either the IH13-P864 terminal or the IHI3-P870 terminal with either terminal being designated as the Master Terminal.. In the.

event communication .cannot be verified at either the IH13-P864 or the lHI3-P870 terminals, communication with the MCR ARPR LAN requirements* can be satisfied using the a

TSC terminal if the TSC terminal. is manned continuously, if direct/constant communication is established with MCR personnel, and the TSC terminal has been designated as the Master Terminal. Channel Functional Test/Calibration requirements can be satisfied at the 1H13-P864 terminal if terminal IH13-P870,is designated as theMaster*

Terminal. The TSC terminal may also be used to satisfy Channel Functional Test/Calibration requirements if the requirements previouslylgiven for use of this terminal are met..

Immediate Completion Time 1.1.15 When "IMMEDIATELY" is used'as a Completion Time, the COMPLETION TIME. Required Action should be pursued. without delay and in a controlled manner.,

1.2 General Operation Requirements 1.2.1 Operation Requirements shall be met during the conditions specified therein; except as provided in Operation Requirement 1.2.2.

1.2.2 Upon discovery of a failure to meet an Operation Requirement', the REMEDIAL REQUIREMENT(s) shall be met, except a's provided in 1.2.3.

I If the Operation Requirement is met or is no longer applicable prior to expiration of the REMEDIAL U

REQUIREMENT(s), completion of the REMEDIAL REQUIREMENT(s) is not required, unless otherwise stated.

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CY-CL-170-301 Revision 22 Page 17 of 195 1.2.3 Equipment removed from service' or declared' inoperable to comply-with REMEDIAL REQUIREMENT(s)- may be-returned to service under administrative control solely to perform testing required to demonstrate OPERABILITY or the OPERABILITY of other equipment. This' is an exception to

OPERATION REQUIREMENT 1.2.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

1.3 General Surveillance Requirements 1.3.1 Surveillance Requirements shall be met during the applicable conditions specified *in and for the associated Operation Requirement', unless otherwise stated in the Surveillance Requirement. Failure to meet a Surveillance, whether such failure is experienced during

• the performance of the surveillance, or between performances of the Surveillance, shall be failure to meet the Operation ,Requi'rement.

1.3.2 The specified 'survei~llance interval for each Surveillance Requirement is met if the' Surveillance is performed within 1.25'times*the .speci'fied': surveillance intervial, as measured from the previous'performance or as measured from the time a specified condition of the Surveillance Requirement is met.

For surveillance intervals specified as "once", the above interval extension does not apply.

If a REMEDIAL REQUIREMENT requires periodic performance on a "once per ... " basis, the above surveillance interval extension applies to each performance after the initial performance.

Exceptions to this Surveillance Requirement are stated in the. individual Surveillance Requirement:s.

Failure to perform a surveillance within t'he specified time interval shall be a failure to meet the Operation Requirement except as provided in Surveillance Requirement 1.3.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

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CY-CL-170-301 Revision 22 Page 18 of 195 1.3.3 If it is discovered that a surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare ,the _

Operational Requirement not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to. the limit of the specified interval, which ever is less. This 'delay period is to allow performance of the surveillan'ce.

If the surveillance is' not performed within the delay period, the Operational Requirement must immediately be declared not met, and the applicable REMEDIAL REQUIREMENTS must be met.

1.4 Effluent Concentration Limit Requirements .

(ECL)

Calculation, 5

1.4.1 Ten times the values found in 10CFR20 AppendixB, Table 2, Column 2 shall be used for all ECL calculations in the ODCM. For dissolved or~entrained noble-gases, the concentration shall be .limited to 2.0 x .10- 4 microcuries/ml I

total activity. TAL ll T A BL E ,- 1 1 - .

SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once *per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W 'At least once per 7 days.

M At least once per 31 days.

Q At least-once per 92 days. £ SA. At least once per 1i 84 days.

A At least once per 366 days,.

R At least once per 18 months '(550 days)

R24 At least once per 24 months (732 days)

P Prior to each release.

S/U Prior to each reactor startup.

NA Not applicable.

Note: A frequency notation for a composite sample describes the time period over which the sample is to be composited.

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CY-CL-170-301 Revision 22 Page 19 of 195 2.0 LIQUID EFFLUENTS 2.1 Introduction Liquid radwaste effluent released from CPS will meet ten times the 10CFR20 concentration limits'at the point of discharge to the unrestricted area shown in Figure 2.1-1.

This design and operation objective will be achieved at all times. Actual discharges of liquid radwaste effluent will normally occur on a batch basis and the average concentration at the point of discharge will be only a small percentage of the allowed limits. Refer to Clinton USAR Section 11.5 for a description.of. radiation monitoring, sampling and effluent control systems.

Cumulativequarterly dose contributions due to radioactive effluents released to-the unrestricted area will .be determined once every 31 days using NUREG-0133

• and Regulatory Guide 1.109 methodology and parameters during periods when liquid effluent activity exceeds the Lower Limit of Detection (LLD)' values.

2.2 Liquid Radwaste Discharge Pr6cess Radiation Monitoring (PRM) System This monitoring subsystem measures liquid radwaste effluent radioactivity prior to the effluent joining plant 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 flow, variable from 10,-60 GPM or 50-300 GPM, combines with Plant Service Water flow (minimum flow approximately 2000 GPM during plant shutdown periods depending on system loads) and Plant Circulating Water flow (0-567,000 GPM) in the Seal Well prior to entering the 3.4-mile discharge flume to Lake Clinton (see Figure 2.5-1).

2.3 10CFR20 Release Rate Limits The Operation and Surveillance Requirements pertaining to discharge of' liquid radwaste effluent to the unrestricted area are specified in Section 2.3.1 as follows.

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CY-CL-170-301 Revision 22 Page 20 of 195 2.3.1 Liquid Effluent Concentration - Operation and Surveillance Requirements OPERATION REQUIREMENT The concentration of radioactive material released in liquid effluent to UNRESTRICTED AREAS (see Figure 2.1-1) shall be limited to ten times the concentrations1:

specified in 10CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the.

concentration shall be limited to 2.OOE-04 microcuries/ml total activity. :This requirement applies during, all releases via this pathway.

REMEDIAL REQUIREMENT:

With the concentration of radioactive material released g in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. I SURVEILLANCE REQUIREMENTS 2.3.1.1 Radioactive liquid wastes shall be sampled'and analyzed according to the sampling and analysis program of Table I

2.3-1. .. .

2.3.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters of Section 2.3.2 to assure that the concentrations at the point of release are maintained within the limits of the above Operation Requirement.,

To comply with the above requirements, setpoints will be calculatedto assure that Seal Well concentrations do not exceed the OPERATIONAL REQUIREMENTspecified in section 2.3.1.

I I

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CY-CL-170-301 Revision 22 Page 21 of 195 TABLE 2.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT LIQUID.... ,MINIMUM OF DETECTION RELEASE SAMPLING ANALYSIS' TYPE OF ACTIVITY (LLD )a TYPE*. FREQUENCY FREQUENCY -ANALYSIS (JiCi/ml)

Batch Waste P P Principal Gamma *5. OOE-07 Release Each Batch EachBatch Emittersc Tanksb 1-131 <1. OOE-06 P, M' Dissolved and *l.00E-05 One Batch/M Entrained Gasese (Gamma Emitters)

P Q. H-3 *I.00E-05 Each Batch Composited Gross Alpha *!.00E-07 P Q Sr.-89, Sr-90 *5. OOE-08 Each Batch Composited Fe, 5 5 <1. OOE-06 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 22 of 195 TABLE 2.3-1 (Continued) I RADIOACTIVE..LIQUID WASTE SAMPLING AND ANALYSISPROGRAM

, TABLE NOTATIONS n aThe LLD is defined, for-purposes of these requirements,:as 'the,.

smallest concentration of radioactive material in a. sample'that will yield a net count, *aboye system background, that wi-ll' be 1

detected with 95%. probability with only 5% probability of:ýfalsely concluding that a blank observation represents a "real" signal.

For a particular measurements system,- which may include' radiochemical separation: .

(-XAt)

LLD = 4.66 Sb/[E x V x 2.22E+06 x Y x exp XA.t)j Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, "

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute:'

I E'is the counting efficiency, as counts per disintegration, 3 V is the sample size in units of mass or volume, 2.22E+06 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide (sec-1) and I At for plant effluents is the elapsed time between the midpoint of sample collection and the midpoint of the counting interval (sec).

I Typical values of E, calculation.

V, Y and At should be used in the I CLINTON '-- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 23 of 195 TABLE 2.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (Continued)

It should be recognized that the LLD is defined as an a priori (before-the-fact) limit representing the-capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

bA batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, the tank is isolated from all inputs and recirculated a minimum of two tank volumes at which time a sample is obtained for isotopic analysis.

The principal gamma emitters are: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of *5.OOE-06 JCi/ml. All identified radionuclides shall be reported in the Radioactive Effluent Release Report pursuant to Technica' lSpecification 5.6.3 in a format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

e Dissolved and Entrained gases are: Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88.

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CY-CL-170-301 I

Revision 22 Page 24 of 195 2.3.2 Liquid Radwaste Discharge PRM Setpoints .I To comply with theOperation Requirements of Section 2.3.1 and Section 2.7.1, the alarm/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is i

satisfied: ,

cf/(F f < -).

ECL (1)

ECL the Effluent Concentration Limit (Section 2.3.1) implementing 10 times the effluent concentration limit of 10CFR20, Appendix B, Table 2, Column 2 and corresponding to the specific mix of radionuclides in the effluent stream being considered, in gCi/ml.

c = thesetpoint, in of the radioactivity oci/mi, monitor measuring the radioactivity concentration in'the effluent line prior to dilutionland, subsequent release.; the setpoint is inversely, proportional to the volumetric flow of the effluentline and proportional to the volumetric flow of the dilution stream(s)I plus the effluent stream.

F = the dilution water flow setpoints as determined at the Seal Well, in volume per

-unit time *  :

f = the liquid radwaste discharge flowsetpoint .

as determined at the liquid radwaste discharge PRM location, in volume per unit time (same units as F) .

The available dilution water flow (F) should be constant for a given release, and the liquid radwaste tank discharge flow (f) and monitor setpoint (c) are set to meet the condition of equation (1) for a given effluent concentration (ECL). The method by which this is accomplished is illustrated in sections 2.3.2.1 through 2.3.2.5.

2.3.2.1 The isotopic concentration for a liquid radwaste tank ii to be discharged is obtained from the sum of the measured concentrations as determined by the analyses required in Table 2.3-1:

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CY-CL-170-301 Revision 22 Page 25 of 195 XiCi=XgCg+yaCa+zSCs+CT+CFe, 9Ci/ml (2)'

where XgCg = The sum of concentrations Cg of* each measured gamma emitter g (including Il31) observed by gamma spectroscopy of..the waste sample, gCi/ml.

XaCa = The sum of concentrations Ca of alpha emitters (a) in liquid radwaste as measured in the most current QUARTERLY composite discharge tank sample, gCi/ml.

. sCs = The sum of concentrations C, of Sr-89/Sr-90 in

. ' liquid radwaste as observed in the most current QUARTERLY composite discharge tank sample,

- 'Ci/ml.

CT = The measured concentration of H-3 in liquid radwaste as determined from analysis of the most current QUARTERLY composite discharge tank

sample, gci/ml..

CFe = The measured concentration of Fe-55 in liquid radwaste as; observed'in the most current

QUARTERLY composite discharge tank sample, pCi/ml.

2.3.2.2 The measured radionuclide concentrations are used to calculate a DILUTION FACTOR (DF) which is equivalent to the ratio of total dilution flow rate to liquid radwaste tank effluent flow, rate required to assure that the limiting concentrations specified in Operational Requirement 2.3.1 are met at the point of discharge to the unrestricted, area.-.

Dreq,g = X Ci i=g ECLi f

• Rmax.

Dreq, ng= " Ci i=ng ECLi f

• Rmax Dreq = Dreq,g + Dreq,ng (3)

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CY-CL-170-301 U

Revision 22 Page 26 of 195 where '

Dreq,g = Required dilution factor for gamma emitters Dreq,ng = Required dilution factor for non-gamma emitters 3 ECLi Effluent concentration limit of nuclide i in 4Ci/ml equal to 10 times the values in 10CFR20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration is limited to 2.00E-04 gCi/ml. I f = Release point safety factor Rmax = The maximum ECL ratio from the release point setpoint definition C1 = The concentration of nuclide i in gCi/ml SF = The conservative SAFETY FACTOR normally applied to compensate for statistical measurement errors, dimensionless.

fluctuations and 1 2.3.2.3 The maximum permissible liquid radwaste tank effluent flow rate, Rewmax, is calculated by the following equation:

I Rcwmax,= Favail -

Dreq (falloc

• Fwaste)_, vqlume/time (4) I where Rcwmax = Maximum waste flow rate Favail = Minimum expected dilution water flow rate (Circulating, and/or Service Water systems), volume/time falloc= 0.9 = Flow rate correction factor to provide a 10% margin for variations in flow rates, dimensionless Fwaste Maximum expected liquid radwaste tank effluent flow rate, volume/time The DILUTION FACTOR calculated by equation Dreq =

dimensionless (3),

I Equation (4) is valid only for DF>l. For DF<l, the liquid radwaste tank effluent concentration meets the limits of Operational Requirement 2.3.1 without dilution and therefore Rceax may assume any value not to exceed discharge pump capacity.

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CY-CL-170-301 Revision 22 Page 27 of 195 2.3.2..4 The liquid radwaste discharge PRM setpoint may now be specified based on the values of ZXC+/- (Eq.2) and Rcwmax

.(Eq.4) which were determined to provide compliance with the concentration limits of Operational Requirement 2.3.1. The monitor response is primarily .a gamma response and the actual setpoint is therefore based on

• XgCg (Eq.2) . The monitor setpoint,..in. counts per minute (cpm), which corresponds to-the particular setpoint concentration, S,ax, 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 use of operational data is considered valid only if the integrity of laboratory methods of determination are proven more accurate than the monitor data.

The set point concentration, Smax, is obtained by the following equations:

Sadj' Rcwmax . (5)

.Fwast~e Smax Sadi

• XgCg (6) where Fwaste = The actual liquid radwaste effluent flow rate, volume/time Rcwmax and Fwaste are defined in section 2.3.2.3.

If Sadj >1, the value obtained for Smax is used to

-determine the monitor setpoint above background, ccpm,

from either of the two methods described above. In the case where Sadj <11 no release may be made using the existing discharge parameter values (Rcwmax, Fwaste)

The setpoint concentration is conservative, even if Rcwax is attainable, since the calculated flow rate contains the SAFETY FACTOR, dilution flow rate and liquid radwaste tank effluent flow rate margins.

2.3.2.5 To prevent spurious alarms, revise the Plant Service Water Effluent PRM setpoint to coincide with the setpoint concentration, Smax, calculated by equation (6). This setpoint is valid only during periods of actual liquid radwaste discharges.

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CY-CL-170-301 Revision 22 Page 28 of 195 FIGURE 2.1-1 UNRESTRICTED AREA BOUNDARY FOR LIQUID EFFLUENTS LEGEND

-- SITE BOUNDARY UNRESTRICTED'AREA AREA

• SPECIAL UNRESTRICTED AREA(See Note 1)

AREA WITHIN SITE BOUN[ DARY NOT OWNED BY IPC tESIDENCE (TYP)

NOTE 4

'NOTE 3 NOTES

1. THE AREA IN THE LAKE BETWEEN THE BUOYS AND THE EXCLUSION AREA BOUNDARY IS UNRESTRICTED AT THIS TIME.

BUT WILL BE CONTROLLED IF PLANT EFFLUENT CONDITIONS WARRANT CLOSURE.

2. LAND PARCEL NOT OWNED BY AMERGEN, INCLUDES RESIDENCES.

3. LAND PARCEL NOT OWNED BY AMERGEN, OIL COMPANY PIPELINE PUMPING STATION.

4. LAND PARCEL NOT OWNED BY AMERGEN, AGRICULTURAL USE.

5. THE LAKE SHORELINE IS APPROXIMATELY 690 FT. MSL ELEVATION LINE.

CLINTON -- UNIT #1 Rev.22 - 12/09

- m m -- - u. r.n -, .mm mm m -

CY-CL-170-301 Revision 22 Page 29 of 195 2.3.3 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 flume. If the plant service water system is in service then radioactive effluent monitoring is required. 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 Table 2.3-1.

If the weekly grab sample analys.is indicates the presence of contamination ,abve background, PRM setpoints will be established following section 2.3.2 methodology as follows: -

2.3.3.1 Perform section 2.3.2.2, solving equation (3) for DF using the appropriate.values in the concentration term from the grab. sample analysis.

2.3.3.2 A modified dilution'factor, DFm, must be determined so that available dilution flows may be apportioned among simultaneous discharge pathways. The modified dilution factor is defined as:

DFm, DF/FA (7) where FA is an administrative allocation factor which may be assigned anyrvalue between 0 and 1 under the condition that In (FA)fn < 1, (8) and where n = the number of liquid discharge pathways for which DF >1 and which are planned for simultaneous release. For simplicity, FA may be assigned the value 1/n. Calculate Rcwmax in equation (4) by substituting the value of DFm for Dreq and perform the calculation specified in section 2.3.2.4 to determine flow rate and PRM setpoints.

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2.3.4 Shutdown

Service Water (SX) Effluent PRM:Setpoints Shutdown Service Water, when initiated, ?is la potential continuous radioactive discharge pathway to the Ultimate-,Heat Sink l(UHS) (see Figure 2.5-2)-. SX effluent.sampling, analysis and setpoint establishment will beperformed as discussed for'the Plant:Service Water system in Section 2.3.3.

2.3.5 Fuel Pool Heat Exchanger Service Water Effluent PRM Setpoints The Fuel PoolHeat Exchanger Service Water, is normally supplied by:-the, Component Cooling Water (CCW) system (a closed loop system).. The Component Cooling Water system rejects-heat loads to the Plant Service Water system where radiation from intersystem leakage would be detected as described in section 2.3.3. Fuel Pool Heat Exchanger Service Water cooling may also be provided from the Safe Shutdown Service'Water System (SX) which is not a closed system. 'Effluent from the SX system is considered a potential radioactive discharge pathway' when SX replaces COmponent Cooling Water as the heat sink for the Fuel Pool heat exchangers. Samples are collected from the Component Cooling Water system on a weekly basis and analyzed as I

discussed in section.2.3.3.- This sample allows Component Cooling Water to be analyzed prior to placing the Fuel Pool Heat Exchanger. in the SX cooling mode.

This will account for a potential radioactive release to the UltimateiHeat Sink via SX. Discharge monitoring is performedany time a Fuel Pool Cooling heat exchanger is in service (FC water is flowing through I

the heat exchanger) AND the heat sink for the FC heat exchanger is being provided by SX. The analysis results may then be used to establish Fuel Pool Heat Exchanger Service,.Water PRM and flow rate setpoints following .Section 2.3.3.1 and 2.3.3.2 methodology.

Any releases of radioactivity to the environment from the Plant Service Water (except during liquid radwaste discharges.), Shutdown Service Water or Fuel Pool Heat Exchanger Service Water Systems are considered abnormal events. Such events will be accounted for as unplanned releases in the RADIOACTIVE EFFLUENT RELEASE REPORT.

I CLINTON-- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 31 of 195 2.3.6 Component Cooling Water*PRM Setpoints

,.The Component Cooling Water system"is'a potential continuous radioactive discharge pathway to the Service Water system due to the Component Cooling water system generally operating at a higher pressure and the

.,potential for heat exchanger tube leaks. Component Cooling provides cooling to components and heat exchangers that carry radioactive fluids or are in areas that could result in radioactive contamination if the components are damaged. Except for the sampling requirement described in 2.3.5, sampling on this system is done on an as needed basis.. The PRM setpoints are established using the methodology in Section 2.3.3.

2.4 ,- 10CFR50, Appendix I Dose Limits.

The OPeration and'Suriveillanc6 Requirements concerning 10CFR50, Appendix I Release Limits are specified in sect'ion.2.4.l. Dose calculations for ensuring compliance with these-jimits are. discussed in section 2.4.2.

2.4.1 loCFR5o, Appendix I Dose Limits - Operation-and Surveillance Requirements SOPERATION REQUIREMENT, The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in/liquid effluents released to UNRESTRICTED AREAS (see Figure 2.1-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body -and'to less than or equal to 5 mrem to any organ, and

b. During any calendar year-to less than or equal to 3 mrem to the total body 'and to less than or equal to 10 mrem to any organ.

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CY-CL-170-301 II Revision 22 Page 32 of 195 I This requirement applies at all times.

REMEDIAL REQUIREMENT:

I With the calculated dose from the release ofi radioactive materials in liquid effluents exceeding any I

of the above limits, prepare and submit to the Regional Administrator of the Regional Office of the NRC within 30 days a Special Report that identifies the cause(s)

II for exceeding the limit(s) and defines the corrective actions thathave been taken to reduce the releases and the proposed, corrective actions to be taken to assure I that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS.

I 2.4.1.1 Cumulative dose contributions from liquid effluents for the current caihndar quafter and the, current calendar I

year shall be determined in accordance with the methodology and parameters described in Section 2.4.2 at least once per 31 days.,

I II a

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CY-CL-170-301 Revision 22 Page 33 of 195 2.4.2 Discussion 2.4.2.1 The dose contribution to the maximumexposed individual from all radionuclides identified in liquid effluents released to the unrestricted area is calculated as follows:

De Ale I Ats

• i *Fsr, mrem (9) where Dj = The cumulative calendar quarter or yearly dose to any organ j from liquideffluent for the total release period, mrem' At, = The length of time .s.. over which Cis_ and Fsr

.. are averaged for liquid releases, hours

" Liquid Radwaste Tank Volume/Liquid Radwas te Discharge Flow Rate..

Cis= The'average concentratioh of nuclide i for time period s in undiluted- liquid effluent during release period Ats for any liquid release, g Ci/ml Fsr = The near field average dilution factor for receptor r during any liquid effluent release, dimensionless. 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 (during the reporting period, i.e., quarter or year) to the unrestricted receiving water and Z

= Average Undiluted Liquid Waste Flow (10)

(Average Discharge Structure Flow)Z Z = The applicable dilution factor for Lake Clinton, dimensionless

= 1.0 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 34 of 195 Aij The composite ingestion dose commitment factor

,for. the total body or criticalorgan j of an ADULT for radionuclide i, mrem/hr per gCi/ml K.

K[(Uw/Dw) + (UfBFI)]DFi . (11) where 3 Ko = A units conversion factor, 1.14E+05 pCi-ml-yr/

gCi-liter-hr 5

= (1.OOE+06 pCi/gCi) (I.00E+03 ml/liter)/8760 hr/yr Uw = Annual water consumption by the maximum adult, 0 liter/yr..'

Dw Dilution factor from the near field area to the nearest!potable water intake, 1.0 Uf = Adult fish _.consumption rate, 21 kg/yr '(Table .

E-5 of RegulatoryGuide 1.109)

BFi = .Bioaccumulation factor for radionuclide i in ,

fish, pCi/kg per pci/liter (Table 2.4-2 taken from Table-A-i of Regulatory Guide 1.109)

DFi = Adult ingestion dose conversion factor for radionuclide i, total body or critical organ,.

mrem/pci (Table 2.4-3 taken from Table E-11 of Regulatory Guide 1.109)

Table 2. 4-1 contains values for Aij as calculated by.

equatiohn-ll (11)

The quarterly limits specified in the OPERATION REQUIREMENT at the beginning of this section represent one-half of the annual design objective of Section II.A I

of !1CFR50, Appendix I. .

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CY-CL-170-301 Revision 22 Page 35 of 195 TABLE 2.4-1 ADULT INGESTION DOSE COMMITMENT FACTORS - Aij (mrem/hr per ýtCi/ml) ,

ISOTOPE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 11-3 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 4.065E+02 4.06E+02 4.06E+02 P-32 1.39E+06 8.62E+04 5.36E+04 NO DATA NO DATA NO DATA 1.56E+05 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 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 4.67E+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 '5.23E501, 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 1E-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 1.94E+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 Y-91mn 5.43E-0,3 NO DATA 2.10E-04 NO DATA NO DATA NO DATA 1.60E-02 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 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 MO-99 NO DATA 1.03E+02 1.96E+01 NO DATA 2.33E5+/-02, NO DATA 2.39E+02 TC-99m 8.86E-03 2.50E-02 3.19E-01 NO DATA 3.80E501

• 1.23E-02 1.48E+01 TCý-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 RU-105 3.68E-01 NO DATA 1.45E-01 NO DATA 4.76E+00 NO DATA 2. 25E+02 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 TE-12Sm 2 .57E+03 9. 28E+02 3.43E+02 7.70E+02 1.04E+04 NO DATA 1. 02E+04 TE-127m 6 .47E+03 2.31E+03 7. 89E+02 1.65E+03 2.63E+04 NO DATA 2 . 17E+04 TE-127 1. 05E+02 3 .77E+01 2 . 28E+01 7.79E+01 4. 28E+02 NO DATA 8 .30E+03 TE-129m 1. 10E+04 4.10E+03 1.74E+03 3. 78E+03 4.59E+04 NO DATA 5. 54E+04 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 S . 95E+00 1.55E+01 8.25E+01 NO DATA 2. 67E+00 CLINTON -- UNIT #1 Rev.22 -

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Revision 22 Page 36 of 195 II TABLE 2.4-1 (cont'd)

ADULT INGESTION DOSE COMMITMENT FACTORS - Aij II ISOTOPE BONE LIVER (mrem/hr per gCi/ml)

T. BODY THYROID KIDNEY LUNG GI-LLI II TE-132 2.41E+03 1,. 56E+03 1. 46E+03 1.72E+03 1.50E+04 NO DATA 7.37E+04 1-130 1-131 1-132

2. 71E+01 1 .49E+02

7. 28E+00 7 .99E+01 2 .13E+02

1. 95E+01

3. 15E+01

1. 22E+02

6. 81E+00 6.78E+03 6.99E+04 6.81E+02 1.25E+02

3. 66E+02

3. 10E+01 NO DATA NO DATA NO DATA

6. 88E+01

5. 63E+01 3 . 66E+00 I

1-133 5 09E+01 8. 85E+01 2. 70E+01 1.30E+04 1.54E+02 U

NO DATA 7. 96E+01 1-134 3. 80E+00 1.'03E+01 3 . 69E+00 1.79E+02 1. 64E+01 NO DATA 9. OOE-03 1-135 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 CS-137 CS-138 BA-139

3. 11E+04 3 .81E+05 2 64E+02

9. 29E-01 1.23E+05 5.21E+05 5.21E+02 6.60E-04 8 .84E+04 3 .41E+05 2 . 58E+02 2 . 72E- 02 NO DATA NO DATA NO DATA NO DATA 6.84E+04 1.77E+05 3 . 83E+02

9. 37E+03

5. 88E+04 3.78E+01

1. 40E+04

1. 01E+04

2. 22E-03 I

6. 18E-04 S3. 75E-04 1. 65E+00 BA-140 BA-141 BA-142

1. 94E+02 4 50E-01 2 .04E-01 2.44E-01 3.40E-04 2.09E-04 1.27E+01 1.52E-02 1.28E-02 NO DATA NO DATA NO DATA

8. 29E-02 3.16E-04

1. 77E-04 1.40E-01 1.93E-04 1.18E-04

4. 00E+02

2. 12E-10 2 89E-19 I

LA- 140 1 .49E-01 7. 53E-02 1. 99E-02 NO DATA NO DATA NO DATA 5 . 53E+03 LA-142 CE-141 CE-143

7. 65E-03 2 .24E-02

3. 94E-03 3.48E-03

1. 51E-02 2.92E+00 8.66E-04 1.72E-03 3 .23E-04 NO DATA NO DATA NO DATA NO DATA

7. 03E-03 1.28E-03

.NO DATA NO DATA NO DATA 2 54E+01

5. 78E+01

1. 09E+02 I

CE-144 1. 17E+00 4.88E-01 6.26E-02 NO DATA 2.89E-01 NO DATA 3 .94E+02 PR-143 PR-144 ND-147

5. 50E-01 1.80E-03

3. 76E-01 2.20E-01

7. 47E- 04 4.34E701 2.72E-02

9. 14E-05 2.60E-02 NO DATA NO DATA NO DATA

1. 27E-01 4 .21E-04 2.54E-01 NO DATA NO DATA NO DATA 2 .41E+03

2. 59E-10 2.08E+03 1

W-187 2 .95E+02 2..47E+02 8 . 63E+01 NO DATA NO DATA NO DATA 8 . 09E+04 NP-239

• 3 .12E+04

2. 84E-02 2.80E-'03 1.54E-03 NO DATA 8.72E-03 NO DATA 5. 74E+02 I

• • Less than 1.OOE-15 I

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CY-CL-170-301 Revision 22 Page 37 of 195 TABLE 2.4-2 BIOACCUMULATION FACTORS -BFi.

(pCi/kg per pCi/liter)

FRESHWATER ELEMENT H 9. OOE-o1 C 4.60E+03 Na 1. 0OE+02 P 1 o00E+05 Cr 2.OOE+02 Mn 4. OOE+02 Fe. 1.O0E+02 Co. 5.OOE+01 Ni 1. OOE+02 Cu. 5.: OOE+01 Zn 2 OOE+03 Br 4 20E+02 Rb . 2 OOE+03

.Sr 3 OOE+01 Y 2 50E+01 Zr 3 .30E+00 Nb 3. OOE+04 Mo 1. 00E+01 Tc 1.50E+01 Ru 1. OOE+01 Rh 1. OOE+01 Te 4 OOE+02 I 1. 50E+01 Cs 2 OOE+03 Ba 4 OOE+00 La 2. 50E+01 Ce 1 OOE+00 Pr 2.50E+01 Nd 2. 50E+01 W 1.20E+03 Np 1. OOE+01 CLINTON -- UNIT #1 Rev.22 -

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TABLE 2.4-3 I ADULT INGESTION DOSE FACTORS -DFi (mrem/pCi ingested) I ISOTOPE BONE LI-VER T. BODY THYROID KIDNEY LUNG I GI-LLI' H-3 C-14 NA-24 NO DATA 2.84E-06*

1.70E-06 1 .0 5E -07

.5. 68E-07

1. 70E-06, 1.05E-07

5. 68E-07

1. 70E-06 1.05E-07 5.68E-07 1.70E-06

1. 05E-07 5.68E-07 1.70E-06 1.05E-07 5,.68E-07 1.70E-06 1.05E-07 5.68E-07 1.:70E-06 U

P-32 CR-51 MN-54

1. 93E-04 NO DATA NO DATA

1. 20E-05 NO DATA

4. 57E-06 7 .46E-06

2. 66E-09

8. 72E-07 NO DATA 1.59E-09 NO DATA NO DATA

5. 86E-10 I..36E-06 NO.DATA 3.53E-09 NO DATA 2.17E-05 6.69E-07 1.40E-05 g

MN- 56 NO DATA 1. 15E-07 2 04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE-55 FE-59 CO-58 2 .75E-06 4.34E-06 NO DATA 1 .90E-06

1. 02E-05 7.45E-07

'4 .43E-07

3. 91E-06 1.67E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA*

1.06E-06 2.85E-06 NO DATA 1.09E-06 3.40E-05 1.51E-05 I

CO-60 NO DATA 2 .14E-06 .4.72E-06 NO DATA NO DATA- NO: DATA 4,.02E-05 NI-63 NI-65 CU-64 1.30E-04 5.28E-07 NO DATA

9. 01E-06 6.86E-08 8 .33E-08,,

4. 36E-06 3.13E-08 3.91E-08 NO-DATA NO DATA NO DATA'

NO DATA NO DATA 2.10E-07; NO DATA NO'DATA

'NO DATA 1.88E-06 1.74E-06

7. 10E-06 gI ZN-65 4.84E-06 1.54E-05.- - 6.96E-06 NO DATA 1.03E-05 NO DATA 9 .70E-06 ZN-69 BR-83 BR-84 1.03E-08 NO DATA NO DATA 1.97E-08 NO DATA, NO DATA 1.37E-09

-4.02E-08 5.21E-08 NO DATA NO DATA NODATA

.1 .28E-08 NO DATA NO DATA, NO DATA NO DATA NO DATA 2 .96E-09

5. 79E-08

4. 09E-13 U

BR-85 NO DATA NO DATA .2.':14E-09 NO DATA NO DATA NO DATA LT 1E-24**

RB-86 RB-88 RB-89 NO DATA NO DATA NO DATA

.2.11E-05'.

6.05E-08 4,01-E08 j9.83E-06 3.21E-08.

%2.82E-08 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 4.16E-06 8.36E-19 2.33E-21 I

SR-89 3:08E-04 NO DATA .8.84E-06 NO DATA NO.DATA NO DATA 4.94E-05 SR-90 SR-91 SR-92 7.58E-03 5.67E-06

2. 15E-06 NO DATA NO DATA NO DATA

.1.86E-03 2.29E-07 9.30E-08 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 2.19E-04 2.70E-05 4.26E-05 I

Y-90 Y-91m Y-91 9.62E-09 9.09E-11 1.41E-07 NO DATA NO DATA NO DATA NO DATA

2. 58E-10 3.52E-12 3.77E-09 2.47E-11 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 1.02E-04

.2.67E-10 7.76E-05 U

Y-92 8.45E-10 NO DATA NO DATA 1.48E-0S NO DATA Y-93 ZR-95 ZR-97 2.68E-09 3 .04E-08 1.68E-09 NO DATA 9.75E-09 3.39E-10 7.40E-11 6.60E-09 1.55E-10 NO DATA NO DATA NO DATA 1.53E-08

5. 12E-10 NO DATA NO DATA NO DATA 8.SOE-05 3.09E-05 1.05E-04 II NB-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3 .42E-09 NO DATA 2.10E-05 MO-99 TC-99m TC-101 NO DATA 2.47E-10 2 .54E-10

4. 31E-06 6.98E-10 3 . 66E-10 8.20E-07 8.89E-09 3 .59E-09 NO DATA NO DATA NO DATA 9.76E-06

1. 06E-08 6.59E-09 NO DATA 3.42E-10 1.87E-10 9.99E-06 4.13E-07 1.10E-21 U

RU-103 1.85E-07 NO DATA 7 .97E-08 NO DATA 7.06E-07 NO DATA 2.16E-0S RU-105 RU-106 AG-110m 1.54E-08 2.75E-06 1.60E-07 NO DATA NO DATA 1.48E-07

6. 08E-09 3.48E-07

8. 79E-08 NO DATA NO DATA NO DATA 1.99E-07 5.31E-06 2 .91E-07 NO DATA NO DATA NO DATA 9.42E-06 1.78E-04 6.04E-05 TE-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1. 09E-05 NO DATA 1.07E-05 TE-127m 6.77E-06 2.42E-06 8 .25E-07 1.73E-06 2. 75E-05 NO DATA 2.27E-05 TE-127 1.10E-07 3.95E-08 2. 38E-08 8. 15E-08 4.48E-07 NO DATA 8.68E-06 I TE-129m 1.1SE-05 4.29E-06 1. 82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE-131m 1.73E-06 8.46E-07 7. 05E-07 1.34E-06 8. 57E-06 NO DATA 8.40E-05 TE-131 1.97E-08 8.23E-09 6 .22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 I

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CY-CL-170-301 Revision 22 Page 39 of 195 TABLE 2.4-3 (cont'd)

ADULT INGESTION DOSE FACTORS -,DFi (mrem/pCi ingested)

ISOTOPE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI TE-132 2.52E-06 1. 63E-06 1.53E-06 1.80E-06 1. 57E-05 NO DATA 7.71E-05 1-130 7. 56E-07 2. 23E-06 8.80E-07 1.895-04 3 .48E-06 NO DATA 1.92E-06 131 4.16E-06 5. 95E-06 3 .41E-06 1.95E-03 1. 02E-05 NO DATA 1.57E-06 I -132 *2 .03E-07 5. 43E-07 1. 90E-07 1.90E-05 8 65E-07 NO DATA 1.02E-07 1-133 1.42E-06 2 .47E-06 7.53E-07 3.63E-04 4 31E-06 NO DATA 2.22E-06

.1-134 I. 06E-07 2 .88E-07 1.03E-07 4.99E-06 4. 58E-07 NO DATA 2.51E-10 1-135 4 .43E-07 1. 16E-06 4.28E-07 7.65E-05 1. 86E-06 NO DATA 1.31E-06 CS-134 6ý. 22E-05 1.48E-04 1.21E NO DATA 4 .79E-05 1.59E-05 2 .59E-06 CS-136 6. 51E-06 2 . 57E-05 1. 85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS-137 7. 97E-05 1. 09E-04 7. 14E- 05 NO DATA 3. 70E-05 1.23E-OS 2. 11E-06

CS-138 5'.52E-08 1. 09E-07 5 .40E-08 NO DATA 8. 01E-08 7. 91E-09 4o.65E-13 BA-139 9s 70E-08 6.91E-11 2 .84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA-140 2 . 03E-05 2. 55E-08 1.33E-06 NO DATA 8. 67E-09 1.46E-08 4. 18E-05

,BA- 141 4.71E- 08 3.56E-li 1.59E-09 NO' DATA 3.31E-11 2. 02E-11 2 .22E-17 1BA-142 :2.13E-08: 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00-E26 LA-140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA' 9.25E-0S LA-142 1.28E-10 '5.82E-11 1.45E-11 :NO DATA NO DATA NO DATA 4.25E-07 CE-141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE-143 1.65E-09 1.22E-06, 1.35E-10 NO DATA 5.37E-10 NO DATA 4.S6E-05 CE-144 4.88E-07 .2.04E-07 2.62E-08 'NO DATA 1.21E-07 NO DATA 1.65E-04 PR-143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR-144 3,.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND-147 6.29E-09 7.27E-09 4.35E-10. NO DATA 4.25E-09 NO DATA 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP-239 1.19E-09 1.17E-10 6.45E-11 NO'DATA 3. 65E-10 NO DATA 2.40E-05

• 2.84E-06

• • Less than 1.00E-24 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 g

Revision 22 Page 40 of 195 i

FIGURE 2.5-1 g LIQUID RADWASTE.TREATMENT SYSTEM gI g

0 I U

g U

U I

I I

• Monitors required by Section 2.7 WF01S Floor Drain OWZ01P Chem. Wst. 2WF04T Floor Drain OWE02PAB, and C I

Evaporator Evap. Tank Pump WF01S Floor Drain OWE01FA,B, and C Evaporator Tank 0WZ01T Chem. Waste Waste Samp. Tk Pumps OWE01TA and B.

gI Evaporator Waste Filters OWZ01S Chemical Waste Evaporator OWE01DA,B, and C Waste Demins Evaporator Tank 1WF04P Flr. Drn.

Evap. Tank Pump Excess Water Tanks OWE01PA and B Excess Water Tank II WF04T Floor Drain Evaporator Tank 0WE02TA,B, and.C 2WF04P Flr. Drn.

Pumps 1PR036 Service U

Waste Sample Tks. Evap. Tank Pump Water PRM OPRO40 Liquid RW Discharge PRM I

I CLINTON -- UNIT #1 12/09 Rev.22 -

i

CY-CL-170-301 Revision 22 Page 41 of 195 FIGURE 2.5-2 SHUTDOWN AND.FUEL POOL HEAT EXCHANGER SERVICE WATER EFFLUENT MONITORS SHUTDOWN SHUTDOWN SERVICE SERVICE WATER WATER EXCHANGER "A" ULTIMATE

-HEAT FUEL POOL HEAT SHUTDOWN SHUTDOWN EXCHANGER SERVICE SERVICE WATER SINK SERVICE WATER WATER PRM LOOP "A" OTHER SYSTEM EFFLUENT "A" 1RIX-PRO04*

LOADS IRIX,-PRO38*

COMPONENT COMPONENT COOLING COOLING WATER WATER 1RIX-PR037 OTHER SYSTEM SHUTDOWN ULTIMATE SHUTDOWN LOADS .SERVICE WATER -HEAT FUEL POOL HEAT SERVICE WATER .EFFLUENT "B" EXCHANGER SERVICE SINK LOOP "B" 1RIX-PRO39* WATER PRM lRIX-PROOS*

SHUTDOWN SHLUTDOWN SEPRVICE RHR HEAT "B" SEXCHANGER T SERVICE WATER WAI 'ER

- NORMAL COOLING SUPPLY - COMPONENT COOLING WATER EMERGENCY COOLING SUPPLY - SHUTDOWN SERVICE WATER

• Monitors required by Section 2..7 lRIX-PRO38. Shutdown Service IRIX-PRO05 Fuel. Pool Heat Water Effluent.."A" Exchanger Service Water PRM lRIX-PR039 Shutdown Service 1RIX-PRO04 Fuel Pool Heat Water Effluent "B" Exchanger Service Water PRM lRIX-PR037 Component Cooling Water CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 42 of 195 FIGURE 2.5-3 SOLID RADWASTE SYSTEM SIMPLIFIED FLOW DIAGRAM OFFSITE BURIAL WASTE DEMINERALIZER DRY RADIOACTIVE WASTE FLOOR DRAIN EVAPORATOR BOTTOMS CHEMICAL WASTE EVAPORATOR BOTTOMS CLINTON -- UNIT #1 Rev.22 - 12/09 m- mm mm m m m m m m mm = m m m

CY-CL-170-301 Revision 22 Page 43 of 195 2.5 Liquid Radwaste Treatment System 2.5.1 Liquid Radwaste Treatment System - Operation and Surveillance Requirements OPERATION REQUIREMENT The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the-system (Figure 2.5-1) shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure 2.1-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period. This requirement applies at all times.

REMEDIAL REQUIREMENT:.

With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation prepare and submit to the Regional Administrator of the Regional Office of the NRC within 30 days a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable

,equipment or subsystems, and the reason for the

,inoperability.

2. Action(s) taken to restore the inoperable equipment to

OPERABLE status, and

3. 'Summary description of action(s) taken to prevent a

'recurrence.

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CY-CL-170-301 I

Revision 22 Page 44 of 195 SURVEILLANCE REQUIREMENTS 5 2.5.1.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters described 'in equatibn:12.

Liquid Effluent Dose Projection Calculations-The 31 day projected dose shall be calculated using the following.equation 3

Dpj= (Dj

• p) + Daj (12) where:

Dpj = the 31 day projected dose by organ j.

Dj = totaldose (mrem) for all valid release points .

for the release period (usually quarter) by organ j. I p = the projection factor which is the results of 31 divided by the number of days from the start of the quarter to the end of. the release. i Daj = additional antic'ipated dose for liquid release by organ j and quarter of release.

2.5.1.2 The liquid radwaste treatment shall be demonstrated OPERABLE by meeting theOperation Requirements'of Section 2.3.1 and 2.4.1.

2.5.2 Temporary Liquid Radwaste Hold-Up Tanks The use of temporary liquid radwaste hold-up tanks may occur at CPS. To comply with Operational Requirements Manual (ORM) 2.4.4, the curie limit for liquid radwaste stored in U

such tanks may be calculated using the methodology presented in Appendix B'of NUREG-0133 (BWR-RATAFR code), but limited to less than or equal tol!0 curies, excluding tritium and dissolved or entrained noble gases.

2.6. Doses From Other Significant Liquid Effluent Pathways Section 2.4 of this manual is based upon the aquatic food and potable water exposure pathways only. Other exposure

,pathways, namely shoreline deposits and irrigated crops, may arise at Clinton power Station and will be included in the I

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 I

an additional dose increment greater than or equal to 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 the land use census or environmental monitoring I

information determine that other significant liquid effluent pathways are present, 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.

I CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 Revision 22 Page 45 of 195 2.7 Radioactive Liquid Effluent Monitoring Instrumentation 2.7'.1 Radioactive Liquid Effluent Monitoring Instrumentation -

Operation and Surveillance Requirements OPERATION REQUIREMENT The radioactive liquid effluent monitoting instrumentation channels shown in Table 2.7-1 shall% be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 2.3.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters described in

'Sections 2.3.2 through 2.3.5.

REMEDIAL REQUIREMENT:'

a. With a radioactive liquid effluent monitoring

'instrumentation chahnel alarm/trip setpoint less conservative than required by the above requirement, without delay suspend the release of radioactive liquid effluents monitored b.%the affected channel, or'declare the channel inoperable aind implement actions of requirement b below.

b. With less than the minimum-number of radioactive liquid effluent monitoring'instrumentation channels OPERABLE, comply with the REMEDIAL REQUIREMENT shown in Table

.2.7-1. Restore the inoperable. instruments to OPERABLE status within 30 days and,, if unsuccessful, explain in the next Radioactive Effluent'Relelase Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 2.7.1.1 Each-radioactive liquid effluent monitoring instrumentation control shall be demonstrated OPERABLE by performance of the CHANNEL CHECK; SOURCE -CHECK, !CHANNEL CALIBRATION and CHANNEL SFUNCTIONAL TEST at the frequencies shown in Table 2.7-2.

CLINTON -- UNIT #1 Rev.22 -12/09

-k CY-CL-170-301 Revision 22 Page 46 of 195 TABLE 2.7-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS REMEDIAL OPERABLE (e) REQUIREMENT APPLICABILITY

1. RADIOACTIVE MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Discharge Process Radiation 1(a) 1 (b)

Monitor (ORIX-PRO40)

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Plant Service Water Effluent.Process Radiation 1(a) 2 (c)

Monitor (IRIX-PR036)

b. Shutdown Service Water Effluent Process. Radiation l/Division* 2 (c)

Monitor (Div. 1: 1RIX-PR038 Div 2:ý IRIX-PRO39) (a)

c. Fuel Pool Heat Exchanger Service Water Radiationn 1/on service (c)

Monitor (Train A: 1RIX-PRO04 Train B: lRIX-PR005) heat 2

exchanger (a)

d. Component Cooling Water Process Radiation Monitor 1 (a) (c)

(IRIX-PR037)

3. FLOW RATE MEASUREMENT DEVICES (OUIX-PRo52),-

a. Liquid Radwaste Effluent Line (Channel l-Low, 3 (b)

Channel 2-High) 1

b. Plant Service Water Effluent Line (Channel 3) 1 3 (b)

c. Plant Circulation Water Line** (Channel 5) 3 (b)

4. TANK LEVEL INDICATING DEVICES 1i

a. Cycled Condensate Storage 4 (d)

(Meter Indication at panel 1H13-P870)

b. Reactor Core Isolation Cooling Storage 4 (d)

(Meter Indication at panel 1H13-P862)

• Division I and Division II only.

The plant circulation water (CW) flow rate measurement device is based upon the CW pump breaker position and an analog signal that specifies a preset flow rate.

CLINTON -- UNIT #1 Rev.22 - 12/09 M M M M m m- = m m m = m

= =`= = -

CY-CL-170-301

.Revision 22 Page 47 of 195 TABLE 2.7-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION (a)Channel OPERABILITY shall include the capability of the MCR ARPR LAN to provide the alarm status of the applicable radiation monitor channel(s).

(b)Required only during radioactive discharge.

(c)Any time system is in service.

(d)During additions to the tank (e)When a channel is placed in' an inoperable status solely for performance of required surveillances (source checks, sampling) entry into associated Remedial Requirements may be delayed for up to one hour.

REMEDIAL REQUIREMENT REMEDIAL With the number of channels OPERABLE less than REQUIREMENT required by the Minimum Channels OPERABLE 1 requirement, effluefht':releases may continue via this pathway provided that'prior to initiating a release:

a. At least two independent 'samples are analyzed in accordance with'Section 2.3.1.1, and

b. At least two technically qualified members independently verify the release rate calculations and discharge line valving:

Otherwise, suspend release of radioactive effluents via this pathway-CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 H

Revision 22 Page 48 of 195 I

REMEDIAL a. If the communication link or the MCR ARPR REQUIREMENT LAN is inoperable perform CHANNEL CHECK 2 using local monitor indication within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. I

b. With the monitor otherwise inoperable, effluent releases via this.pathway may g

continue provided that at least once per12 hours., grab samples are. collected and analyzed for radioactivity at a Lower Limit g

'of Detection-of *5.OOE-07 ICi/ml for the Principal Gamma Emitters. The Principal Gamma Emitters are: Mn-54, Fe-59, Co-58, Co- g 60,.

Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141.

Ce-144 shall' be measured with an LLD of

• 5.00E-06jJCi/*. Dissolved and Entrained Gases (gamma emitters only) shall be measured with an LLDpof *.i00E 5 gCi/ml. These Dissolved and Entrained Gases are: Xe-133, Xe-135,, Xe138,' Kr-85m, Kr-87,' and Kr-88.

I CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 49 of 195 TABLE 2.7-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION REMEDIAL With the number of channels OPERABLE less than REQUIREMENT required by the Minimum Channels OPERABLE 3 requirement, effluent releases via this pathway may continue provided the flow rate. is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump performance curves generated in place may be used to estimate flow. CW flow may also be estimated from the number of CW pumps in operation.

All flows diverted from. Plant Service Water must be taken into~account whensestimating dilution flow when Plant Service Water is the only dilution source.

REMEDIAL With the number ofichanhels OPERABLE less than REQUIREMENT required by the Minimum Channels OPERABLE 4 requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank.

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CY-CL-170-301 Revision 22 Page 50 of 195 TABLE 2.7-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Discharge Process Radiation Monitor Effluent Line P R(3) Q()

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Plant Service Water Effluent Process Radiation Monitor S(5) M R (3) 0(2)

b. Shutdown Service Water Effluent Process Radiation Monitor S(5) M R(3) Q(2)

c. Fuel Pool Heat Exchanger Service Water Radiation Monitor S(5) M R (3) Q(2)

d. Component Cooling Water Process Radiation Monitor' S(5) M R(3) Q(2)

CLINTON -- UNIT #1 Rev.22 - 12/09

- m - - - m m

= m

= - = = -

-I - " - m lr - m - m - - - - -- m -

CY-CL-170-301 Revision 22 Page 51 of 195 TABLE 2.7-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

3. FLOW RATE MEASUREMENT. DEVICES

a. Liquid Radwaste Effluent Line S(4) NA R Q

b. Plant Service Water Effluent Line S(4) NA R Q

c. Plant Circulation Water Line** S(4) NA N/A R

4. TANK LEVEL INDICATING.DEVICES

a. Cycled Condensate Storage NA R NA

b. Reactor Core Isolation Cooling NA R NA

• During liquid additions to-the tank.

• • The plant circulation water (CWY flow rate measurement device is based upon the CW pump breaker position. and an analog signal that specifies a preset flow rate.

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Revision 22 Page 52 of 195 II TABLE 2.7-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS I (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs and that the MCR ARPR LAN provides annunciation and event display in response to each of the following conditions:

1. Instrument indicates measured levels above the alarm/trip I' (HIGH) setpoint.

2. Detector failure (LOW FAIL, HI FAIL).

3. Sample flow failure (EXTERNAL FAIL) .

4. Instrument not set innormal operate mode MAINTENANCE, or STANDBY.)*

(CALIBRATE, I (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that the MCR ARPR LAN responds with annunciation and event display to each of the following conditions:

U

1. Instrument indicates measured levels above the alarm (HIGH) setpoint.

I

2. Detector failure (LOW FAIL, HI FAIL). I

3. Sample flow failure (EXTERNAL FAIL).

4. Instrument not set in normal operate mode (CALIBRATE, MAINTENANCE, or STANDBY.)

I I

O

• A demonstration of automatic isolation of the release pathway is not applicable to this condition.

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CY-CL-170-301 Revision 22 Page 53 of 195 TABLE 2.7-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology :(NTST) or using standards that have been obtained from-suppliers that participate in measurement assurance activities with NIST.

• These standards shall permit calibrating:the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of-.verifying indication ,of flow during periods of discharge. CHANNEL CHECKs are required when continUbus, periodic; or batch releases are made.

(5) The Channel Check performed from the MCR ARPR LAN also verifies communication.'

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CY-CL-170-301 II Revision 22 Page 54 of 195 3.0 GASEOUS:-EFFLUENTS 3.1 Introduction Gaseous-effluents from CPS are released on both a batch rand continuous basis. :Gaseous effluents are normally discharged ona long term basis. High volume Continuous Containment Purge and mechanical vacuum pump discharge may be considered short term releases.

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 (reference Table 9.2-1).

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 followinginputs::,

1) Continuous Containment Purge (CCP)

2) Containment Building Ventilation

3) Turbine Building Ventilation

4) Radwaste Building Ventilation

5) Auxiliary Building Ventilation

6) Fuel Building Ventilation

7) Auxiliary,,Building Refrigerant Purge

8) Laboratory Ventilation System

9) Counting/Equipment Decon Rooms Ventilation

10) Steam:Packing Exhauster

11) Mechanical VacuumPump

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 gaseous effluent 10CFR20 and 10CFR50, Appendix I Release Rate Limits.

I CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 55 of 195 3.2 Gaseous Effluent Release Point Monitoring 3.2.1 HVAC Stack Process Radiation Monitoring (PRM) System The HVAC Stack inputs are monitored for radioactivity prior, to discharge to the environment-by the HVAC Stack PRM. The PRM detector configuration provides effluent monitoring using nine (9) channels as follows:

i) Beta scintillator for particulates

2) Alpha surface barrier detector to account for the radon/thoron contribution to the beta particulate measurement

3) Gamma scintillator-for-iodine

-4) Iodine background subtraction'

5) Beta scintillator for lowlrange noble gas

6) Energy-compensated Geiger-Mueller (G-M) detector for high range noble gas

7) Energy-compensated G-M'detector for gamma area subtraction

8) Sample pressure indication at the HVAC PRM

9) Sample flow rate indication at the HVAC PRM This monitor has one control function. Upon detection of activity that exceeds the high alarm setpoint on any channel, a failure of any channel (low Or high) loss of AC power to the monitor, or flow failure the HVAC Accident Range PRM (ORIX-PRO12) automatically transfers from a "STANDBY" condition to in service.- Also, an annunciator alarms in the Main Control Room where proper response actionswill be initiated in accordance with:-CPS procedures.

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CY-CL-170-301 U

Revision 22 Page 56 of 195 3.2.2 SGTS Stack Process Radiation Monitoring (PRM.) System 3 As discussed in section 3.1, the SGTS is used to reduce post-accident concentrations of radioactivity in the primary7 and secondary containment via filter trains.

The SGTS' Stack'PRM monitors the gaseous effluent of the I

filter trains at the SGTS Stack prior'to release to the environment. The PRM detector configuration utilizes nine .(9) channels as follows:

I

1) Beta scintillator for particulates 2). Gamma scintillator for iodine

3) Iodine background subtraction-

4) Beta scintillator for low range noble:gas

5) Energy-compensated G-M detector for intermediate range noble gas

6) Energy-compensated G-M detector for gamma area subtraction

7) Alpha surface barrier:detector to account for the radon/thoron contribution to the beta particulate measurement I

8) Sample pressure indication at the SGTS PRM

9) Sample flow-rate indication at the SGTS PRM This monitor has no control function but annunciates in the Main Control Room where proper response actions 3

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)

U The Pre-Treatment Off-Gas PRM monitors hydrogen I recombiner effluent for gross noble gas radioactivity.

This effluent is then routed to the charcoal adsorbers for eventual release to the environment via the station HVAC Stack (see Figure 3.3-1). The PRM detector I

configuration consists of a single energy-compensated G-M detector mounted in a gas volume.

The monitor has no control function but annunciates in the Main Control Room where proper response actions will be initiated in accordance with CPS procedures.

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CY-CL-170-301 Revision 22 Page 57 of 195 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 stationHVAC Stack for release to the environment (see Figure 3.3-1) The PRM detector configuration is as described for the HVAC Stack PRM (Section 3.2.1) .

The monitor has two control functions. Upon detection of noble gas activity in 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 Tech Spec Release Rate Limitsý'

The Operation and Surveillance Requirements concerning Tech Spec Release Rate Limits are specified in Section 3.4.1. Dose Rate calculations for ensuring compliance with these limits are discussed in Sections 3.4.2 and 3.4.3.

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Revision 22 Page 58 of 195 3.4.1 Tech Spec Release Rate Limits - Operation and Surveillance Requirements OPERATION REQUIREMENT The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.1-1) shall be limited to the following:

I

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less. than or equal .to 3000 mrem/yr to the skin, and

b. For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with I

half lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

This requirement applies at all times.

REMEDIAL REQUIREMENT:

With the dose rate(s) exceeding the abovel limits, immediately restore the release rate to within the above limit(s).

I SURVEILLANCE REQUIREMENTS 3.4.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 3.4.2 by obtaining representative samples and performing.. analyses in accordance with the sampling and analysis program specified in Table 3.4-1.

I 3.4.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater-than 8 days in gaseous effluents shall be I

determined to be within the above limits in accordance with the methodology and parameters in, Section 3.4.3 by obtaining representative samples and performing I

analyses in accordance with the sampling and analysis program specified in-Table 3.4-1. I I

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CY-CL-170-301 Revision 22 Page 59 of 195 TABLE 3.4-1.

RADIOACTIVE GASEOUS WASTE SAMPLING AND-ANALYSIS PROGRAM Lower Limit of Detection Sampling Analysis Type of LLD Gaseous Release Type Frequency Frequency Activity Analysis (gCi/cc)

A. Station HVAC.Exhaust 2

1. Noble Gas and W Principal Gamma <1. 0OE-04 Tritium Release Grab -- upon Emitters' initiation of flow H-3 *I. OOE-06 without delay in a controlled manner 3 4

2. Iodines Release Continuous W 1-131 <1. 0OE-12 I-:133

<I. OOE-10 3

3. Particulates Continuous Principal Gamma *I. OOE-11 Release Emitters' M Gross Alpha *1.OOE-11 Composite Activity Q Sr-89, Sr-90 <I. OOE-11 Composite6 Acftivity B. Standby Gas Treatment System Exhaust, when flow:exists

1. Noble Gas and Each Release Each Principal Gamma <I. OOE-04 Tritium Release Grab -- upon Emitters' initiation of flow <I. OOE-06

.without delay in a controlled manner

2. IodinesRelease Continuous- when 11-131 <1. OOE-12 VG System Flow .1-133

<1. OOE-10 exists3

3. Particulates Continuous -- when .W4 Principal Gamma <I. OOE-11 VG System 3 Flow Release exists Emitters' M Gross Alpha <1. OOE-11 Composite Activity I Q. Sr-89, Sr-90 <I. OOE-11 Composite Activity C. Drywell Purge and High Volume Containment Ventilation, modes 4 and 5 only 5,6 I. Noble Gas.-and Grab -- upon Each .,Principal Gamma *I. OOE-04 Tritium Release initiation of flow Release Emitters' without delay in a H-3 <1. OOE-06 controlled manner D. Mechanical Vacuum Pump 5,6

1. Noble Gas and Grab -- upon Each Principal Gamma <1. OOE-04 Tritium Release initiation of flow Release Emitters' without delay in a H-3 < .OOE-06 controlled manner CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 I

Revision 22 Page 60 of 195 TABLE 3.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS I aThe LLD is definedfor purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be I

detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For aparticular measurement system, which may include radiochemical .separation:

LLD = 4.66 Sb/[E x V x 2.22E+06 x. Y x exp -At)]

Where: .

LLD is the "a priori" lower limit of. detection as defined above, as microcuries per unit miss or volume, Sb is the standard deviat ion of the background counting rate or of the counting rate of a blank sample as appropriate, as

't counts per minute,sb Rbkg where Rbkg = background count rate t = the background count time E is the counting efficiency, as counts per disintegration, V is the sample size in units of ma'ss or volume, 2.22E+06 is the number of disintegrations per minute per, microcurie,":

Y is the fractional radiochemical yield,- when applicable, kis the radioactive decay constant for the particular radionuclide (sec-1) and.

At for plant effluents is the elapsed time between the midpoint of sample collection and the midpoint of the counting interval (sec).

Typical values of E, V, Y, and At should be used in the-calculation.

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CY-CL-170-301 Revision 22 Page 61 of 195 TABLE 3.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS .(Continued)

It should be recognized that the LLD is'defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limitý for a particular measurement.

'The principal gamma emitters are: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and. Xe-138 in noble gas releases and *Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, .Cs-13.7, Ce-141 and Ce-144 in iodine and particulate releases. Other gamma peaks that are identifiable, .together with those of the above nuclides, shall be analyzed and reported in the Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

2Sampling and analysis shall . also be performed without delay in a controlled manner following shutdown, -startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

3The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 3.4.1, 3.5.1 and 3.5.2.

4Samples shall be changed, at least once per 7 days and analysis shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup,, or THERMAL POWER change exceeding 15%, of RATED THERMAL POWER in 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less are analyzed, the corresponding LLDs may be increased by a factor of 10. Twenty-four (24) hour sampling requirements do apply if:

(1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased more than a factor* of 3, and (2) the noble gas monitor on the applicable PRM (HVAC or SGTS) shows that effluent activity has increased more than a factor of 3.

5Samples are taken from the in-service HVAC PRM.

6 Iodines and Particulates released from these discharges are accounted for in the weekly samples taken in accordance with items A2 and A3 above.

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Revision 22 Page 62 of 195 3.4.2 Dose Rate Due to Noble Gases In order to comply with Section 3.4.1.(a), the dose rate at or beyond the site boundary due to noble gases shall be calculated as follows:

Dt = YiK* shf

• Yv[(X/Q)vr*Qiv] ()

= .total body dose rate at time of release, mrem/year Ds '*i 1 shf * (Li + l.Mi)* II[(X/Q)vr

• Qiv] (2)

- skin dose rate at time of release, mr.em/year

ýThe terms in the above equations are defined in section 3.4.3.

3.4.3 Dose Rate Due to Radioiodines, Particulates and Tritium In order to comply with Section 3.4.1(b), organ dose rates due to radioiodines (I-13.1, 1-133), particulates with half-lives > 8 days. and tritium shall be calculated as follows:

Dj I[Pij

• Qivm * (X/Q)v] (3)

'- organ dose rate at time of release, mrem/yr The terms used in as follows:

equations (1) through (3) are defined a

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide. i, mrem/yr per gCi/m 3 from Table 3.4-2 Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide i, mrem/yr per gCi/m 3 from Table 3.4-2 Mi =The air dose factor due to gamma emissions for each identified noble gas radionuclide i, mrad/yr per gCi/m3 (1.1 mrem/mrad converts air dose to skin dose) from Table 3.4-2 shf = Noble gas dose shielding factor, which is set to 1.

CLINTON--UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 63 of 195 Pij = The dose factor for nonfl:noble gas radionuclide 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 gCi/m 3 , pathway are listed in Table 3.4-3 (CHILD). Dose factors are based on NUREG-0133, Section 5.2.1.1 assumptions unless otherwise stated.

Qiv = The release rate of noble gas radionuclide i in gaseous effluent from mixed mode release point v, gCi/sec Qivm = The release rate of non-noble gas radionuclide i in gaseous effluent from mixed mode release point v, gCi/sec (X/Q)vr = The highest value of the annual atmospheric, dispersion factor from release pointv at the site boundary, for all sectors, (sec/m 3 )

(X/Q)v = The highest calculated average relative concentration (X/Q) for any area at or beyond the site boundary from mixed mode release point v. sec/m3.

Dj is calculated for each of six Organs and the total body; the maximum Dj value is then used to determine compliance with Section 3.4.1(b).

The factors Ki, Li, and Mi relate the radionuclide airborne concentrations to var~ious dose rates assuming a semi-infinite cloud. These factors are listed in Table 3.4-2 and were obtained from Table B-1 of Regulatory Guide 1.109 after multiplying the values by the conversion 106 pCi/gCi.'

10CFR20 organ dose rate calculations are limited to the inhalation pathway only. Section 3.4.1(a) is applicable to the unrestricted area location characterized by the (X/Q)v value which results in the maximum total body or skin dose commitment. Should the total body and skin locations differ, the selected location shall be that which minimizes allowable release rates.

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Revision 22 Page 64 of 195 I

There are unrestricted areas within the CPS site I

boundary which are utilized by members of the public for residences, farming, recreation and camping.

areas are identified in Table 3.4-4.

These Table 3.4-4 will I

be revised to remain consistent with the most recent land use Icensus. I' II H

I I

£ II I

CLINTON -- UNIT #1 Rev.22 -

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wfýNi w -l ow MW SW 4M 00 10 "M 'a -

CY-CL-170-301 Revision 22 Page 65 of 195 TABLE 3.4-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Radionuclide Ki (mrem/yr per ýiCi/m 3 ) (mrem/yr per RCi/m 3 ) (mrad/yr per gCi/m 3 ) (mrad/yr per gCi/m 3)

Kr-85m 1. 17E+03 1 .46E+03 1.23E+03 1.97E+03 Kr-85 1. 61E+01 1. 34E+03 1.72E+01 1.95E+03 Kr-87 5 . 92E+03 9 .73E+03 6.17E+03 1ý.03E+04 Kr-88 1. 47E+04 2. 37E+03 1.52E+04 2.93E+03 Kr-89 1. 66E+04 1. 01E+04 1. 73E+04 1. 06E+04 Kr-90 1. 56E+04 7. 29E+03 1. 63E+04 7. 83E+03 Xe-131m 9. 15E+01 4. 76E+02 1 .56E+02 1. 11E+03 Xe-133m 2. 51E+02 9. 94E+02 3 .27E+02 1. 48E+03 Xe-133 2. 94E+02 3.06E+02 3. 53E+02 1. 05E+03 Xe-135m 3. 12E+03 7 .11E+02 3. 36E+03 7. 39E+02 Xe-135 1. 81E+03 1. 86E+03 1.92E+03 2 .46E+03 Xe-137 1. 42E+03 1 .22E+04 1 .51E+03 1 27E+04 Xe-138 8 . 83E+03 4. 13E+03 9. 21E+03 4.75E+03 Ar-41 8.84E+03 2. 69E+03 9. 30E+03 3.28E+03

• The listed dose factors are for radionuclides that may be detected in gaseous efflulents.

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I!

CY-CL-170-301 Revision 22 Page 66 of 195 I

I TABLE 3.4-3 INHALATION PATHWAY DOSE RATE FACTORS (mrem/yr per pCi/m 3 )

(CHILD) -Pij II N'

ORGAN ISOTOPE H-3 P-32 BONE NO DATA

2. 60E+06 LIVER

1. 12E+03

1. 14E+05 S. T. BODY 1.12E+03 9.88E+04 THYROID 1.12E+03 NO DATA KIDNEY 1.12E+03 NO DATA LUNG 1.12E+03 NO DATA GI-LLI 1.12E+03 4.22E+04 Ii CR-51 MN- 54 FE-55 NO DATA NO DATA 4.74E+04 NO DATA 4.29E+04

2. 52E+04 1.54E+02 9.51E+03 7.77E+03 8.55E+01 NO DATA NO DATA 2.43+01 1.00E+04 NO DATA 1.70E+04 1.58E+06

1. 11E+05 1.08E+03 2.29E+04

'2.871+03 I

FE-59 2.07E+04 3 .34E+04 '1.67E+04' NO DATA NO DATA 1.27E+06 ý7.ý07E+04 CO-58 CO-60 NI-63 ZN-65 NO DATA NO DATA 8.21E+05

4. 26E+04

1. 77E+03 1.31E+04

4. 63E+04 1.13E+05

3. 16E+03 2.26E+04 2.80E+04 7.03E+04 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 7.14E+04 1.11E+06 7.07E+06 2.751E+05 9.95E+05 3 .44E+04 9 62E+04 6.33E+03 1.63E+04

-U RB-86 SR-89 SR-90 NO DATA

5. 99E+05 1.01E+08

1. 98E+05 NO DATA NO DATA 1.14E+05

1. 72E+04 6.49E+06 NO DATA NO DATA NO DATA NO, DATA NO DATA NO DATA NO DATA 2.16E+06 1.48E+07 7 . 99E+03 1.67E+05 3'. 43E+05 I

Y-90 4. 11E+03 NO DATA 1. 11E+02 NO DATA NO DATA 2.62E+05 2.68E+05 Y-91 ZR-95 NB-95

9. 14E+05

1. 90E+05 2.35E+04 NO DATA

4. 18E+04

9. 18E+03 2 .44E+04 3 .70E+04 6 .55E+03 NO DATA NO DATA NO DATA NO DATA

5. 96E+04 8.62E+03 2.63+06 2 .23E+06 6.14E+05 1.84E+05 6.11E+04 3.70E+04 Al 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 NO DATA 7.03E+03 6.62E+05 4.48E+04 11 RU-103 2. 79E+03 NO DATA 1 . 07E+03 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+04 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 1.48E+06 7.14E+04 TE-129m 1. 92E+04 6.85E+03 3 .04E+03 6.33E+03- 5. 03E+04 1. 76E+06 1.82E+05 1-130 8. 18E+03 1. 64E+04 8.44E+03 1.85E+06 2 .45E+04 NO DATA 5.11E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7 .88E+04 NO DATA' 2.84E+03 1-132 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 1-135 CS-134

1. 17E+03

4. 92E+03 6.51E+05

2. 16E+03 8.73E+03 1.01E+06 9'. 95E+02 4.14E+03 2.25E+05 5.07E+04 7.92E+05 NO DATA 3 .30E+03

1. 34E+04 3 .30E+05 NO DATA NO DATA 1.21E+05

9. 55E+02 4.44E+03 "3.84E+0-3 II CS-136 6.51E+04 1. 71E+05 1.16E+05 NO DATA 9. 55E+04 1.45E+04 4.18E+03 CS-137 BA- 140 CE-141

9. 07E+05 7.40E+04 3 .92E+04 8 .25E+05 6 .48E+01

1. 95E+04 1.28E+05 4.33E+03 2.90E+03 NO DATA NO DATA NO DATA 2 .82E+05 2.11E+01 8.55E+03

1. 04E+05 1.74E+06 5.44E+05 3.62E+03 1.02E+05 5.66E+04 U

2 .12E+06 3.62E+05 NO DATA 1.17E+06 1.20E+07 3.89E+05 Ii CE- 144 6 .77E+06 PR-143 1.85E+04 5. 55E+03 9.14E+02 NO DATA 3.00E+03 4.33E+05 9.73E+04 ND-147 1. 08E+04 8 73E+03 6.81E+02 'NO DATA 4. 81E+03 3.28E+05 8.21E+04 I

II

-u CLINTON -- UNIT #1 Rev.22 - 12/09 a

I CY-CL-170-301 Revision 22 I Page 67 of 195 I TABLE 3.4-4 LOCATION OF MEMBERS OF THE PUBLIC WITHIN THE CPS SITE BOUNDARY AND THEIR ASSOCIATED OCCUPANCY FACTORS*-

I Distance .Occupancy Ii Location (mile/meter) Sector (hrs/yr)

Road 1243 (1) 0.3/495 SE I'

.,Agricultural SAcreage (2) 0.9/1372 SSW 966-(3)-

I Clinton Lake 0.2/335 NW 2208 (4.)

di Department of Conservation Recreation Area 0.8/1287 ESE 2208 (5)

.Residence 0.8/1219 .iSW 8760 3 Residence Residence 1.5/2414 1.7/2736 WSW, SSE

.8760 8760

.5 (1) Assumes travel on road for forty minutes per day.

I' (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.

I (4). Assumes.continuous occupation on Clinton Lake for the months of June,. July, and August.

~II (5) Assumes continuous occupation on Department of Conservation camping areas for the months of June,.July, and August.

• Doses for such MEMBERS OF THE PUBLIC are provided in the Radioactive Effluent Release Report as given in Section 6.3.2.

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Revision 22 Page 68 of 195 3.5 10CFR50, APPENDIX I RELEASE RATE LIMITS The Operation and Surveillance Requirements concerning 10CFR50 (Appendix I) Release Rate Limits are.. specified in Sections 3.5.1 and 3.5.2. Dose calculations for 7' ensuring compliance with these limits are discussed in Sections 3.5.3 and 3.5.4. N) 3.5.1 Noble Gas Dose Operation and Surveillance Requirements N OPERATION REQUIREMENT The air:dose due to noble gases released in gaseous I effluents, from each reactor unit, to.areas at and beyond the SITE BOUNDARY (see Figure 3.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and 1

b. During any calendar year: Less than or equal to 10 mrad for gamma.,radiation and less than or equal to 20 mrad for beta radiation.

This requirement :applies at all times. I REMEDIAL REQUIREMENT: I

a. With the calculated air dose from radioactive nobles gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the-Regional I

,Administrator of the Regional Office of the NRC within 30 days a Special Report that identifies the, cause(s) for exceeding the limit(s) and defines the corrective actions that. have been taken to reduce the releases and the proposed corrective actions to be taken to assure that [

subsequent releases will be in compliance with the above limits. .

• i CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 69 of 195 SURVEILLANCE REQUIREMENTS 3.5.1._1 '"Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and

• :,parameters described in Section 3!.5.3 at least once per 31 days.

3.5.2 Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form - Operation and Surveillance Requirements OPERATION REQUIREMENT

....The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in

.:particulate form with half-lives greater than 8 days in gaseous effluents released to areasat and beyond the SITE BOUNDARY (see Figure 3.1-1) shall be limited to the-following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: Less than or equal to 15 mrem to any organ.

This requirement applies-at all times.

REMEDIAL REQUIREMENT:

a. With the calculated dose from the release of

. iodine-131, iodine-133, tritium,; and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits prepare and submit to~the Regional

• Administrator of the Regional Office of the NRC within 30 days 'a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assureithat subsequent releases will be in compliance with, the above limits.

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CY-CL-170-301 Revision 22 Page 70 of 195 SURVEILLANCE REQUIREMENTS 3.5.2,1 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be I

determined in accordance with the methodology and parameters described in Section 3.5.4 at least once pera 31 days."

3.5.3 Noble Gas Air Dose Equations. II The air dose.at or beyond thesite boundary due to noble gases released in gaseous effluent will be determined using the following equations;.

3.5.3.1 During any calendar quarter or calendar yea r., for gamma radiation:

Dy = 3.17E-08

• 1i[ Mi* (X/Q)v

• Qiv] (4) 3.5.3.2 During any calendar quarter or calendar year, for beta

ýradiation:

Do = 3.17E-08

• Xi[Ni . (X/Q)v

• Qiv] (5) where .

M+/-= The gamma air dose factor for each identified noble gas radionuclide i, -i

mrad/year per gCi/m 3 (Mi -values are listed in Table 3.4-2).

Ni = The beta air dose factor for each identified noble gas radionuclide i, mrad/year per JtCi/m 3 (Ni values are listed in Table 3.4-2).

(X/Q)v = The highest calculated average relative concentration from mixed-mode release 5

points .for areas at or beyond the site boundary, sec/M3 . U Q=v The total release of noble gas radionuclide i for long-term releases i from mixed-mode release points, ICi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

3.17E-08 The inverse of the number of seconds in a year.

j CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 71 of 195 Section 3.5.1 noble gas dose calculations are evaluated at the site boundary location where-maximum air doses prevail. Should the beta and gamma locations differ,

'the selected location shall be that which minimizes

-.allowable release rates due to the' gamma component.

3.5.4 Radioiodines, Particulates and Tritium Dose Equations The dose to an individual at or beyond the site boundary due to radioiodines (1-131, I-133), tritium and particulates with half-lives > 8 days, will be

.:determined using the follow equation:

for any calendar quarter or calendar year,

3.17E-08,* fo

• 1i[RPija Wpv* Qi] (6) where Qiv = The releases of radionuclide i (1-131, 1-133, tritium and particulates with half-lives greater than 8&days): for releases from vent v for mixed-mode releases, gCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

Wv P = The annual average dispersion parameter for estimating the dose to an individual as appropriate to pathway p and release point v, at a controlling location, for mixed-mode releases.

(X/Q), sec/m3 , for the inhalation pathway and tritium at the location of the critical receptor.

-2

(=

D/Q)m, m-, for the food and ground plane pathways at the location of the critical receptor..

3.17E-08 = The inverse of the number of seconds in a year.

R~ija = The dose factor for each identified radionuclide i, pathway (P), organ (j), and age group (a),, m2 -mrem/year per pCi/sec or 3

mrem/year per VCi/m .

f0 = Occupancy factor which is set to 1 CLINTON--UNIT #1 Rev.22 -

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CY-CL-170-301 I

Revision 22 Page 72 of 195 Sectioh 3.5.2 is applicable to the location at or beyond.the site boundary where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways exist at all locations; other i

pathways exist as determined by the most current land use census. I 3.5.4.1 Dose Factor For Radionuclide i (RPjaý)

The Rpija values used to calculate Dj in equation (6) are determined separately for each of the potential exposure pathways, namely: 9

- Inhalation (I)

- Ground Plane Contamination (G)

- Grass-Cow/Goat-Milk

- Grass-Cow-Meat '(r)

(C)"' Ii

- Vegetation (V)

The R ija parameter: is' independent of the duration of gaseous releases and is calculated using the methodology discussed in the remainder of this section. 'U 3.5.4.1.1 Calculation of the"Inhalation Pathway Factor, RIija Rija = K' (BR) a(DFAi)ja, mrem/year per [LCi/m' (7) where I K' = A units conversion constant, 106 pCi/gCi (BR)a = The breathing rate of the receptor age group (a), m3 /year II

=

=

1400 3700 (infant)

(child)

I'

= 8000 (teen and adult) .

Values for (BR)a are obtained from NUREG-0133, pg. 32 (DFAij)a= The organ inhalation dose factor for receptor of age group (a) for radionuclide i, and organ j, mrem/pCi. Values for (DFAi)a were I

• obtained from Tables E-7 through E-10 of Regulatory Guide 1.109 and are presented in I Tables 3.5-1 through 3.5-4 of this manual.

[

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CY-CL-170-301 Revision 22 Page 73 of 195 G

3.5.4.1.2 Calculation of the Ground Plane Pathway Factor, R ija RGij a = K'K" (SF) (DFGij) [(1- (exp (--kit)) )/i], (8) 2 m -mrem/year per ýtCi/sec where K' = A units conversion constant, 106 pCi/JLCi K" = A units conversion constant, 8760 hour/year SF. = The shielding. factor, dimensionless

= 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 DFGij = The ground plane dose,conversion factor for radionuclide i and organj, mrem/hour per pCi/m 2 . Values for DFGi were obtained from Table E-6 of Regulatory Guide 1.109 and are presented in Table .3.5-5 of this manual.

= The decay constant for radionuclide i, sec-1 t = The exposure time, sec

= 6.31E+08 sec (20 years)

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Revision 22 Page 74 of 195 3.5.4.1.3 Calculation of the Grass-Cow/Goat-Milk Pathway Factor, RCija = ' [QF (Uap)/ (Xi + Xw)] Fm(r) (DFLi)ja (9)

• [fpfs/Yp + (l-fPfs)exp(-kith)/Ys] exp(-Xith) ,

m -mrem/yr per gCi/sec where I K' = Aunits conversion constant, 106 pCi/.Ci QF = The.cow/goat feed consumption rate, kg(wet)/day Uap = The receptor's milk consumption rate for age group (a), liters/year Yp The agricultural productivity by unit area of 2

pasture* feed grass, kg/m Ys = The agricultural productivity by unit area of stored feed, kg/mr Fmi The stable element transfer coefficient for nuclide i in milk, days/liter. These values are from Tables E-1 and E-2 of Regulatory Guide 1.109.

r = Fraction of deposited activity retained on feed grass, dimensionless (DFLi)ja *. . .

• The organ ingestion dose factor for radionuclide i, organ j, and the receptor in age group (a), mrem/pCi. Values for (DFLi)ja were obtained from Tables E-1l through E-14 of Regulatory Guide 1.109 and are presented in Table 3.5-6 through 3.5-9 of this manual.

= The decay constant for radionuclide i, sec-1 Xw = The decay constant for removal of activity on leaf and plant surfaces by weathering, sec

-1

= 5.73E-07 sec (corresponding to a 14-day half-life)

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CY-CL-170-301 Revision 22 Page 75 of 195 tf The transport time from pasture~to animal, to milk, to receptor, sec th The transport time from pasture to harvest, to animal, sec fp = Fraction of the year that the cow/goat is on pasture, dimensionless.

fsFraction of the cow/goat feed that is pasture grass while the cow/goat is on pasture, dimensionless The input parameters for calculating RCija are listed in Table 3.5-10.

Tritium The concentration of tritium in. milk is based on its airborne concentration rather than the deposition.

C' R T = K'K"FmQFUap(DFLi)ja

• 0.75(0.5/H),

mrem/yr per RCi/m 3 (10) where K" = A units conversion constant, 103 gm/kg H = The absolute atmospheric humidity

= 8 gm/mn3 (NUREG-0133, p. .34) 0.75 = The fraction-of total feed that is water, dimensionless 0.5 The ratio of the specific activity of the feed grass water to the atmospheric water, dimensionless The other parameters are as defined in the calculation of RCija CLINTON -UNIT #1 Rev.22 -

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Revision 22 Page 76 of 195 3.5.4,14 Calculation of the Grass-Cow-Meat Pathway Factor, RMija RMija [K'QF (Uap) / (ki + kw) ]Ff (r) (DFLi) ja *

[fpfs/-Yp +

(exp (-rritrs))

m-_mrem/yr

.2

[(l-fpfs)/Ys] (exp(-kith))]*

per gCiisec I

(11) where II K! =

=

A units conversion constant, The receptor's meat consumption rate for age 106 pCi/gCi II Uap group (a), kg/year II a

Ff = The stable element transfer coefficient, days/kg ts = The transport time from pasture to animal to slaughter-of meat animal to receptor, seconds th = The transporttime from crop field to harvest 1

to animal, seconds* .

(DFLi) ja = The organ ingestion dose factor radionuclide i, -organ j, and the receptor in for 5 age group (a), mrem/pCi. Values for (DFLi)ja were obtained from Tables E-11 through E-14 of Regulatory Guide 1.10-9 and are presented ii in Table 3.5-6 through 3.5-9 of this manual.

The input parameters necessary for calculating RMija are II listed in, Table 3.5-11. All other terms are as defined for equations (9) and (10).

I' Tritium The concentration of tritium in meat is based on its airborne concentration rather than the deposition.

I RMT K'K"FfQFUap(DFLi)ja mrem/yr per gCi/m 3

[0.75(0.5/H)],

(12)

I The terms in equation (10) and (11).

(12) are as defined in equations II I

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CY-CL-170-301 Revision 22 Page 77 of 195 3.5.4.1.5 Calculation of the Vegetation Pathway Factor, RVipj RV ip K' [(r) / [Y, (Xi + ))) (DFLi) ja *

[ULafL(exp(-kitL)) + USaf fg(eXP(-kith))],

2 m -mrem/yr per gCi/sec (13) where K' = A units conversion constant, 106 pCi/pCi ULa = The consumption rate of fresh leafy vegetation by the receptor in age group (a),

kg/year U.a /= The consumption rate of stored vegetation by the receptor in age. group (a), kg/yr fL = The fraction.of. the. annual intake of fresh leafy vegetation grown locally, dimensionless f 'The fraction-of !theannual intake of stored vegetation grown locally,, dimensionless tL = The average-time-between harvest of leafy vegetation and its consumption, seconds th = The average time between harvest of stored vegetation and its consumption, seconds Yv = the vegetation area density, kg/M2 (DFLi)ja= The organ ingestion dose factor for organ j, radionuclide i, and the receptor in age group (a), mrem per pCi. Values are tabulated in Table 3.5-6 through 3.5-9 of this manual.

The input parameters necessary for calculating RVija are listed in Table 3.5-12. All other terms are as defined for equations (9) and (14).

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43 CY-CL-170-301 Revision 22 Page 78 of 195 Tritium The concentration of tritium in vegetation is based on its airborne concentration rather than the deposition.

RvT K' K" (UT'afL + USafg) (DFLi)ja [0.75(0-.5/H)]

mrem/yr per ý.Ci/ml -I (14)

The terms in equation (14) are as defined inequations (10) and (13)

II The pathway dose rate factors (R'ija, RCija, RVija, RMija, R Gi, 3.5-31.

by age group are listed in'Table 3.5-13 through a

I I

II a

II a

II II

'1 ii CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 79 of 195 3.6 Gaseous Radwaste (Offgas Treatment) 3.6.1 GaseousRadwaste (Offgas Treatment) System - Operation and.,Surveillance Requirements OPERATION REQUIREMENT The GASEOUS RADWASTE (OFFGAS) TREATMENT SYSTEM shall be in operation. This requirement applies whenever the main condenser steam jet air ejector' system is in operation.

REMEDIAL REQUIREMENT:

a. With gaseous radwaste from'the-main condenser air ejector system being discharged without treatment for more than 7 days, prepare and submit to the Regional Administrator of the Regional Office of the NRC within 30 days a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability.

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENT 3.6.1.1 The GASEOUS RADWASTE (OFFGAS) TREATMENT SYSTEM shall be verified to be in operation once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the main condenser air ejector is in use to ensure that the main condenser offgas treatment system is functioning.

NOTE When placing the Offgas Treatment System in the charcoal bypass mode, the alarm setpoints for the Station HVAC Exhaust and the Post-Treatment Offgas radiation monitors may 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 delay) in the primary coolant offgas.

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CY-CL-170-301 Revision 22 Page 80 of 195 3.7 Ventilation Exhaust Treatment 3.7.1 Ventilation Exhaust Treatment System - Operation and Surveillance Requirements .

OPERATION-REQUIREMENT The VENTILATION EXHAUST TREATMENT SYSTEM (VETS) shall be used to;reduce radioactive materials in gaseous waste prior to.their discharge when the projected doses due to gaseous. effluent releases to areas at'and beyond the SITE BOUNDARY (see Figure 3.1-1) would exceed 0.3 mrem to any organ in a 31-day period. This requirement applies at all times other than when the VETS is undergoing routine maintenance..

REMEDIAL REQUIREMENT::.

a. With gaseous waste being discharged without treatment and in excess of the above limit, prepare and submit to the Regional Administrator of the Regional Office of the NRC.within 30 days a Special Report that includes the following information:

.1. Explanation of why gaseous radwaste was being discharged without treatment, identification of .any inoperable equipment or subsystems, and, :the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

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CY-CL-170-301 Revision 22 Page 81 of 195 SURVEILLANCE REQUIREMENTS 3.7.1.1 .- Doses due to gaseous releases from the-site shall be projected at least once. per 31 days in accordance with this manualwhen the ventilation exhaust treatment system is not in use. The projected..doses resulting from such releases will be calculated using Section

'3.7.2 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.

3.7.12ý.,2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall-be considered OPERABLE by'meeting the Operation Requirements of Sections. 3.4,.'3.5.l, and 3.5.2.

3.7.2 Gaseous Effluent Dose Project~ion.Calculations The 31 day projected-dose shall be calculated using the following equation.

Dpj (Dj

• p), + Daj (15) where:

Dpj = the 31 day projected dose by organ j.

Dj = sum of dose for all valid release points for the release period (usually-quarter) by organ j.

p= the projection factor which is the results of 31 divided by the number of days from the start of the quarter to the end of the release.

Daj,3= additional anticipated dose for gaseous release by organ j and quarter of. release.

3.8 -Effluent Monitor SetpOint Calculations Gaseous effluent Process Radiation Monitor (PRM) alarm setpoints shall be calculated to ensure that the instantaneous dose rate in unrestricted areas due to noble gases released do not exceed 500 mrem/year to the total body and 3000 mrem/year to the skin. The initial setpoints were calculated using the BWR/GALE code radionuclide mix obtained for CPS; when the actual radionuclide mix can be determined, it will be used for setpoint calculations. The PRM setpoints are based on the instantaneous noble gas dose rates and are applied at the point of which the effluent enters an unrestricted area.

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Revision 22 Page 82 of 195 It Due to PRM limitations, non-noble gas setpoints will not be implemented to demonstrate compliance with Section 3.4.1(b). Compliance with the organ dose rate limitation II is demonstrated during performance of sampling and analysis activities required by Table 3.4-1.- 1 Both total body and skin dose setpoints will be calculated and the more restrictive limit applied to the respective PRM. The actual setpoint used may be lower than the restrictive limit since the two release I

points will be partitioned such that their sum does not exceed 1Q0 percent of the restrictive limit., The percentages used to partition the release points could I

vary at plant discretion to accommodate plant operational conditions. In no case will the combined releases due to variations in the PRM setpoints result I

in effluent limiits being exceeded.

Ii 1

5 a

I I

I Ii

/3 II I

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, 3.8.1 Total Body Dose Rate Setpoint The fraction of the total gaseous radioactivity in each gaIseous g effluent release path j for each noble gas radionuclide i shall be determined using the following relationship:

i = Cij/ (IiC+/-j) , dimensionless (16) 3 where Cij = The measured concentration of identified noble gas radionuclide i in gaseous effluent release

.. path j, gCi/cc The maximum acceptable release-rate of all noble gases in release path j to comply with' Section 3.4.1 is calculated by using the equation:

whre QTj = 500 Fj/ [ (X/Q) j~i (Kifij)] , gCi/sec (17) where QTj = The maximum acceptable release rate of all noble gases in release path j, gCi/sec Fj = Total dose rate allocation factor assigned to release path j (varying between 0.0 and 1.0),

dimensionless 500 = Total body dose rate limit specified in Section 3.4.1(a), mrem/year 3nconcentration (X/Q)j = The highest calculated average relative boundary of release path j at the site Ki The total body dose factor due to gamma emissions of noble gas radionuclide i as listed in Table B-1 of Regulatory Guide 1.109 and Table 3.4-2 of this manual, mrem/yr per I 3Ci/m3

=fij The fraction as defined by equation (16),

dimensionless

[I il CLINTON -- UNIT #1 Rev.22 -

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I CY-CL-170-301 Revision 22 Page 84 of 195 I

The total maximum acceptable concentration setpoint of noble gas radionuclides in release path.j isr calculated 1

using the following equation:

CTj = QTj /Rj, gýi/cc (18) where CTj = The total maximum acceptable concentration setpoint of all noble gases in release path j, RCi/cc QTj = The maximum acceptable release rate of all no ble gases in release path j determined from equation (19), RCi/sec

= The effluent release rate of release point j, I

cc/'sec .

II I

5 I

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CY-CL-170-301 Revision 22 Page 85 of 195 1 3.8.2 Skin Dose Rate Setpoint To ensure compliance with the section 3.4.1(a) skin dose rate limit, PRM :setpoints shall 'be calculated using the methodology presented in Section 3.8.1 and by substituting the following equation for equation (16):

Qsj (3000*Fj) (X/Q) ji (Li+l. iMi) *fij] gCi/sec (19) where

.Qs = The maximum acceptable'release rate of all noble gases in release path j, gCi/sec

• F= Total dose rate allocation factor assigned to

• 7 release path j (varying between 0.0 and 1.0),

dimensionless 3000 = Skin dose rate limit specified in Section 4 3.4.1(a), mrem/year 11 (X/Q)j = The highest calculated average relative concentration of release path j at the site i13 boundary Li = The skin dose factor due to gamma emissions for each identified noble gas radionuclide i, p mrem/yr per ýtCi/m 3, as listed in Table 3.4-2 of this manual.

1 1.1 =An air dose to skin dose equivalent conversion factor, mrem/mrad Mi = The air dose factor due to gamma emissions

• for each identified noble gas radionuclide i, mrad/yr per ICi/m , as listed in Table 3.4-2 of this manual fij = The fraction defined by equation (16)

The calculated total body and skin maximum acceptable concentration setpoints are compared and the more restrictive setpoint used. A safety factor may also be applied to the concentration setpoint calculated by i*equation (17) to compensate for statistical fluctuations and measurement errors.

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CY-CL-170-301 Revision 22 Page 86 of 195 3.9 Radioactive Gaseous Monitoring Instrumentation ,

3.9.1 Offgas Radiation Monitoring Instrumentation-- Operation and Surveillance Requirements OPERATION REQUIREMENT The offgas radiation monitoring instrumentation channels shown in Table 3.9.1-1 shall be OPERABLE, with

'5 their alarm/trip setpoints within the specified limits.

This requirement applies during operation of the main condenser air ejector(s).

REMEDIAL REQUIREMENT:

a. With a radiation monitoring instrumentation.

channel alarm/trip setpoint exceeding :the value shown in-Table 3.9.1-1, immediately suspend theI release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable. ,

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation.*

channels OPERABLE, comply with the REMEDIAL.

REQUIREMENT specified in Table 3.9.1-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 3.9.1.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION at the frequencies shown in Table 3.9.1-2.

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CY-CL-170-301 Revision 22 Page 87 of 195 TABLE 3.9:1-1 OFFGAS RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS ALARM/TRIP INSTRUMENTATION OPERABLE (e) REMEDIAL.

d SETPOINT REQUIREMENT

1. Pre-treatment Off-gas PRM - Noble Gas < 50 ILCit/cca~b 5 Activity Monitor 1RIX-PR034

2. Post-treatment Off-gas PRM IRIX-PR035/41

a. High-Range Noble Gas Activity < 7.06 RCi/ccc Monitor Providing 6

Alarm and Automatic Termination of Release (Ch 7)

b. Effluent System Flow Rate NA' Measuring Device 7

1N66R602A, 1N6GRG02B or computer point OG--.

DA06. 6

c. Sample Flow Rate Measuring Device 1 NA (Ch 15)

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Revision 22 Page 88 of 195 TABLE 3.9.1-1 (Continued) 3 OFFGAS RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS I a Alarm only.

b Radioactivity concentration expected at the monitor location is a noble gas mix with a 2.9-minute decay.

I.

c Radioactivity concentration expected at the monitor location is a noble gas mix released from the off-gas treatment system.

'I d Channel OPERABILITY shall include the capability of the MCR ARPR LAN to provide the alarm status of the applicable radiation monitor channel(s) .

e When a channel is placed inman inoperable status solely for performance of required Surveillances (source checks, sampling) entry into associated Remedial Requirements may be delayed for up to one hour.,-

REMEDIAL REQUIREMENT 5 REMEDIAL REQUIREMENT a. If the communication link with the MCR ARPR LAN is inoperable, 5

1. Perform a CHANNEL CHECK using local monitor indication within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and 2: Locally check for TREND alarm within 2

- hours and at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thereafter. (Note: This requirement is to provide sample indication to initiate Tech Spec Surveillance Requirement 3.7.5.1.)

3.. Restore communication for the applicable channel(s) within the next 30 days,. and if unsuccessful, prepare and submit-to the Regional Administrator of the Regional Office of the NRC within the next 10 days a Special Report outlining the cause of the communication u failure or malfunction and the action '

taken to restore the inoperable equipment to OPERABLE status.

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CY-CL-170-301 Revision 22 Page 89 of 195 TABLE 3.9.1-1 (Continued)

OFFGAS RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS

b. With the Pre-treatment Off-gas PRM - Noble Gas Activity Monitor otherwise inoperable, gases from the main condenser off-gas treatment system may be released to the environmentprovided:

1. The off-gas treatment system is not bypassed, except for filtration system by-pass during plant start-ups and NOTE: The following step ensures compliance with Technical Specification Surveillance Requirement 3.7.5.1 2., Perform grab'samples every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the monitor !is:returned to OPERABLE status.

REMEDIAL REQUIREMENT a. With the MCR ARPR LAN inoperable, 6

1. Perform a CHANNEL CHECK using local monitor indication within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and

2. Restore the MCR ARPR LAN to OPERABLE status for the applicable channel(s) within the next 30 days, and if unsuccessful, prepare and submit to the Regional Administrator of the Regional Office of the NRC within the next 10 days a Special Report outlining the cause of the MCR ARPR LAN failure or malfunction and the action taken to restore the inoperable equipment to OPERABLE, status.

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Revision 22 Page 90 of 195 TABLE 3.9.1-1 (Continued)

OFFGAS RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS I

b. With the Post-treatment Off-gas PRM High Range Noble Gas Activity Monitor otherwise inoperable, I'

effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and a noble gas:gamma isotopic analysis performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

REMEDIAL REQUIREMENT 7 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway.

may continue provided the flow rate is estimated at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. a

,I 5i II CLINTON -- UNIT #1 Rev.22 -

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mMm -n0 . up- A= M --

CY-CL-170-301 Revision 22 Page 91 of 195 TABLE 3.9.1-2 OFFGAS RADIATION MONITORING INSTRUMENTATION SURVEILLANCE -REQUIREMENTS CHANNEL CHANNEL SOURCE FUNCTIONAL CHANNEL INSTRUMENTATION CHECK CHECK TEST CALIBRATION

1. Pre-Treatment Off-gas S(3) M Q(1) R(2)

PRM-Noble Gas Activity Monitor

2. Post-Treatment Off-gas PRM

a. High Range Noble S(3) W Q (1) R24 (2) a Gas Activity Monitor Providing Alarm and Automatic Termination of Release

b. Effluent System D NA Q. R Flow-Rate Measuring Device

c. Sample Flow-Rate S NA Q R24 Measuring Device CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 U

Revision 22 Page 92 of 195 TABLE 3.9.1-2 (Continued) I OFFGAS RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION a Automatic isolation of valve 1N66-F060 shall be demonstrated during the CHANNEL.CALIBRATION.

(1). The CHANNEL FUNCTIONAL TEST shall also demonstrate that the MCR ARPR LAN responds with annunciation and event display to each of the following conditions:.

1. Instrument indicates measured levels above the alarm/trip (HIGH) setpoint.

2. Detector failure (LOW FAIL, ,HI FAIL) . .'

3. Sample flow failure.. (EXTERNAL FAIL).

4. Instrument not set in.normal operate mode (CALIBRATE, MAINTENANCE, or STANDBY).

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the referencestandards certified by the National Institute of Standards and Technology (NIST). or using standards that have been obtained from suppliers that participate in measurement assurance'activities with NIST.

These standards shall permit calibrating the system over its intended energy~range and measurement range. Subsequent CHANNEL CALIBRATION shall be performed using the initial radioactive standards or other standards of equivalent quality or. radioactive sources that have been related to the initial calibration.

(3) The CHANNEL CHECK performed from the MCR ARPR'LAN also verifies communication..

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CY-CL-170-301 Revision 22 Page 93 of 195 3.9.2 Radioactive Gaseous Effluent Monitoring Instrumentation

- Operation and Surveillance Requirements OPERATION REQUIREMENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.9.2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section'3.4.1 and Technical Specification 3.7.5 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with theýmethodology and parameters in this manual. This requirement applies as shown in Table 3.9.2-1.

REMEDIAL REQUIREMENT:

a. With a radioactive gaseous-effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, fordedlare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, comply with the REMEDIAL REQUIREMENT specified in Table 3.9.2-1. Restore

• the inoperable instrumentation:to OPERABLE status

• within 30 days and, i~f unsuccessful, explain in the next Radioactive Effluent'Release Report pursuant to Technical Specification 5.6.3 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS' 3.9.2.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3.9.2-2.

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CY-CL-170-301 Revision 22 Page 94 of 195 TABLE 3.9.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM REMEDIAL INSTRUMENT CHANNELS OPERABLE (g) APPLICABILITY REQUIREMENT

1. Station HVAC Exhaust PRM ORIX-PRO01/2

a. High-Range Noble Gas Activity a 1c Monitor (Ch 7)

b. Low-Range Noble Gas Activity c a Monitor (Ch 5) 1

c. Iodine Sampler(d) a

d. Particulate Sampler(d) a

e. Sample Flow-Rate Measuring Device 1 a (Ch 15)

2. Standby Gas Treatment System Exhaust PRM ORIX-PRO03/4

a. High-Range Noble Gas Activity c 1 b Monitor (Ch 9) c

b. Low-Range Noble Gas Activity 1 b Monitor (Ch 6)

c. Iodine Samplerd 1 b d

1 b

d. Particulate Samplerd

e. Sample Flow-Rate Measuring Device 1 b (Ch 15)

3. Station HVAC Exhaust AXM ORIX-PRO12

a. High-Range Noble Gas Activity 1 e Monitor (Ch 3)

b. Intermediate-Range Noble Gas 1 e Activity Monitor (Ch 4)

c. Sample Flow-Rate Measuring Device 1 e OFI-PRO12B CLINTON -- UNIT #1 Rev.22 - 12/09 Wa a Auin S as a an'a 0n m e a" a a a a

m ll ---m -0110 mW , Im am M, M W CY-CL-170-301 Revision 22 Page 95 of 195 TABLE 3.9.2-1 (cont'd)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM REMEDIAL INSTRUMENT CHANNELS OPERABLE (g) APPLICABILITY REQUIREMENT

4. Standby Gas Treatment System Exhaust AXM ORIX-PRO08

a. High-Range Noble Gas Activity 1 e 11 Monitor (Ch 3)

b. Intermediate-Range Noble Gas 1 e 11 Activity Monitor (Ch 4)

c. Sample Flow-Rate Measuring Device 1 e OFI-PRO08B

5. Station HVAC Effluent System 1 a 10 Flow-Rate Measuring Device OUIX-PRO51 Ch 6

6. SGTS Effluent System Flow-Rate 1 f 10 Measuring Device OUIX-PRO51 Ch 1 CLINTON -- UNIT #1 Rev.22 - 12/09

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Revision 22 Page 96 of 195 U RADIOACTIVE TABLE 3.9.2-1 GASEOUS EFFLUENT (Continued)

MONITORING INSTRUMENTATION TABLE NOTATIONS 1

a b

Operable and inservice at all times.

Available and in service when standby gas treatment system is in standby or operation. Table 3.4-1 sampling I

requirements are only applicable when VG flow is present.

c Channel OPERABILITY shall include the capability of the MCR ARPR LAN to provide the alarm status of the applicable II radiation monitor channel(s).

d Filter media (particulate collection patch for particulates and charcoal cartridge for iodines) in place with an operating sample pump constitutes an operable I'

iodine/particulate sampler.

e f

Operable and in standby/service modes 1, 2, and 3 only When standby gas treatment system is in operation.

I g When a channel is placed in an inoperable status solely for performance of required surveillances (source checks, sampling) entry into associated Remedial Requirements may be delayed for up to one hour.

II REMEDIAL REMEDIAL REQUIREMENT I

REQUIREMENT a. If communication using the alternative 8 terminals is inoperable, perform a CHANNEL CHECK using local monitor indication within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> II thereafter.

b. With the noble gas activity monitor channel(s) otherwise inoperable, effluent I

releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for gross noble gas activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

II REMEDIAL With the number of channels OPERABLE less than REQUIREMENT 9

required by the minimum channels OPERABLE requirement, effluent releases via this pathway £ a

may continue provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable, samples required by Table 3.4-1 are continuously collected with auxiliary sampling equipment.

REMEDIAL REQUIREMENT 10 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated II at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Alternate flow instruments or summation of system ventilation flows may be used in the estimation of SGTS and HVAC flow rates.

II II II CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 97 of 195 REMEDIAL REQUIREMENT ,With the number of OPERABLE Channels less than 11 required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

a. Initiate the preplanned alternate method of monitorinq the appropriate parameter(s).

b. Instrument inoperabil ity does not preclude changing mode.

CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 98 of 195 TABLE 3.9.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SOURCE CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Station HVAC Exhaust PRM

a. High-Range Noble Gas (3) M R(2) Q(1)

Activity Monitor

b. Low-Range Noble Gas (3) M R(2) Q(1)

Activity Monitor

c. Iodine Sampler W NA NA NA

d. Particulate Sampler W NA NA NA

e. Sample Flow Rate Measuring S NA R Q Device

f. Effluent System Flow Rate S NA R Q Measuring Device

2. Standby Gas Treatment System Exhaust PRM

a. High-Range Noble Gas (3) NA R(2) Q(1)

Activity Monitor S

b. Low-Range Noble Gas S(3) M R(2) Q(1)

Activity Monitor

c. Iodine Sampler W NA NA NA

d. Particulate Sampler W NA NA NA

e. Sample Flow Rate Measuring S NA R Q Device

f. Effluent System Flow Rate S NA R Q Measuring Device

3. Station HVAC Exhaust AXM

a. High-Range Noble Gas (3 M R(2) NA Activity Monitor (

b. Intermediate-Range Noble S(3) M R(2) NA Gas Activity-Monitor

c. Sample Flow Rate Measuring

• NA R NA Device CLINTON -- UNIT #1 Rev.22 - 12/09 SMm m - mm M

m , m * -- m --- mmmm , m m CY-CL-170-301 Revision 22 Page 99 of 195 TABLE 3.9.2-2 (cont'd)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SOURCE CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

4. Standby Gas Treatment System Exhaust. AXM

a. High-Range Noble Gas M R(2) NA Activity Monitor

b. Intermediate-Range Noble M R(2) NA Gas Activity Monitor

c. Sample Flow Rate Measuring

• NA .R NA Device

d. Automatic Operation(4) NA NA NA NA

5. Inservice Calibrations on NA NA A (a, b) NA Station HVAC Exhaust and Standby Gas Treatment System Exhaust PRMs

• Shiftly when-in operation with the pump running.

CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 I

Revision 22 Page 100 of 195 TABLE 3.9.2-2 (Continued) I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3 TABLE NOTATIONS a Per Regulatory Guide 1.21, compare the PRM readings with3 grab sample results for the noble gas and particulate/iodine channels. Modify the channel calibrations as ;necessary to ensure monitor readings are related to the concentration or release rates of nuclides in the monitored path.

I b Not applicable if the activity in the sample stream is not high enough to provide a statistically' relevant comparison.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that the MCR ARPR LAN responds with annunciation and event display to each of the following conditions:.

I

1. Instrument indicatesmeasuredlevels above the alarm (HIGH) setpoint,.

2. Detector failure (LOW FAIL, HI FAIL). 3

3. Sample flow failureý (EXTERNAL FAIL).

4. Instrument' not set in normal operate mode (CALIBRATE, MAINTENANCE, or"STANDBY).

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been 'obtained from supplierss that participate in measurement assurance activities with NIST.

1 These standards shall permit calibrating the'system over its intended range of energy and measurement range. Subsequent CHANNEL CALIBRATION shall be. performed using the initial radioactive standards or other 'standards of equivalent quality or radioactive sources that have been related to the initial calibration.

(3) The CHANNEL CHECK performed from the MCR ARPR LAN also verifies communication..

(4) Verify the SGTS AXM automatically starts upon initiation of DIV I SGTS and remains in service following shutdown of I DIV I SGTS. Periodicity = 24 months I

CLINTON -- UNIT #1 Rev.22 -

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i. - -mom=

n m M - i CY-CL-170-301 Revision 22 Page 101 of 195 FIGURE 3.1-1 CPS SITE BOUNDARY FOR GASEOUS EFFLUENTS LEGEND SITE BOUNDARY UNRESTRICTED AREA AREA SPECIAL UNRESTRICTED AREA(See Note 1)

AREA WITHIN SITE BOUNDARY NOT OWNED BY IPC RESIDENCE (TYP)

NOTE 4

'NOTE 3 HWY. 10 NOTES

1. The area in the lake between the buoys and the exclusion area boundary is unrestricted at this time.

But will be controlled if plant effluent conditions warrant closure.

2. Land parcel not owned by AmerGen, includes residences.

3. Land parcel not owned by AmerGen, oil company pipeline pumping station.

4. Land parcel not owned by AmerGen, agricultural use.

5. The lake shoreline is approximately 690 ft. MSL elevation line.

CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 U

Revision 22 Page 102 of 195 FIGURE 3.3-1 I MAIN CONDENSER OFF-GAS TREATMENT SYSTEM,"

U 1CA01AA I U

I U

GTSEXHAUST I

STACK

• Monitors'required by Sections 3.9.1 and 3.9.2 i 1CD01A Main Condenser OCA0ITA CV Separator Tank IN66B010B Cooler Condenser B 1N66D013 Charcoal Adsorber 1RIX-PR035 Off-Gas Post Treatment PRMý I

1CA01AA Steam Jet Air Ejector. A OCA01TB CV Separator Tank B

lN66Z003A

,Desiccant Dryer A 1N66D016 HEPA.

Filter 1RIX-PRO41 Off-Gas Post Treatment PRM.

a ICA01AB Stteam 1N66D005A lN66Z003B ORIX-PRO01 Jet Air Ejector B Recombiner A Desiccant Dryer B HVAC Stack .PRM

1. 1 ORIX-PRO03 Standby Gas Treatment PRM I

OCA01PA IN66D005B 1N66B011 Gas ORIX-PRO02 ORIX-PRO04 Condenser Vacuum (CV)

Pump A Recombiner B Cooler HVAC Stack PRM

1. 2 Standby Gas Treatment PRM I OCA01PB CV Pump B IN66B010A Cooler Condenser A 1N66D012 Charcoal Adsorber 1RIX-PR034 Off-Gas Pretreatment ORIX-PRO12 HVAC Stack AXM I PRM ORIX-PRO08 Standby Gas i Treatment AXM CLINTON -- UNIT #1 Rev.22 -

12/09 i

CY-CL-170-301 Revision 22 Page 103 of 195 TABLE 3.5-1 INHALATION DOSE FACTORS FOR INFANT - (DFAi)a (mrem per pCi inhaled)

NUCLIDE BONE-- LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 P-32 1.4 5E-03 8. 03E-05 5;53E-05 NO DATA NO DATA NO DATA 1. 15E-05 CR-51 NO DATA NO DATA 6. 39E-08 4.11E-08 9.45E-09 9. 17E-06 2. 55E-07 MN-54 .NO DATA 1. 81E-05 3 . 56E-06 NO DATA 3 .56E-06 7.14E-04 5. 04E-06 FE-55 1.41E-05 8. 39E-06 2 .38E-06 NO DATA NO DATA 6.21E-05 7. 82E-07 FE-59 9.69E-06 *1. 68E-05 6. 77E-06 NO DATA NO DATA 7. 25E-04 1. 77E-05 CO-58' '.NO DATA 8.71E-07 1 30E-06 ,NO DATA NO DATA 5.55E-04 7. 95E-06 CO-60. NO DATA 5. 73E-06 8 .41E-06 NO DATA, NO DATA 3.22E-03 2 28E-05 NI-63 2:.42E-04 1.46E-05 8 .29E-06 NO DATA, NO DATA 1 .49E-04 1. 73E-06 ZN-65 1.,38E-05 4.47E-05 2 .22E-05 NO DATA 2.32E-05 4.62E-04 3 .67E-05 RB-86 NO DATA 1.36E-04 6 30E-05 NO DATA NO DATA NO DATA 2 17E-06 SR-89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4 .57E-05 SR-90 2.92E-02 NO DATA 1. 85E-03 NO DATA NO DATA 8.03E-03 9 .36E-05 Y-90 2.35E-06 NO DATA 6 .30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y-91 4.20E-04 NO DATA I.'12E-05 NO DATA NO DATA 1.75E-03 5 .02E-05 ZR-95 8.24E-05 1.99E-05 .145E-05 NO DATA;, 2.22E-05 1.25E-03 1.55E-05 NB-95 1. 12E-05 4.59E-06 2*7OE-06 NO DATA 3.37E-06 3.42E-04 9 .05E-06 MO-99 NO DATA 1.18E-07 2.31E'08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC-99m 9.98E-13 2.06E-12 2166E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 RTJ-103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RUJ-106 6.20E-05 NO DATA 7.70E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG-II0m 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE-125m 3.40E-06 1.42E-06 4.70E-07 1. i6E-06 NO DATA 3.19E-04 9.22E-06 TE-127m 1.19E-05 4.93E-06 1.48E-06 3*.48E-06 2.68E-05 9.37E-04 1.95E-05 TE-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 1-133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA. 1.31E-06 CS-134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS-136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS-137 3 . 92E-04 4 37E-04 3 .25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 BA- 140 4 *0OE-05 4 OOE-08 2. 07E-06 NO DATA 9. 59E-09 1. 14E-03 2.74E-05 CE-141 1. 98E-05 1. 19E-05 1.42E-06 NO DATA 3. 75E-06 3.69E-04 1. 54E-05 CE.- 144' 2-. 28E-03 8 65E-04 1.26E-04 NO DATA 3 .84E-04 7.03E-03 1. 06E-04 PR- 143 1. ODE-05 3. 74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 ND-147 5.67E-06 5. 81E-06. 3. 57E-07 NO DATA 2 .25E-06 2.30E-04 2 .23E-05 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 U

Revision 22 Page 104 of 195 II TABLE 3.5-2 INHALATION DOSE FACTORS FOR CHILD - (DFAi)a I

NUCLIDE BONE LIVER (mrem per pCi inhaled)

T.BODY THYROID KIDNEY LUNG GI-LLI I

H-3 NO DATA 3.04E-07 .3.04E-07 3.04E-07 3.04E-07. 3.04;E-07 3.04E-07 P-32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR-51 NO DATA NO DATA 4.,17E-08 2.31E-08 6.57E 4.59E-06 '2.93E-07 MN-54 NO DATA .1.16E-05 ,2.57E-06 NO DATA 2.71E-06 4.26E-04 .6.19E-06 FE-55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.OOE-05 7.75E-07 FE-59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3".43E-04 1.91E-05 CO-58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO-60 NO DATA 3.55E-06 -6.12E-06 NO DATA NO DATA .1.91E-03 2.60E-05 NI-63 ZN-65 RB-86 2.22E-04 1.15E-05 NO DATA 1.25E-05 , 7.56E-06 3.06E-05 5.36E-05 i.90E-05 3.09E-05 NO DATA NO DATA NO DATA NO DATA 1.93E'05 NO DATA 7.43E-05 2.69E-04

-NO DATA 1.71E-06 4.41E-06 2.16E-06 p

SR-89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5..83'E-04 4.52E-05 SR-90 2.73E-02 NO DATA: "I74E-03 NO DATA NO DATA 3.99E-03 .9.28E-05 Y-90 1.11E-06 NO DATA -_2. 999E-08 ... NO.DATA NO'DATA 7.07E-05 -7.24E-05 Y-91 2.47E-04 NO DATA 6.59E-06 NO.DATA NO DATA 7.10E-04 4.97E-05 ZR-95 5.13E-05 1.13E 05 .,1ý.OOE-05;, NO.DATA '1.61E-05 6.03E-04 1:65E-05

.NB-95 6.35E-06 2.48E-06 1. 77E-06 NO DATA 2.33E-06 1I66E-04 1.OOE-05 MO-99 NO DATA .4.66E-08 1.I,.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 TC-99m 4.81E-13' 9.41E-13 1L56Ei t ...... NO DATA 1.37E-11 2.57E-07 1.30E-06 RU-103 7.55E-07 NO DATA 2.90E-07 NODATA 1.90E-06 1.79E-04 1.21E-05 RU-106 3.68E-05 NO DATA ý.57E-06 NO DATA 4;97E-05 3.87E-03 -I1.16E-04 AG -iIm 4.56E-06 3.08E-06 .2.,47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05

• TE-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE-127m 6.72E-06 2.31E-06 8.18E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE-129m . 5.19E-06 1.85E-06 8,22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 1-131 1.30E-05 1.30E-05:, 7.37E-06 4.39E-03, 2.13E-05 NO DATA 7.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 1 -133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04: 3.62E-06 NO DATA 1.20E-06

.. CS-134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 CS-136 1.76E-05 4,62E-05 3.,14E-05 NO DATA 2.58E-05 3-93E-06 ' 1.13E-06 CS-137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05

• 9.78E-07 BA-140 2.OOE-05 1.75E-08 1.17E-06' NO DATA 5.71E-09: 4.71E-04 2.75E-05 CE-141 1.06E-05.. 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE-144 1.83E 5.72E-04 9.77E-05 :NO DATA 3.17E-04 3.23E-03 :1.05E-04 PR-143 4.99E-06 1.50E-06 2.47E-07

• NO DATA 8;11E-07 1.17E-04 2.63E-05 ND-147 2.92E-06 2.36E-06 1.84E-07' NO DATA 1.30E-06 8.87E-05 2.22E-05 I

I I

I CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 105 of 195 TABLE 3.5-3 INHALATION DOSE FACTORS FOR TEEN - (DFAi)a (mrem per pCi inhaled)

NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 1.59E-07 1.59E-07 1.59E-07, 1.59E-07 1.59E-07 1.59E-07 P-32 2.36E-04 1.37E-05 8'95E-06 NO DATA NO DATA: NO DATA 1.16E-05 CR-5i NO DATA NO DATA 1.69E-08 9.37E-09 -3.84E-09 2.62E-06 3.75E-07 MN-54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 FE-55 ' 4.;18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE-59

• 1*99E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 CO-58 NO DATA 2.59E-07 3.47E-07 NO DATA 'NO DATA 1.68E-04 1.19E-05 CO-60 NO DATA 1.89E-06 2.48E-06 NO DATA -NO: DATA 1.09E-03 3.24E-05 NI-63 7.2.5E'05. 5.43E-06 2.47E-06 NO DATA °NO-DATA 3.84E-05 1.77E-06 ZN-65 ._82E-06 1.67E-05 7.80E-06 NO DATA 1.-08E-05 1.55E-04 5.83E-06 RB-86  ::.NO DATA 2.38E-05 1.05E-05 NO DATA- NO DATA NO DATA 2.21E-06 SR-89 - 5.43E-05 _NO DATA '1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR-90 I,.35E-02 'NO DATA 8.35E-04 NO DATA -'NO DATA 2.06E-03 9.56E-05 Y-90 3.73E-07 NO DATA 1.OOE-08 NO DATA NO DATA *3.66E-05 6.99E-05 Y-91 8.26E-05 NO DATA 12.21E-06 NO DATA NO DATA 3.67E-04 5;11E-05

.ZR-95 1.82E-05 5.73E-06 3.94E-06 NO'DATA 8'.42E-06 3..36E-04 ' 1.86E-05 NB-95 2.32E-06 1.29E-06 7.08E-07 NO DATA ' 1.25E-06 9.39E-05 1.21E-05 MO-99 NO'DATA 2.11E-08 ".403E-09"' NO.DATA " 5.14E-08 1.92E-05 3.36E-05 TC-99m 1.73E-13 4.83E-13 6.24E-12. NO-DATA 7.20E-12 1.44E-07 7.66E-07 RU-103 2.63E-07 NO DATA 1'.12E-07 NO DATA 9.29E-07 9.79E-05 .. 36E-05 RU-106 i.23E-05ý NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG-I 1.73E-06 1m 1.64E-06 9.99E-07 NO DATA .3.13E-06 8.44E-04 3.41E-05 TE-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE-127m. 2.25E-06 1.02E-06 2.73E-07. 5.48E-07' 8.17E-06 2.07E-04 '1.99E-05 TE-129m I..74E-06 8.23E-07 2.81E-07 5'72E-07 6.49E-06 2.47E-04 5.06E-05 1-130 7.80E-07 2.24E-06 8.96E-07 I..86E-04 3.44E-06 NO DATA 1.14E-06

-I1i31 .4.43E-06 6.14E-06 3.30E-06 1.83E I:.05E-05 NO DATA 8.1iE-07 I-132 *i1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA i-.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 1-134 1.IE-07 2..90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09

.1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 CS-134 6.28E-05 -1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS-136 6.44E-0G6 2.42E-05 1.71E-05 NO DATA i.38E-05 2.22E-06 1.36E-06 CS-137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3'80E-05 i.51E-05 ' 1.06E-06 BA-140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 CE-14i 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.llE-06 7.67E-05 1.58E-05 CE-144 6iliE-04 2.53E-04 3.28E-05 NO DATA I.51E-'04 ' I!67E-03 1.08E-04 PR-i43 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07.' 6.04E-05 2.67E-05 ND-147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.'28E 4.65E-05 2.28E-05 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 U

Revision 22 Page 106 of 195 I

TABLE 3.5-4 I INHALATION DOSE FACTORS FOR ADULT - (DFAi) a NUCLIDE BONE LIVER (mrem per pCi inhaled)

T. BODY THYROID KIDNEY LUNG IO U

GI-LLI H-3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 P-32 1.65E-04 9. 64E- 06 6.26E-06 NO DATA. NO DATA NO DATA 1. 08E-05 CR-Si NO DATA NO DATA 1. 25E-08 7.44E-09 2 .85E-09 1.80E-06 4. 15E-07 MN-54 FE-5S FE-59 NO DATA

3. 07E-06 1.47E-06

4. 95E-06 2.12E-06 3.47E-06

7. 87E-07

4. 93E-07

1. 32E-06 NO DATA NO DATA NO DATA.

1.23E-06 NO DATA NO DATA 1.75E-04

9. 01E-06 1.27E-04

9. 67E-06

7. 54E-07 2.35E-05

=1 CO-58 NO DATA 1. 98E-07 2. 59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 CO-60 NI-63 ZN-65 NO DATA 5.40E-05

4. 05E-06 1.44E-06 3 . 93E-06 1.29E-05

1. 85E-06

1. 81E-06

5. 82E-06 NO DATA NO DATA NO DATA NO DATA NO DATA 8.62E-06 7.46E-04 2.23E-05 1.08E-04 3.56E-05

1. 67E-06 6.68E-06 i

RB-86 NO DATA 1. 69E- 05 7. 37E-06 NO DATA NO DATA NO. DATA 2.08E-06 SR-89 3. 80E-05 NO DATA 1. 09E-06 NO DATA NO DATA 1.75E-04 4. 37E-05 SR-90 Y-90 Y-9i 1.24E-02 2 . 61E-07

5. 78E-05 NO DATA NO DATA NO DATA

7. 62E-04

7. 01E-09

1. 55E-06.

NODATA NO DATA NO DATA NO DATA NO DATA NO DATA 1.20E-03 2 . 12E-05 2.13E- 04 2.21E-04 9.02E-05 6.32E-05

4. 81E-05 I

ZR-95.. 1.34E-05 4.30E *2*. 91E-06 NO-DATA 6. 77EE-06 1.88E-05

=1

'NO DATA NB-95 1.76E-06 9.77E-07 5. 26E-07 9. 67E-07 6. 31E-05 1.30E-05 MO-99 NO DATA 1.51E-08 2. 87E-09' ,ýNO DATA 3 .64E-08 1.14E-05 3. 10E-05 TC-99m 1.29E-13 3 . 64E-13 4 . 63E712* 'NO DATA 5. 52E-12 9.5SE-08 5 20E-07 RU-103 1. 91E-07 NO DATA 8.23E-08 NO DATA 7. 29E-07 6.31E-05 1.38E-05 RU-106 AG-Il0m TE-125m 8.64E-06 1.35E-06 4.27E-07 NO DATA 1.25E-06

1. 98E-07 1:09E-06 7.43E-07 5.84E-08 NO DATA NO DATA 1.31E-07

1. 67E-05 2 .46E-06

1. 55E-06

1. I:7E-03 5.79E-04

3. 92E-05

1. 14E-04 3.78E-05 8.83E-06

=3 TE-127m 1.58E-06 7 .21E-07 1. 96E-07 4.11E-07 5.72E-06 1.20E-04 1. 87E-05 TE-i29m 1-130 1-131 1.22E-06

5. 72E-07 3 . 15E-06 5.84E-07

1. 68E-06 4 .47E-06 1.98E-07 6.60E-07 2.56E-06 4.30E-07 1.42E-04 1.49E-03

4. 57E-06

2. 61E-06 7.66E-06 1.45E-04 NO DATA NO DATA

4. 79E-05 9.61E-07 7.85E-07 B

1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA .5. 0,8E-08 17133 1-134 1-135 "1.08E-06

8. 05E-08 3 . 35E-07

1. 85E-06 2 .16E-07 8.73E-07 5.65E-07 7.69E-08 3 .21E 2.69E-04 3.73E-06

.5.60E-05 3.23E-06 3.44E-07 1.39E-06 NO DATA NO DATA NO DATA

1. 1IE-06 1.26E-10 6 .56E-07

-I CS-134 CS-136 CS-137

,BA7140 4.66E-05 4.88E-06

5. 98E-05 4 .88E-06

1. 06E-04 1.83E-05

7. 76E- 05 6.. 13E-09

9. IE-05 1.38E-05 5 .35E-05 3 .21E-07 NO DATA

.NO DATA NO DATA NO DATA 3.59E-05 1.07E-05

2. 78E-05

2. 09E-09 1.22E-05 1.50E-06 9.40E-06

.1. 59E-04 1.30E-06 1.46E-06 1.05E-06

-I 2.73E-05 CE-141 CE-I44 PR-143 2 .49E-06

4. 29E-04

1. 17E-06 1.69E-06

1. 79E-04

4. 69E-07

1. 91E-07 2.30E-05

5. 80E-.08 NO DATA NO DATA NO-DATA 7.83E-07 1.06E-04 2.70E-07 4 .52E-05

9. 72E-04 3 .51E-05 1.50E- 05

1. 02E-04 2.50E-05

-I ND-147 6 . 59E-07 7. 62E-07 4.56E-08 NO DATA 4.45E-07 2 .76E-05 .2..16E-05 I

I I

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CY-CL-170-301 Revision 22 Page 107 of 195 TABLE 3.5-5 GROUND PLANE DOSE FACTORS DFGi.

,.(mrem/hr per pCi/m2 )

ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 P-32 0.0 ".:0.0 Cr-51 2 .20E-10 2.60E-10 Mn-54 - 5 .80E-09 6 .80E-09 Fe-55 . 0.0 0.0 Fe-59 8 .OOE-09 9.40E-09 Co-58 -- 7. 00E-09 8.20E-09 Co-60 1.70E-08 2 .OOE-08 Ni-63 . 0.0 0.0 Zn-65 4.00E-09 4.60E-09 Rb-86 66.30E-I0 7.20E-10 Sr-89 5 .-60E-t13 6.50E-13 Y-90 ..2.20E- 12., 2 .60E-12 Y-91 2-ý40E-8,'11. 2 .70E 11 Zr-95 5.OOE-:09' 5 .80E-09 Nb-95 5.10E-09 6.OOE-09 Mo-99 1 .90E-09. 2.20E-09

.Tc-99m, 9.60E-10 1.10E-09 Ru-103 3.60E-09, 4 .20E-.09-Ru-106 1.50E-09 1.80E-09

ýAg-il0m 1.80E-08 2. lOE-08 Te-125m 3.50E-II 4 .80E-ii Te-127r 1.10E-12 it 1.30E-12 Te -129m 7 . 70E-10 9. OOE-10.

1-130 i.40E-08 1.70E-08 1-131 2.80E-09 3.40E"09 IT-132 1.70E-08 2.00E-08 T-133 3.70E-09 4.50E-09 i-i34 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134* 1.20E-08 1.40E-08 Cs-i36ý 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Ba-140 2.10E-09 2.40E-09 Ce-141 5.50E-I0 6.20E-10 Ce-144 3.20E-I0 3.70E-10 Pr-143 0.0 0.0 Nd-147 1.OOE-09 1.20E-09 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 II Revision 22 Page 108 of 195 I

TABLE 3.5-6 INGESTION DOSE FACTORS FOR INFANT - (DFLi)a I

NUCLIDE BONE LIVER (mrem per pCi ingested)

T.BODY THYROID KIDNEY LUNG GI-LLI II H-3 P-32 CR-51 NO DATA 1.70E-03 NO DATA 3.08E-07 1.00E-04 NO DATA 3.08E-07

.6.59E-05 1.41E-08

'3.08E-07 NO DATA 9.20E-09 3.08E-07 NO DATA 2.01E-09 3.08E-07 NO DATA 1.79E-08 3.08E-07 2.30E-05 4.11E-07 U

MN-54 NO DATA. 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 FE-55 1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 CO-60 NO DATA 1.08E-05.5 2.55E-05 NO DATA NO DATA -NO DATA 2.57E-05 NI-63 6.34E-04 3.92E 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 ZN-65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 RB-86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA . NO DATA 4.'34E-06 SR-89 2.51E-03 NO DATA .7.20E-05 NO DATA NO DATA NODATA .5.16E-05 SR-90 Y-90 Y-91 1.85E-02 8.69E-08 1.13E-06 NO DATA NO DATA NO DATA 4.71E-03

.O2.33E-09 3.01E-08 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA

,:NO DATA NO DATA NO DATA 2.31E-04 1.20E-04 8.10E-05 U

ZR-95 2.06E-07 5.02E-08 .3:56E-08 NO, DATA .5.41E-08 NO DATA 2.50E-05 NB-95 MO-99 '

TC-99m 4.20E-08 NO DATA 1.92E-09 1.73E-08 3.40E-05 3.96E-09

'I.OOE-08

6. 63E-06,

'5.10E-08 8:

NO DATA, NO DATA NO DATA 1.24E-08 5.08E-05 4.26E-08 NO DATA NO DATA 2.07E-09 1.46E-05 1.12E-05 1.15E-06 U

RU-103 1.48E-06 NO DATA 4.95E-07 NO DATA

• 3.08E-06 NO DATA 1.80E-05 RUt106 2.41E-05 NO DATA 3.01E-06 NO' DATA 2.85E-05 NO DATA ý1.83E-04 AG-II0m 9.96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE-125m 2.33E-05 7.79E-06. 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE-127m 5.85E-05 E-05 -05 " 7.08E-06 1.69E-05 1.44E-04 NO. DATA 2.36E-05

• TE-129m 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 1-130 6.OOE-06 1.32E-05, 5.30E-06 1.48E-03 1.45E-05 NODATA 2.83E-06 1-131 3.59E-05 4.23E-05. 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 1 3.76E-06 NO DATA 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1'.84E-06 1-135 3.64E-06 7.24E-06, 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 CS-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E 7.42E-05 1.91E-06 CS-136 4.59E-051 1,35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05

• 2.OSE-06 CS-137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 p

BA-140 1.71E-04 1.71E-07 8.81E-06 NO DATA . 4.06E-08 1.05E-07 ' 4.,20E-05 CE-141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE-144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR-143 8..13E-08', 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA .4.29E-05 ND-147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08' NODATA 3.60E-05 U

I CLINTON -- UNIT #1 Rev.22 -

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'TABLE 3.5-7 INGESTION*DOSE FACTORS FOR CHILD -(DFLi)&

(mrem per pCi ingested:)

NUCLIDE BONE LIVER T.BODY THYROID 'KIDNEY LUNG GI-LLI H-3 NO' DATA 2.03E-07 2.03E-07 2.03E-07 '2.03E-07 '2.03E-07 2.03E-07 P-32 8:.25E-04 ,3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 CR-51 ýNO DATA NO DATA 8.90E-09 4.94E-09 i.35E-09 9.02E-09 4.72E-07 MN-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 FE-55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 CO-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 CO-60 NO'DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI-63 5.38E-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA I1.94E-06 ZN-65 1.37E-05 3.65E-05 2.27E-05:- ,NO DATA 2.30E-05. NO DATA 6.41E-06 RB-86 NO DATA , 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 SR-89 '1.32E-03 NO-DATA 3.77E-05 NO DATA NO DATA NO DATA 5.11E-05 SR-90 1.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 Y-90 4.11E-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04 Y-91 6.02E-07 -NO DATA 61E.6iE8 NO DATA- NO DATA: NO DATA 8.02E-05 ZR-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 NB-95 2.25E-08 8.76E-09 6.26E-09 NOýDATA 8.23E-09 NO DATA 1.62E-05 MO-99 NO DATA 1.33E-05 3;29E-06 .,NO DATA,: 2.84E-05 NO DATA 1.10E-05 TC-99m 9.23E-10 1.81E-09 3.OOE-08' NO DATA 2.63E-08 9.19E-10 1.03E-06 RU-103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 RU-106 1.17E-05 NO DATA .146E-06' NO:DATA 1.58E-05 NO DATA l.82E-04 AG-110m 5.39E-07 3.64E-07 2.9iE-07' NO DATA 6.78E-07 NO DATA 4.33E-05 TE-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.1I0E-05 TE-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 . 8.,24E-05 NO DATA .2.34E-05 TE-129m 4.87E-05 1.36E 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 1-1-30 2.92E-06' 5.90E-06 3.04E-06 6.50E-04 ': 8.82E-06 NO DATA 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA .1.54E-06 1-132 8.00E-07 -1.47E-06 6.76E-07 6.82E-05 2.25E-06 NO DATA 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 1-134 4;19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA .. 5.16E-07 1-135 1.75E-06 3.15E-06' 1.49E-06 2.79E-04 4.83E-06. NO DATA :2.40E-06 CS-134 - 2.34E-04. 3.84E-04 8.10E-05 NO DATA 1.'19E-04 4.27E-05 2.07E-06 cs-i36 2.35E-05 6.46E-05 4.18E-05 NO DATA 3;44E705 . 5.13E-06 2.27E-06 CS-137 3.27E-04i 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 BA-140 8.31E-05' 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 CE-141 8.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09'. NO DATA 2.47E-05 CE-144 2.08E-06: 6.52E-07 1.I1E-07 NO DATA 3.61E-07' NO DATA 1.70E-04 PR-143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 ND-147 2.79E-08 2.26E-08 1.75E-09 ' NO DATA 1.24E-08.: NO DATA 3.58E-05 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 U

Revision 22 Page 110 of 195 I

TABLE 3.5-8 INGESTION DOSE FACTORS FOR TEEN - (DFLi)a NUCLIDE BONE LIVER (mrem per pCi ingested)

T. BODY THYROID KIDNEY LUNG GI-LLI I

NO DATA I.06E-07 1.06E-07 1.06E-07 1. 06E-07 1. 06E-07 H-3 1. 06E-07 P-32 CR-51 MN-54 2.76E-04 NO DATA NO DATA

1. 71E-05 NO DATA

5. 90E-06

1. 07E-05 3.60E-09

1. 17E-06 NO DATA

2. 00E-09 NO DATA NO DATA 7.89E-10 1.76E-06 NO DATA 5.14E-09 NO DATA 2.32E-05

6. 05E-07

1. 21E-0S U

FE-55 3. 78E-06 2 . 68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1. 16E-06 FE-59 CO-58 CO-60 5.87E-06 NO DATA NO DATA 1.37E-05

9. 72E-07 2.81E-06 5.29E-06 2 .24E-06 6.33E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 4 .32E-06 NO DATA NO DATA 3.24E-05 1.34E-05 3.66E-05 I

NI-63 ZN-65 RB-86 1.77E-04 5.76E-06 NO DATA 1.25E-05 2 00E-05 2 . 98E-05

6. OOE-06 9..33E-06 1.40E-05 NO DATA NO DATA NO DATA NO DATA l..28E-05 NO, DATA NO DATA NO DATA NO DATA

.1.99E-06

.8.47E-06

4. 41E-06

-I SR-89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA 5.24E-05 SR-90 Y-90 Y-91 8.30E-03 1.37E-08 2.01E-07 NO DATA NO DATA

-NO DATA 2.05E-03 3%.69E-10 5.39E-09 NO DATA NO-DATA

-NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 2.33E-04

.1.13E-04 8.24E-05 I

ZR-95 4.12E-08 1.30E-08 ,8:94E-09 NO DATA 1.91E-08 NO DATA 3.OOE-05 NB-95 MO-99 TC-99m 8.22E-09 NO DATA, 3.32E-10 4.56E-09 6.03E-06 9.26E-10 2.*51E-09 1- 15E-06, 17.20E-08 NO DATA NO DATA NO DATA 44.42E-09 1.38E-05 1.38E-08 NO DATA NO DATA 5.14E-10 1.95E-05 1.08E-05 6.08E-07 I

RU-103 2.55E-07 NO DATA 1_ 09E-07 NO DATA 8.99E-07 NO DATA 2..13E-05 RU-106 AG-II0m.

-TE-125m 3.92E-06 2.05E-07 3.83E-06 NO DATA 1.94E-07 1.38E-06, 4.94E-07

..:18E-07 5.12E-07 NO DATA NO DATA 1.07E-06&

7.56E-06 33.70E-07 NO DATA NO DATA NO DATA NO DATA

1. 88E-04 5.45E-05 1.13E-05 I

TE-127m 9.67E-06, 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2 .41E-05 TE-1299m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 1-130 1.03E-06 , 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 .2,.39E-03 1.41E-0S NO DATA 1.62E-06 I1-32 1-133 1-134 2.79E-07 2.01E-06 1.46E-07 7.30E-07 3.41E-06 3.87E-07 2.62E-07 1.04E-06 1.39E-07 2.46E-05 4.76E-04 6.45E-06

-1.15E-06 5.98E-06 6.10E-07 NO DATA NO DATA NO DATA 3.18E-07 2.58E-06 5.10E-09 I

I-l35 6.10E-07,- 1.57E 5.82E-07 1.01E-04 2;.48E-06 NO'DATA 1.74E-06 CS-134 8.37E-05 *1.:97E-04 9.14E-05 NO DATA 6.26E-OS 2.39E-05 2.45E-06 CS-136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS-137 1.12E-04 .149E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 BA-140 2.84E-05, 3.48E-08 1.83E-06 NO DATA 1.18E-08 , 2.34E-08 4.38E-05 CE-141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4,18E-09, NO DATA 2.54E-OS CE-144 6.96E 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA *1.75E-04 PR-143 1.31E-08 5.23E-09 6.52E-10 NO DATA 3.04E-09 NO DATA 4.31E-05 ND-147 9..38E-09 1.02E-08 6.11E-10 NO:DATA 5.99E-09 NO DATA 3.68E-05 Il I

I I

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CY-CL-170-301 Revision 22 Page 111 of 195 TABLE 3.5-9 INGESTION DOSE FACTORS FOR ADULT - (DFLi)a (mrem per pCi ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI--LLI H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 "1.05E-07 1.05E-07 P-32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR-51 NO DATA NO DATA 2.66E-09 11.59E-09 5.86E-10 3.53E-09 6.69E-07 MN-54 NO-DATA 4.57E-06 8.72E-07 NO DATA 1-.36E-06 NO DATA 1.40E-05 FE-55 - 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI-63 :1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 ZN-65 *4.84E-06. 1.54E-05 6.96E-06 NO DATA 1-.;03E-05 NO DATA 9.70E-06 RB-86 'NO DATA .2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 SR-89 3.08E-04 NO DATA 8.84E-06 NO DATA. NO DATA NO DATA 4.94E-05 SR-90 77.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 Y-90 9:-.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y-91 1.41E-07 NO DATA *'3.77E-09 NO.'DATA NO DATA NO DATA 7.76E-05

.ZR-95 3.O4E-08 9.75E-09 6!.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 NB-95 6.22E-09 3.46E-09 "1.86E-09ý NO DATA 3.42E-09' NO DATA 2.10E-05 MO-99 NO DATA 4.31E-06 ý.8.2"0E-07:ý NO DATA 9.76E-06 NO DATA 9.99E-06 TC-99m 2.47E-10 6.98E-10 8.89E-09 NO-DATA 1.06E-08 3.42E-10 4.13E-07 RU-103 1.85E-07 NO DATA 7.97E-08 NO'DATA 7.06E-07 NO DATA 2.1'6E-05

• RU-106 2.75E-06 NO DATA 3.48E-07. NODATA 5.31E-06 NO DATA 1.7.8E-04 AG-Il0m 1.60E-07 1. 48E-07 8. 79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE-125m 2 . 68E-06 9. 71E-07 3.59E-07 8. 06E-07 1.09E-05 NO DATA 1 .07E-05 TE-127m 6. 77E-06 2 .42E-06 8. 25E-07 1'.73E-06 2.75E-05 NO DATA 2 .27E-05 TE-129m 1.15E-05 4 .29E-06 1.82E-06 3 .95E-06 4. 80E-05 NO DATA 5.79E-05 1-130 7 56E-07 2. 23E-06 8 80E-07 1.89E-04 3.48E-06 NO DATA 1. 92E-06 1-131 4 .16E-06 5.95E-06 3 .41E-06 1. 95E i.02E-05 NO DATA 1.57E-06 1-132 2.03E-07 5. 43E-07 1. 90E-07 1. 90E-05 8.-65E-07 NO DATA 1. 02E-07

• 1-133 1.42E-06 2 .47E-06' 7 .53E-07 3. 63E-04 4.31E-06 NO DATA 2.22E-06 i1-134 1.06E-07 2.88E-07 1. 03E-07 4. 99E-06 4.58E-07 NO DATA ,2. 51E-10 1-135 4.43E-07 1.,16E-06 4 .28E-07 7. 65E-05 1. 86E-06 NO DATA 1. 31E-06

-CS-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4. 79E-O5 1.59E-05 2. 59E-06 CS-136 6. 51E-06 2. 57E-05 1. 85E-05 NO DATA 1.143E-05 1. 96E-06 2 . 92E-06 CS-137 7. 97E-05 1. 09E-04 7 14E-05 NO DATA 3.70E-05 1 *23E-05 2. 11E-06 BA-140 2.03E-05 2. 55E-08 1. 33E-06 NO DATA 8 .67E-09 1.46E-08 4. I8E-05 CE7141 9. 36E-09 6233E-09 7. 18E-10 NO DATA 2 .94E-09 NO DATA 2.42E-05 CE-144 4. 88E-07 2 . 04E-07 2. 62E-08 NO DATA 1.21E-07 NO DATA 1. 65E-04 PR7143 9 20E-09' 3. 69E-09 4. 56E-10 NO DATA 2 .13E-09 NO DATA 4.03E-05 ND-147 6 .29E-09 7 :27E-09 4. 35E-10 NO DATA 4 .25E-09 NO DATA 3.49E-05 CLINTON -- UNIT #1 Rev.22'-

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CY-CL-170-301 I

Revision 22 Page 112 of 195 I

TABLE 3.5-10 INPUT PARAMETERS FOR CALCULATING RCija Parameter Value Table* I QF (kg/day) 50 for cow E-3 Uap (liters/yr) - Infant 6 for goat 330 E-5 U

- Child 330 E-5 Teen 400 E-5 Adult 310 E-5 Yp (kg/M2 ) 0.7 E-15 Ys(kg/m 2 ) 2.0 E-25 Fm (days/liter) Each stable element for cow Each stable element for goat E-2' r(dimensionless) 1.0 for radioiodine 0.2 for particulates E-15 E-15 I

tf (seconds) th(seconds) 1.73E+05(2 days) 7.78E+06(90 days)

E-15 E-15 U

fs (dimensionless) 1.0 for cow 1.0 for goat NUREG 0133 Section I

5.3.1.3 f p(dimensionless) 1.0 for cow NUREG -

1.0 for goat 0133 Section 5.3.1.3

• of Regulatory Guide 1.109 unless otherwise stated I

i i

CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 113 of 195 TABLE 3.5-11 INPUT PARAMETERS FOR CALCULATING RMija Parameter Value Table*

Uap (liters/yr) - Infant 0 E-5

- Child 41 E-5 Teen 65 E-5 Adult 110 E-5 Ff (days/kg) Each stable element E-1 ts (second~s) 1.73E+06 (20 days) E-15 th (sedonds) 7.78E+06 (90 days) E-15 Yp(kg/m 2) 0.7 E-15 Ys(kg/m 2 ) 2.0 E-15 r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Qf (kg/day) 50 E-3

• of Regulatory Guide 1.109 CLINTON -- UNIT #1 Rev.22 -

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TABLE 3.5-12

.,'.INPUT PARAMETERS FOR CALCULATING RVija U

Parameter ULa (kg/yr) Infant Value 0

Table* I

- E-5 Child, Teen Adult

-26 42 64 E-5 E-5 E*-.5 U

usa (kg/yr)

- Infant Child Teen 0

520 630 E-5 E-5 E-5 I

fL (dimensionless)

- Adult 5.20 1.01 E-5 E-15 -

I fg (dimensionless),

II 0.76 E-15 tL (seconds) 8-.60E+04 (1 day) E-15 th (seconds) 5'l8E+06, (60 days). .E-15 Yv (kg/m2) -2.0 E-15 U

• of Regulatory Guide 1.109' U

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CY-CL-170-301 Revision 22 Page 115 of 195 TABLE 3.5-13 INHALATION PATHWAY FACTORS - RIija (INFANT) 3 (mrem/yr per gCi/m )

ORGAN: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 P-32 2.03E+06 1.12E+05 7.74E+04 NO DATA NO DATA NO DATA 1.61E+04 CR-51 NO DATA NO DATA 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3. 57E+02 MN- 54 NO DATA 2 .53E+04 4.98E+03 NO DATA 4.98E+03 1.OOE+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 NO DATA NO-DATA 8.69E+04 1.09E+03 FE-59 1.36E+04 2 .35E+04 9.48E+03 NO DATA NO DATA 1.02E+06 2. 48E+04 CO-58 NO DATA 1.22E+03 1.82E+03 NO DATA NO DATA 7.77E+05 1.11E+04 CO-60 NO DATA 8 .02E+03 1.18E+04 NO DATA NO DATA 4.51E+06 3 .19E+04 NI-63 3.39E+05 2. 04E+04 1.16E+04 NO DATA NO DATA 2.09E+05 2 .42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 NO DATA 3.25E+04 6.47E+05 5. 14E+04

'RB-86 NO DATA 1.90E+05 8.82E+04 NO DATA NO DATA NO DATA 3 .04E+03 SR-89 3.98E+05 NO DATA 1.14E+04 NO DATA NO DATA 2.03E+06 6.40E+04 SR-90 4.09E+07 NO DATA 2.. 59E+06 NO DATA NO DATA 1.12E+07 . 1.31E+05 Y-90 3.29E+03 NO DATA 8.82E+01 NO DATA NO DATA 2.69E+05 1.04E+05 Y-91 5.88E+05 NO DATA 1.157E+04 NO DATA NO DATA 2.45E+06 7.03E+04 ZR-95 1.15E+05 2.79E+04 2.03E+04 NO DATA 3.11E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 NO DATA 4.72E+03 4.79E+05 1.27E+04 MO-99 NO DATA 1.65E+02 3.23E+01 NO DATA 2.65E+02 1.35E+05 4. 87E+04 TC-99m 1.40E-03 2.88E-03 3.72E-02 NO DATA 3.11E-02 8.11E+02 2 .03E+03 RU-103 2.02E+03 NO DATA 6.79E+02 NO DATA 4.24E+03 5.52E+05 i.61E+04 RU-106 8.68E+04 NO DATA 1.09E+04 NO DATA 1.07E+05 1.16E+07 1.64E+05 AG-II0m 9.98E+03 7.22E+03 5.00E+03 NO DATA 1.09E+04 3.67E+06 3 .30E+04 TE-125m 4.76E+03 1.99E+03 6.58E+02 1.62E+03 NO DATA 4.47E+05 1. 29E+04 TE-127m 1.67E+04 6 .90E+03 2.07E+03 4. 87E+03 3.75E+04 1.31E+06 2. 73E+04 TE-129m 1.41E+04 6. 09E+03 2.23E+03 5. 47E+03 3.18E+04 1.68E+06 6. 90E+04 1-130 6.39E+03 1. 39E+04 5.57E+03 1. 60E+06 1.53E+04 NO DATA 1.99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 NO DATA 1.06E+03 1-132 1.69E+03 3. 54E+03 1.26E+03 1. 69E+05 3.95E+03 NO DATA 1.90E+03 1-133 1.32E+04 1. 92E+04 5.60E+03 3 .56E+06 2.24E+04 NO DATA 2.16E+03 1-134 9.21E+02 1. 88E+03 6.65E+02 4.45E+04 2.09E+03 NO DATA 1.29E+03 1-135 3.86E+03 7. 60E+03 2.77E+03 6. 96E+05 8.47E+03 NO DATA 1.83E+03 CS-134 3.96E+05 7. 03E+05 7.45E+04 NO DATA 1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1. 35E+05 5.29E+04 NO DATA 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6. 12E+05 4.55E+04 NO DATA 1.72E+05 7. 13E+04 1.33E+03 BA- 140 5.60E+04 5. 60E+01 2.90E+03 NO DATA 1.34E+01 1. 60E+06 3.84E+04 CE-141 2.77E+04 1. 67E+04 1.99E+03 NO DATA 5.25E+03 5. 17E+05 2.16E+04 CE-144 3.19E+06 1. 21E+06 1.76E+05 NO DATA 5.38E+05 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 NO DATA 1.97E+03 4. 33E+05 3.72E+04 ND-147 7.94E+03 8. 13E+03 5.00E+02 NO DATA 3.15E+03 3. 22E+05 3.12E+04 CLINTON -- UNIT #1 Rev.22 -

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TABLE 3.5-14 I' INHALATION PATHWAY (mrem/yr per FACTORS RCi/m 3

RIija

)

(CHILD)

I 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 P-32 2..60E+06 1.14E+05 9.8.7E+04 NO DATA NO DATA :NO DATA 4.21E+04 CR-51 NO DATA NO DATA 1.54E+02 8.54E+01 2.43E+01 .1.70E+04 1.08E+03 MN'-54 NO DATA 4.29E+04 9.51E+03 NO DATA 1.OOE+04 1!.58E+06 2.29E+04 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 C0758 NO DATA 1.77E+03 ,3.16E+03 NO DATA NO DATA '1.11E+06 3.44E+04 CO-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 ZN-65 4.26E+04' I..13E+05.. 7'.03E+04 NO DATA 7.14E+04. 9ý.95E+05 1.63E+04 RB-86 NO DATA 1.98E+05 1.14E+05 NO DATA NO DATA NO DATA 7.9.9E+03 SR-89 SR-90 Y-90 5.99E+05 1.01E+08 4.11E+03 NO DATA NO DATA NO DATA 1.72E+04 6.44E+06 1.11E+02

,NO DATA NO DATA

-NO DATA NO DATA.-

NO DATA 2.:16E+06 NO DATA , 1.,48E+07 2.62E+05 1.67E+05 3.43E+05 2.66E+05 I

Y-91 9.14E+05 NO DATA ,-2.44E+04, NO DATA NO DATA 2.63E+06 1.84E+05 ZR-95 1.90E+05. 4.18E+04 ,3:.70E+04' NO DATA 5.96,E+04 2.23E+06 6.11E+04 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 _-51.77E-02 NO DATA 5.07E-02 9.51E+02 4.81E+03 RU-103 2.79E+03 NO DATA ,1-.07E+03 NO DATA 7.035+03 6.62E+05 4.48E+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 TE-127m TE-129m 6.73E+03 2.'49E+04 1.92E+04 2.33E+03 8.55E+03 6.85E+03 9.14E+02 3.02E+03 3.04E+03 1.92E+03 6.07E+03 6.33E+03 NO DATA 6.36E+04 5.,03E+04 4.77E+05 1.48E+06 1.76E+06, 3.38E+04 7.14E+04 1.82E+05 I

.1-130 +. 8.18E+03 1.64E+04, 8.44E+03 1.85E+06 2.45E+04 NODATA 5.11E+03 1-131 4.81E+04 4;81E+04' 2.73E+04 .1.62E+07 7.88E+04 NO DATA 2.84E+03 1-132 2.12E+03- 4.07E+03 1.88E+03 1.94E+05 , 6.25E+03 -NO DATA 3.20E+03 I-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 NODATA 9ý.54E+02 4.92E+03 8.,73E+03 4.14E+03 7.92E+05, 1.34E+04 NO DATA 4.44E+03 1-135 CS-134 CS-136 6.51E+05-6.51E+04 1.01E+06 1'.71E+05 2.25E+05 1.16E+05

.NO DATA NO:DATA 3.30E+05 9.55E+04,"

.1.21E+05

• 1.45E+04 3.85E+03

.4.i8E+03

[

CS-137 9.70E+05 8.25E+05 1.28E+05 NO DATA 2;-82E+05, 1.,04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 NO DATA 2.11E+01 1.74E+06 1.02E+05 CE-141" 3.92E+04 1.95E+05 2.90E+03 NO DATA 8.55E÷03 5;'44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 NO DATA 1.17E+06 I,20E+07 3.89E+05 PP-143 1.85E+04 5.55E+03 9,.14E+02 NO DATA 3.00E+03 4.33E+05 :9.73E+04 ND-147 1..08E+04 8.73E+03 6.81E+02 NO DATA 4.81E+03 3.28E+05 .8.21E+04 I

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CY-CL-170-301 Revision 22 Page 117 of 195 TABLE 3.5-15 INHALATION PATHWAY FACTORS - Rijia ý(TEEN)

(mrem/yr per PCi/rm3 )

ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P-32 1.89E+06 1.1OE+05 7.16E+04 NO DATA' NO DATA 'NO DATA 9.28E+04 CR-51 NO DATA NO DATA 1.35E+02 7.50E+01' 3.07E+01 '2.10E+04 3.00E+03 MN-54 ' NO DATA 5.11E+04 8.40E+03 NO DATA ' 1'.27E+04 1.98E+06 6.68E+04 FE-55 3.34E+04' 2.38E+04 5.54E+03 NO DATA " NO DATA 1.24E+05 6.39E+03 FE-59 1.59E+04' 3.70E+04 1.43E+04 NO DATA' 'NO DATA 1.53E+06. 1.78E+05 CO-58 NO DATA 2.07E+03 2.78E+03 'NO DATA NO DATA 1.34E+06 9.52E+04 CO-60 NO DATA 1.51E+04 1.98E+04 NO DATA NO DATA 8.72E+06 '2.59E+05 NI-63 '5:80E+05 4.34E+04 1.98E+04 NO DATA 'NO DATA 3.07E+05 1.42E+04 ZN-65 3.786E+04: 1.34E+05 6.24E+04 NO DATA 8.64E+04 1.24E+06 '4.66E+04 RB-86 NO DATA 1.90E+05 *'8.40E+04 NO DATA-' NO DATA NO DATA '1.77E+04 SR-89 4.34E+05 NO DATA 1.25E+04 NO DATA NO DATA 2.42E+06 3.71E+05 SR-90 1.08E+08 "NO DATA 6.68E+06 NO DATA NO DATA 1.65E+07 7.65E+05 Y-90 2:.98E+03 'NO DATA 8.00E+01 NO DATA NO DATA 2.93E+05 5.59E+05 Y-91 6.'61E+05 NO DATA  !.77E+04-NO -DATA NO DATA 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04', NO DATA 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5. 66E+03 -NO! DATA' "1.00E+04 7.51E+05 9.68E+04 MO-99 NO DATA 1.69E+02 3.22E+012 .NQ DATA 4.11E+02 1.54E+05 .2.69E+05 TC-99m 1.38E-03 3.86E-03 '4.99E-02 NO DATA 5.76E-02 1.15E+03 6.13E+03 RU-I03 2.10E+03 NO DATA 8.96E+02 NO DATA 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 NO DATA 1.24E+04 NO DATA 1.90E+05 1.61E+07 9.60E+05 AG-II0m 1.38E+04' 1.31E+04 7. 99E+03' NO DATA 2.50E+04 6.75E+06, 2.73E+05

.. TE-125m, 4.88E+03 2.24E+03 6.67E+02 1.40E+03' NO DATA 5ý.36E+05 7.50E+04 TE-127m 1.80E+04. 8.16E+03' 2.18E+.03 4.38E+03 6.54E+04 1.66E+06. 1.59E+05 TE-'129m 1*39E+04 6.58E+03 2.25E+03' 4.58E+03- 5.19E+04 1.98E+06 4.05E+05 1-130 6.24E+03 1.78E+04 7.17E+03 1.49E+06-: 2.75E+04 NO DATA 9.12E+03 I-131 3:54E+04 ' 91E+/-04 2.64E+04 1.46E+07 8.40E+04 NO DATA 6.49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 ' 6.92E+03 NO DATA 1.27E+03

'1-133 1.22E+04 2:.05E+04 6.22E+03 2.92E+06 ' '3.59E+04 " NO DATA 1.03E+04

.1-134 8.88E+02 2.32E+03 .8.40E+02 3.95E+04' 3.66E+03, NO DATA 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 NO-DATA 6.95E+03 CS-134 5.02E+05 1.12E+06 5.49E+05 NO DATA 3.75E+05 1.46E+05 '9.76E+03 CS-136 5.15E+04ý 1.94E+05 1.37E+05 NO DATA 1.10E+05 1.78E+04 1.09E+04 CS-137 6.,70E+05 8.48E+05 3.11E+05 NO DATA 3.04E+05+ 1.21E+05 8.48E+03

.BA-140 5_47E+04 6.70E+01 3.52E+03 NO DATA .2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+041 .1.90Et04 2.17E+03 NO DATA 8.88E+03'* 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 ' 2.62E+05 NO DATA 1.21E+06 1.34E+07 8.64E+05 PR-143 1.34E+04 5.31E+03 .6.62E+02 NO DATA 3.09E+03 4.83E+05 2.14E+05

• ND-147 7.86E+03 8.56E+03 5.13E+02 "NO DATA 5.02E+03: 3.72E+05 1.82E+05 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 I

Revision 22 Page 118 of 195 I TABLE 3.5-16 U

INHALATION PATHWAY FACTORS - RIija (mrem/yr per gCi/m 3 )

(ADULT)

U ORGAN:

ISOTOPE H-3 BONE NO DATA LIVER

1. 26E+03 T.BODY

1. 26E+03 THYROID 1.26E+03 KIDNEY 1.26E+03 LUNG 1.26E+03 GI -LLI 1.26E+03 g

P-32 1. 32E+06 7. 71E+04 5. 01E+04 NO DATA NO DATA NO DATA 8.64E+04 CR-51 MN-54 FE-55 NO DATA NO DATA

2. 46E+04 NO DATA:

,3.'96E+04

1. 70E+04

1. OOE+02

6. 30E+03 3.94E+03

5. 95E+01 NO DATA NO DATA

2. 28E+01

9. 84E+03 NO DATA 1.44E+04 1.40E+06 7.21E+04 3 .32E+03

7. 74E+04

6. 03E+03 1

FE759 1. 18E+04 2.78E+04 1. 06E+04 NO DATA NO DATA I..02E+06 1. 88E+05 CO-58 CO-60 NI-63 NO DATA NO DATA 4.32E+05 1.58E+03 1.15E+04 3.14E+04

2. 07E+03 1.48E+04 1.45E+04 NO DATA NO DATA NO DATA NO DATA, NO DATA NO DATA 9.28E+05 5,97E+06:

1,.78E+05 1.06E+05 2.85E+05 1.34E+04 I

ZN-65 3.24E+04 1.03E055 4 .66E+04 NO DATA 6.90E+04 8ý.64E+05 5.34E+04 RB786 NO DATA 1.35E+05 15.90E+04 NO DATA NO DATA _NO DATA .1.66E+04 SR-89 3.04E+05 NO DATA 8.72E+03 NO DATA NO DATA 1.40E+06 3.50E+05 SR-90 9.92E+07 NO DATA: 6.1 0E+06 NO DATA, NO DATA- 9.6.0E+06 7.22E+05 Y-90 2.09E+03 NO DATA, 5.61E+01-ý NO DATA NO DATA I..70E+05 .5.06E+05 Y-91 4.62E+05 NO DATA . 1.24E+04- NO DATA:: NO DATA 1.70E+06 3.85E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 NO DATA 5.42E+.04 1.77E+06 1.50E+05 NB-95 1.41E+04 7.82E+03. 4.21E+03. NO DATA 7.74E+03, 5.05E+05 1.04E+05 NO DATA 1.21E+02- NO DATA :2:91E+02 9.12E+04 2.48E+05 O

MO-99 ,2.30E+01 TC-99m 1.03E-03 2.91E-03.. ,ý3.70E-02 NO DATA 4.42E-02 .7.64E+02 4.16E+03 RU-103 1.53E+03 NO DATAi .6.58E+02 NO DATA 5.83E+03 5.05E+05 1.10E+05 RU-106 6.91E+04 NO DATA 8.72E+03 NO DATA 1.34E+05 9.36E+06 9.12E+05 AG-IIrn TE-125m TE-127m 1.08E+04 3.42E+03 1.26E+04 1.00E+04_.

1.58E+03 5.77E+03 5.94E+03 4.67E+02 1.57E+03 NO DATA 1.05E+03 3.29E+03 1.97E+04 1.24E+04 4.58E+04 4.63E+06 3.14E+05 9.60E+05 3.02E+05 7.06E+04 1.50E+05 I

TE-129m 9. 76E+03 4.'67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1-130 4 58E+03 1. 34E÷04 5.28E+03 1. 14E+06 2.09E+04 NO DATA 7 69E+03 1-131 2 52E+04 3. 58E+04 2 .05E+04 1. 19E+07 6 13E+04 NO DATA .6.28E+03 1-132 1. 16E+03 3.26E+03 1. 16E+03 1. 14E+05 5. 18E+03 NO DATA 4 .06E+02 1-133 8 .64E+03 1.48E+04 4. 52E+03 2 . 15E+06 2 . 58E+04 NO DATA 8. 88E+03 1-134 1-135 CS-134

6. 44E+02 2 .68E+03

3. 73E+05 1.73E+03 6.98E+03

8. 48E+05

6. 15E+02

2. 57E+03 7.28E+05 2 .98E+04

4. 48E+05 NO DATA 2.75E+03 1.11E+04

2. 87E+05 NO DATA NO DATA 9.76E+04

1. 01E+00

5. 25E+03

.1.04E+04 I!

CS-136 3.90E+04 1.46E+05 1. 10E+05 NO DATA 8 ; 56E+04 1.20E+04* .117E+04 CS- 13 7 BA-140 CE-1141

4. 78E+05 3 . 90E+04

1. 99E+04

6. 21E+05 4.90E+01

1. 35E+04

4. 28E+05

2. 57E+03

1. 53E+03 NO DATA NO DATA NO' DATA.

.2.22E+05

1. 67E+01

6. 26E+03

7. 52E+04 1-.27E+06 3.62E+05 8.40E+03 2.18E+05

.1. 20E+05 II CE-144 3.43E$06 1.43E+06 1. 84E+05 NO DATA 8. 48E+05 7..78E+06 8.16E+05 PR-143 ND-147

9. 36E+03 5.27E+03

3. 75E+03 6.10E+03 4.64E+02

-3.65E+02 NO DATA NO DATA 2 16E+03 2. 81E+05 3 ý 56E+03 :2. 21E+05 2.00E+05

1. 73E+05 II II II II CLINTON -- UNIT #1 12/09 Rev.22 -

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CY-CL-170-301 Revision 22 Page 119 of 195 TABLE 3.5-17

.COW MILK PATHWAY FACTORS - RCija (INFANT) 2 (m rem/yr per JICi/sec)

ORGAN: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 2.38E+03* 2.38E+03* 2.38E+03"* -2.38E+03* 2.38E+03* 2.38E+03*

P-32 1.60E+11 9.41E+09 6.20E+09 NO DATA NO DATA NO DATA 2.16E+09 CR-51 .NO DATA NO DATA 1.61E+05 1.05E+051 2.29E+04 2.04E+05 4.69E+06 MN NO DATA 3.90E+07 8.84E+06 NO DATA 8.64E+06 NO DATA 1.43E+07 FE-55; 1.35E+08 8.72E+07 2.33E+07 NO DATA NO DATA 4.26E+07 1.11E+07 FE-59 2..25E+08 3.92E+08 1.55E+08 NO DATA -NO DATA 1.16E+08 1.87E+08

• CO-58 .NO'DATA 2.43E+07 6.06E+07 NO DATA. NO DATA NO DATA 6.05E+07 CO-60 NO DATA 8.82E+07 2.08E+08 NO DATA NO DATA NO DATA 2.10E+08 NI-63 3.50E+I0 2.16E+09- 1.21E+09 NO DATA: NO DATA. NO DATA 1.08E+08 ZN-65 5.55E+09 1.91E+10 8.78E+09 NO DATA 9.23E+09 NO DATA 1.61E+10 RB-86 NO DATA' 2.23E+10 1.10E+10 NO DATA NO DATA NO DATA 5.70E+08 SR-89 1.26E+10 NO DATA 3.61E÷08 NO DATA NO DATA NO DATA 2.59E+08 SR-90 1.22E+11, NO DATA ,3.10E+10 NO DATA NO DATA NO DATA 1.52E+09 Y-90 6.83E+02 NO DATA. 1.83E+01 NO DATA NO DATA NO DATA 9.43E+05 Y-91 7.33E+04 NO DATA 1.95E+03 NQ DATA NO DATA NO DATA 5.26E+06 ZR-95 6.82E+03 1.66E+03 .. l.18E+03 NO DATA 1.79E+03 NO DATA 8.28E+05 NB-95 5.93E+05 2.44E+05 1.41E+05: NO DATA 1.75E+05 NO DATA 2.06E+08 MO-99 NO DATA 2.07E+08 4.04E++/-7: -NO DATA 3.10E+08 NO DATA, 6.83E+07 TC-99m 2.75E+01 5.66E+01 7.29E+02 'NO DATA 6.09E+02 2.96E+01 1.64E+04

• RU-103 8.67E+03 NO DATA. 2.92E+03 NO DATA 1.81E+04 NO DATA- 1.06E+05 RU-106 1.91E+05 NO DATA 2.38E+04 NO DATA 2.26E+05 NO DATA 1.45E+06 AG-II0m 3.85E+08 2.81E+08 1.86E+08 NO DATA' 4.02E+08 NO DATA 1.46E+10 TE-125m 1.51E+08 5.05E+07 2.04E+07 5.08E+07 NO DATA NO DATA 7.19E+07 TE-127m 4.22E+08 1.40E+08 5.10E+07 1.22Ei08 1.04E+09 NO DATA' 1.70E+08 TE-129m 5.56E+08 1.91E+08 8.56E+07 2.14E+08 1.39E+09 NO DATA 3.32E+08 1-130 3.53E+06 7.76E+06 3.12E+06 8.70E+08 8.53E+06 NO DATA 1.66E+06 1-131 2.71E+09 3.19E+09 1.40E+09 1.05E+12' 3.73E+09 NO DATA 1.14E+08 1-132 1.43E+00 2.90E+00 1.03E+00 1.36E+02 3.24E+00 'NO DATA 2.35E+00 1-133 3.63E+07 5.28E+07 1.55E+07 9.60E+09 6.21E+07 NO DATA 8.93E+06 1-134 1.64E-11 3.36E-11 1.20E-11 7.86E-10`ý 3.76E-II NO DATA 3.48E-11 1-135 1.13E+05 2.24E+05 8.18E+04 2.01E+07 2.50E+05 NO DATA 8.12E+04 CS-134 3.65E+10 6.81E+10 6.88E+09 NO DATA 1.75E+10 7.19E+09 1.85E+08 CS-136 1.97E+09 5.81E+09 2.17E+09 NO DATA 2,31E+09 4.73E+08 8.82E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 NO DATA 1.62E+10 6.44E+09 1.89E+08 BA-140 .2.45E+08 2.45E+05 1.26E+07 NO DATA 5.72E+04 1.50E+05 5.92E+07 CE-141 4.34E+04 2.65E+04 3.12E+03 NO DATA 8.17E÷03 NO DATA 1.37E+07 CE-144 2.34E+06 9.56E+05 1.31E+05 NO DATA 3.87E+05 NO DATA 1.34E+08 PR-143 .1.49E+03 5.56E+02 7.37E+01 NO DATA 2.07E+02 NO DATA 7.85E+05 ND-147 8.79E+02 9.03E+02 5.53E+01 NO DATA 3.48E+02 NO DATA 5.72E+05

• mrem/yr per gCi/m3 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 120 of 195 I

TABLE 3.5-18 II COW MILK PATHWAY FACTORS - RCija (CHILD)

(m2mrem/yr per gCi/sec)

ORGAN:

ISOTOPE H-3 BONE NO DATA LIVER 1.57E+03*

T.BODY 1.57E+03*

THYROID 1.57E+03*

KIDNEY 1.57E+03,*

LUNG 1.57E+03*

GI-LLI 1.57E+03*

I P-32 7.79E+10 3.64E+09 3.OOE+09 NO DATA NO DATA NO DATA 2.15E+09 CR-51 NO DATA NO DATA+ 1.01E+05 5.63E+04 1.54E+04 1,.03E+05 5.38E+06 MN-54 NO DATA 2.10E+07 5.59E+06 NO DATA 5.88E+06 NO DATA 1. 76E+07 FE-55 1.12E+08 5,94E+07 1.84E+07 NO DATA NO DATA .3.36E+07 1.10E+07 FE-59 1.20E+08 1.95E+08 9.71E+07 NO DATA NO DATA 5.65E+07 -2.03E+08 CO-58 NO DATA 1.21E+07 3.7IE+07 NO DATA NO DATA .NO DATA 7.08E+07 CO-60 NO DATA 4.32E+07 1.27E+08 NO DATA NO DATA. .NO-DATA: 2.39E+08 NI-63 2.97E+10 1.59E+09 1.01E+09 NO DATA NO DATA NO DATA 1.07E+08 ZN-65 4.13E+09 1.10E+10,:. 6.83E+09 NO DATA 6.92E+09 -NO DATA 1.93E+09 RB-86 NO DATA 8.78E+09. 5.40E+09 NO DATA NO DATA NO' DATA 5.65E+08 SR-89 6.63E+09 NO, DATA 1.89E+08 NO DATA NO DATA. NO DATA 2.57E+08 SR-90 1.12E+11 NO DATA :2.84E+10 .NO DATA NO DATA . NO DATA 1.51E+09 Y-90 3.23E+02 NO DATA 8.65E+00 NO DATA' NO DATA, NO DATA 9.20E+05 Y-91 3.90E+04 NO DATA 1..04E+03. NO DATA NO DATA NO' DATA 5.20E+06 ZR-95 3.84E+03 8.44E+02: 7.51E+02 NO DATA 1.21E+03 NO DATA 8.80E+05 NB-95 3.18E+05 ý1.24E+05 8.84E+04. NO DATA 1.16E+05 NO DATA 2.29E+08 MO-99 NO DATA 8.15E+07 2.02E+07, NO DATA 1.74E+08 NO DATA 6.74E+07

'TC-99m 1.32E+01 2.58E+01 .4,'28E+02 NO DATA 3.75E+02 1.31E+01 1.47E+04 RU-103 4.29E+03 NO DATA 1.65E+03 NO DATA 1.08E+04 NO DATA .1.11E+05 RU-106, 9.25E+04 NO DATA ,1.15E+04 NO DATA 1.25E+05 NO. DATA 1.44E+06 AG-II0m 2.09E+08 1.41E+08 '1.13E+08 NO DATA. 2.63E+08 NO DATA. 1.68E+10 TE-125m 7.39E+07 2.OOE+07 . 9.85E+07 2.07E+07 NO DATA NO DATA -7.13E+07 TE-127m 2.08E+08 5. 61E+07 ,. 2.47E+07. 4.98E+07 5.94E+08 NO DATA 1.69E+08 TE-129m .2.71E+08 7..58E+077; 4.21E+07 8.74E+07 7.97E+08 NO DATA 3.31E+08 1-130 1.72E+06 3.47E+06 1.79E+06 3.82E+08 5.19E+06 NO DATA 1.62E+06 1-131 1.30E+09 1,.31E+09 7.44E+08 4.33E+II1 2-.15E+09 NO DATA 1.17E+08 1-132 6.91E-01 "1:27E+00 5.84E-01 5.89E+01 1.94E+00 NO DATA 1.49E+00 1,-133 1.72E+07 2.12E+07 8.03E+06 3.94E+09 3.54E+07 NO DATA, 8.56E+06 1-134 7.92E-12 ,1.47E-11 6.77E-12 3.38E-10 2.25E-11 NO.DATA 9.75E712 1-135 5.43E+04 9.77E+04 4.62E+04 8.56E+06 1.50E+05 NO DATA 7.44E+04 CS-134 2.27E+10 . 3.72E+10 7.85E+09 NO DATA 1.15E+10 4.14E+09 i2.01E+08 CS-136 1.01E+09 2.78E+09 1.80E+09 NO DATA 1.48E+09 2.21E+08 9.76E+07 CS-13.7 3.23E+10 3:.09E+10 4.56E+09,. NO DATA 1.01E+10 3.63E+09 1'.94E+08 BA-140 1.18E+08 1.03E+05- 6.84E+06 NO. DATA 3.3.7E+04 6.12E+04: 5.94E+07 CE-141 CE-144 2.19E+04 1.63E+06 1.09E+04 5.10E+05 1.62E+03 8.68E+04 NO DATA NO DATA..

4.78E+03 2.82E+05 NO DATA .

NO DATA 1.36E+07 1.33E+08 I

PR-143 ND-147 7.19E+02 4.44E+02 2.16E+02 3.59E+02 3.57E+01 2.78E+01.

NO DATA NO DATA 1.17E+02 1;97E+02 NO DATA NO DATA 7.76E+05 5.69E+05 3

• mrem/yr per gCi/m3 I

II CLINTON -- UNIT #1 12/09 Rev.22 -

I

CY-CL-170-301 Revision 22 Page 121 of 195 TABLE 3.5-19

.COW MILK PATHWAY FACTORS -RCija (TEEN)*a (m2mrem/yr per RCi)

ORGAN: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 -NO DATA 9.92E+02* 9.92E+02* 9.92E+02" 9.92E+02* 9.92E+02* 9.92E+02*

P-32 3.15E+10 1.95E+09 1.22E+09 NO DATA' NO DATA NO DATA 2.64E+09 CR-51 NO DATA NO DATA 5.OOE+04 2.78E+04 1.10E+04 7.14E+04 8.41E+06 MN-54 NO DATA 1.40E+07 2.78E+06 NO DATA 4.19E+06 NO DATA 2.88E+07 FE-55 4.46E+07 3.16E+07 7.38E+06 NO DATA. NO DATA 2.01E+07 1.37E+07 FE-59' 5.18E+07 1.21E+08 *4.67E+07 NO DATA NO DATA 3.81E+07 2.68E+08 CO-58 NO DATA 7.98E+06 1.84E+07 NO DATA 'NO DATA NO DATA 1.10E+08 CO-60 NO DATAý 2.78E+07 6.26E+07 NO DATA NO DATA NO DATA 3.62E+08 NI'63 l..1I8E+10 8.34E+08 4.00E+08 NO DATA NO DATA NO DATA 1.33E+08 ZN-65 2.11E+09 7.32E+09 3.41E+09 NO DATA 4.68E+09 NO DATA .3.10E+09 RB-86 -NO DATA 4.74E+09. 2.23E+09 NODATA NO DATA NO DATA 7.01E+08 SR-89 2'.'68E+09- NO DATA 7.67E+07 NO DATA NO DATA NO DATA 3.19E+08 SR-90 6.62E+10 NO DATA .1.64E+10 NO DATA NO 'DATA NO DATA 1.86E+09 Y-90 1.31E+02 NO',DATA 3.53E+00 ' NO:DATA NO DATA NO DATA 1.08E+06 Y-91 1.58E+04 NO DATA '4.24E+02 NO DATA

• NO DATA NO DATA 6.48E+06 ZR-95 1.65E+03 5.20E+02' -3:58E+02 NO DATA 7.65E+02 NO DATA 'i.20E+06 NB-95 1.41E+05 7.81E+04 4.30E+04 NO bATA 7.57E+04 NO DATA 3.34E+08 MO-99 NO-DATA 4.46E+07,' 8;50E+06 !NO bATA 1.02E+08 NO DATA 7.98E+07 TC-99m 5.74E+00 1.60E+01- 2.08E+02 NO DATA 2.39E+02 8.89E+00 1.05E+04

'RU-103. 1.81E+03 NO DATA .7.73E+02 NO DATA 6.37E+03 NO DATA 1.51E+05 RU-106 3.75E+04. NO DATA 4.73E+03 NO DATA 7.23E+04 NO DATA 1.80E+06 AG-II0m 9.ý64E+07 9.12E+07 5.55E+07 NO DATA' 1.74E+081 NO DATA 2.56E+10 TE-125m' 3.01E+07 1.;08E+07 4.02E+06 8.41E+06 NO DATA NO DATA 8.88E+07 TE-127m 8.43E+07 2.99E+07 1.00E+07 2.01E+07' 3.42E+08' NO DATA 2.10E+08 TE-129m , 1..10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 NO DATA 4.14E+08 1-130 7.33E+05 .2.12E+06 8.47E+05 1.73E+08 3.27E+06 NO DATA 1.63E+06 1-131 5.36E+08 7.50E+08 4.03E+08' 2.19E+11- 1.29E+09 NO DATA 1.48E+08 1-132 :2.90E-01 7.59E-01 2.72E-01 2.56E+01 1.20E+00 NO DATA 3.31E-01 1-133 7.06E+06 1.20E+07 3.65E+06 1.67E+09 2.10E+07 NO DATA 9.06E+06 1-134 3.34E-12 -8.86E-12 3. 18E-12 1.48E-10 1i.40E-11 NO DATA ' 1.17E-13 1-135 2.29E+04 5.90E+04' ' 2.19E+04 3.80E+06 9.32E+04 NO DATA ' 6.54E+04 CS-134 9.79E+09 2.30E+10- 1.07E+10 NO DATA 7.32E+09 2.80E+09 2-.87E+08 CS-136 4.48E+08 1.76E+09 1.18E+09 ýNO DATA 9.59E+08 1.51E+08 i.42E+08 CS-137. 1.33E+10 1.77E+10 6.18E+09 NO DATA 6.03E+09 2.34E+09 ' 2.52E+08 BA-140 4.85E+07 5.95E+04 3.13E+06 NO DATA 2.02E+04 4.OOE+04 7.49E+07 CE-141 8.88E+03 5.93E+03 6.81E+02' NO DATA 2.79E+03- NO DATA 1.70E+07 CE-144 6.61E+05 2.73E+05 3.55E+04 NO DATA 1.63E+05 NO DATA 1.66E+08 PR-143 2.,91E+02 '1.16E+02.. 1.45E+01 NO DATA 6.75E+01 NO, DATAý 9.57E+05 ND-147 1.81E+02 1.97E+02 1.18E+01 NO DATA 1.16E+02 NO DATA 7.10E+05

• mrem/yr per RCi/m3 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 U

Revision 22 Page 122 of 195 TABLE 3.5.-20 I COW MILK PATHWAY FACTORS.- RCija (ADULT)

(m 2mrem/yr per liCi/sec)

ORGAN: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 7.62E+02* 7.62E+02* 7.62E+02* 7.62E+02* "7.62E+02* 7.62E+02*

P-32 1.71E+10 I.06E+Q9 6.61E+08 NO DATA NO DATA NODATA 1.92E+09 CR-51 NO DATA NO DATA, 2.85E+04 .1.70E+04 I

.6.27E+03 3.,78E+04 7.16E+06 MN-54 NO DATA ,8.41E+06 1.60E+06 NO DATA 2.50E+06 NO.DATA 2.58E+07 FE-55 2.51E+07 1.73E+07' 4.04E+06 NO DATA NO DATA 9.68E+06 9.95E+06 FE-59 2.97E+07 6.99E+03 2.68E+07 NO DATA NO DATA 1.95E+07 2.33E+08 CO-58 NO DATA 4.72E-06 1.06E+07 NO DATA NO DATA  ::NOIDATA 9.57E+07 CO-60 NO DATA 1,.64E+07 .3.62E+07 NO DATA NO DATA .. NODATA 3.08E+08 NI-63 6.73E+09 4.67E+018 2.26E+08 NO DATA NO DATA NO.DATA 9.74E+07 ZN-65 1.37E+09 4.37E+09, 1.98E+09 NO DATA 2.93E+09 'NO DATA 2.755+09 RB-86 NO DATA 2.60E+09 1.21E+09 NO DATA 'NO DATA NO DATA 5.12E+08 SR-89 1.45E+09 NO DATA ,. 4.16E+07 NO DATA NO DATA ', NO DATA 2.33E+08 SR-90 4.68E+10 NO DATA', 1.15E+10 NO DATA .,NO DATA NO DATA 1.35E+09 Y-90 7.10E+01 NO DATA I1.90E+00 NO:DATA: 'NO DATA NO DATA 7.53E+05 Y-91 8.60E+03 NO.DATA. 2.30E+02, NO.DATA NO DATA NO DATA 4.73E+06 ZR-95 9.45E+02 3.03E+02 2.05E+02 .NOr.DATA 4.76E+02 NO DATA 9.61E+05 NB-95 8.25E+04 4.59E+04 '2,.47E+04 NO DATA 4.54E+04 NO DATA 2.79E+08 MO-99 NO DATA 2.48E+07 '. 4.72E+06. NO DATA 5.61E+07 NO DATA 5.74E+07 TC-99m 3.31E+00 9.35E+00 1.19E+02 NO DATA 1.42E+02 4.58E+00 5.53E+03 RU-103 1.02E+03 NO DATA 4.39E+02 NO DATA 3.89E+03 NO DATA 1.19E+05 RU-106 2.04E+04 NO DATA ,. 2.58E+03 "NO DATA 3.94E+0.4 NO DATA 1.32E+06 AG-II0m 5.82E+07 5.39E+07 3.20E+07 NO DATA 1.06E+08 NO DATA 2.20E+10 TE-125m 1.63E+07 5.91E+06 2.19E+06 4.91E+06 6.64E+07 NO DATA 6'.52E+07 TE-127m 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 NO DATA 1.53E+08 TE-129m 6.01E+07 2.24E+07 9.52E+06 2.07E+07 2.51E+08 NO DATA 3;03E+08 1-130 4.16E+05 1.23E+06 4.84E+05 1.04E+08 1.91E+06 NO DATA .1.06E+06 1-131 1-132 1-133 2.97E+08 1.65E-01 3.86E+06 4.24E+08 4.40E-01 6.72E+06 2.43E+08 1.54E-01 2.05E+06

- 1.39E+11 1.54E+01 9.87E+08

.7.27E+08 7.02E-01 1.17E+07 NO NO NO DATA DATA DATA 1.12E+08 8.27E-02 6.'04E+06 I

1-134 1.89E-12 5.13E-12 1.83E-12 8.88E-11 !8:15E-12 NO DATA 4.47E-15 1-135 CS-134 CS-136 1.29E+04 5.67E+09 2.64E+08 3.39E+04 1.35E+10 1.04E+09 1.25E+04 1.10E+10 7.49E+08.

2.23E+06 NO DATA NO DATA 5.43E+04.

4.37E+09 5.79E+08 NO DATA 1.45E+09 7.94E+07 3.83E+04 2'.36E+08 1.18E+08 i

CS-137 .7.39E+09', 1.01E+10 6.62E+09ý NO DATA 343E+09

3. 1-14E+09 1.96E+08 BA-140 2. 72E+07, 3.42E+04 1.78E-06 NO DATA 1.16E+04 1.96E+04- 5.60E+07 CE-141 CE-144 4.84E+03 3.58E+05 3.27E+03 1.50E+05 3.71E+02 ..

1.92E+04 NO NO DATA DATA 1.52E+03*

8.87E+04 NO DATA NO DATA 1,.25E+07 1.21E+08 I

PR-143 1.58E+02 6.35E+01 7.84E+00 NO DATA 3.66E+01 NO DATA 6.93E+05 ND-147 , 9.44E+01 1.09E+02 6.53E+00 NO DATA 6.38E+01 NO DATA 5.24E+05

• mrem/yr per ý,Ci/m3 I

I CLINTON -- UNIT #1 Rev.22 -

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U CY-CL-170-301 Revision 22 Page 123 of 195 I TABLE 3.5-21 GOAT MILK PATHWAY FACTORS - RCija' (INFANT)

(m 2mrem/yr per ýtCi/sec)

ORGAN: :BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 .NO DATA 4.86E+03* 4.86E+03* 4.86E+03* -4.86E+03* 4.86E+03* 4.86E+03*

P-32 1.90E+II 1.12E+10 7.46E+09 NO DATA NO DATA NO DATA 2.58E+09 CR-51 NO DATA NO DATA 1.93E+04 1.26E+04 2.75E+03 2.45E+04 5.63E+05 MN-54 NO DATA 4.68E+06 1.06E+06 NO DATA .1.04E+06 NO DATA 1.72E+06 FE-55 :1-.75E+06 1.13E+06 3.02E+05 NO DATA NO DATA- 5.53E+05 1.44E+05 FE-59ý'. 2.91E+06 5.08E+06 2.OOE+06 NO DATA NO DATA 1.50E+06 2.43E+06 CO-58 NO DATA .2.90E+06 7.24E+06 NO DATA NO DATA NO DATA 7.23E+06 CO-60 **.NO.'DATA 1.06E+07 2.49E+07 NO DATA' NO DATA NO DATA 2.51E+07 NI-63 4.19E+09, 2.59E+08 1.45E+08 NO DATA* NO DATA NO DATA 1.29E+07 ZN-65 6.ý64E+08 2.28E+09 1.05E+09 NO DATA 1.10E+09 NO DATA 1.92E+09 RB-86 NO DATA .2.65E+09 1.31E+09 NO DATA NO DATA NO DATA 6.79E+07 SR-89 ,2:6E+0 'NO DATA 7.56E+08 NO DATA NO DATA NO DATA 5.42E+08 SR-90 2.55E+11, NO DATA 6.50E+10 NO DATA, NO DATA NO DATA ' 3.19E+09 Y--90 8.19E+01' "'NO DATA 2.19E+00 NO: DATA' NO DATA NO DATA 1.13E+05 Y-91 8.78E+03- NO DATA 2.;34E+02 NO DATA' NO DATA NO DATA ,6.29E+05 ZR-95 8.16E+02 :1.99E+02 1.41E+02 NODATA 2.14E+02 NO DATA 9.90E+04 NB-95 7.12E+04 2.93E+04 1.:69E+04 NO, DATA 2.10E+04 NO DATA. 2.47E+07 MO-99 NO DATA 2.48E+07 4.84E+06 NO DATA 3.71E+07 NO DATA ý8.18E+06 TC-99m 3.26E+0.0 ' 6.73E+00 8.67E+01 NO DATA1 7.24E+01 3.52E+00 1.96E+03 RU-103 1.04E+03 NO DATA 3.47E+02 NO'DATA 2.16E+03 NO DATA 1.26E+04 RU-106 2.28E+04 NO DATA 2.84E+03 .NO DATA' 2.69E+04 NO DATA. 1.73E+05

.AG-110m. 4.62E+07 3.37E+07 2.23E+07 NO DATA 4.83E+07 NO DATA '1.75E+09

.TE-125m 1.80E+07 6:.02E+06 2.43E+06 6.06E+06 NO DATA NO DATA 8.58E+06 TE-127m 5.04E+07 1.67E+07 6.10E+06 1.46E+07 1.24E+08 NO DATA 2.03E+07 TE-129m. 6.68E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 NO DATA 3.99E+07 J-130 4.22E+06 9.28E+06 3.73E+06 1.04E+09- 1.02E+07 NO DATA 1.99E+06 1-131 3.25E+09 3.83E+09 1.69E+09 1.26E+12 4..48E+09 NO DATA ,1.37E+08 1-132 1.73E+00 3.50E+00 1.25E+00 1.64E+02 " 3.91E+'00 NO DATA 2.84E+00 1-133 4.34E+07 6.32E+07 1.85E+07 1.15E+10 7.43E+07 NO DATA 1.07E+07 1-134 1.97E-11 4.04E-11 1.44E-11 9.42E-10 ,4,52E-11 NO DATA 4.18E-11 1-135 1.36E+05 2.70E+05 9.85E+04 2.42E+07 3.01E+05 NO DATA 9.77E+04

CS-134 1.09E+11. 2.04E+II 2.06E+10 NO DATA 5.25E+10 2.15E+10 5.54E+08 CS-136&' 5.92E+09. 1.74E+10 6.50E+09 NO DATA 6.94Et09 1.42E+09, 2.64E+08 CS-137 1.54E+11 I1.80E+11 1.28E+10 NO DATA -4.84E+10 1.96E+10 -5.63E+08 BA-140 2.87E+07' 2.87E+04 1.48E+06 NO DATA 6.82E+b3: 1.76E+04 7.06E+06 CE-141 5.20E+03: 3.17E+03 3.73E+02 'NODATA 9.78E+O.2 NO DATA '1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 NO DATA 4.61E+04 NO DATA 1.60E+07 PR-143 1.78E+02 ý6.66E+01 8.83E+00 NO DATA 2.47E+01 -NO DATA 9.40E+04 ND-147 1.06E+02 1.08E+02 6.65E+00 NO DATA 4.18E+01 NO DATA 6.88E+04

• mrem/yr per g[Ci/m3 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 I

Revision 22 Page 124 of 195 I

TABLE 3.5-22 U GOAT/MILK PATHWAY FACTORS - RCija (m2 mrem/yr per gCi/sec)

(CHILD-)

I ORGAN: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 3.20E403* 3.20E+03* 3.20E+03* 3.20E+03* 3.20E+03* 3.20E+03*

P-32 9.32E+10 4.36E+09 3.59E+09 NO DATA NO DATA NO DATA 2.58E+09 CR-51 NO DATA ýNO DATA 1.22E+04 6.77E+03 1.85E+03 1.24E+04 6.47E+05 MN-54 NO DATA 2.515+06 6.70E+05 NO'DATA 7.05E+05 NO DATA 2.11E+06 FE-55 1.45E+06 7.65E+05 2.38E+05 NO DATA NO DATA . 4.35E+05 1.42E+05 FE-59 1.55E+06 2.52E+06 1.25E+06 NO DATA NO DATA :7.29E+05 2.62E+06 CO-58 NO DATA 1'.46E+06 4.46E+06 NO DATA NO DATA NO DATA 8.49E+06 CO-60 NO DATA 5.16E+06,- 1.52E+07 NO DATA NO DATA NO DATA .2.86E+07 NI-63 3.55E+09 1.90E+08 1.21E+08 NO DATA NO DATA NO DATA 1.28E+07

• ZN-65 4.96E+08 1.32E+09 8.22E+08 NO DATA 8.33E+08 NO DATA 2.32E+08 RB-86 NO DATA 1.05E+09 6.47E+06 - NO DATA , NO DATA NO DATA 6.77E+07 SR-89 1.39E+10 NO DATA 3.96E+08 NO DATA ýNO DATA NO DATA 5.37E+08 SR-90 2.35E+11 NO DATA' -5.95E+10 NO DATA NO DATA -NO DATA 3.16E+09 Y-90 3.86E+01 NO DATA 1.03E+00 NO DATA NO DATA NO DATA 1.10E+05 Y-91 4.67E+03 NO DATA 1.I.25E+02 , NO DATA NO DATA NO DATA 6.22E+05 ZR`95 4.58E+02 1.01E+02"", 8.97E+01 NO DATA 1.44E+02 NO DATA 1.05E+05 NB-95 3.81E+041 1.48E+04 .l.06E+04 NO DATA 1.39E+04 NO DATA 2.75E+07 MO-99 NO DATA 9.74E+06 2.41E+06 NO DATA. 2.08E+07 NO DATA 8.05E+06 TC--99m 1.58E+00 3.10E+00 :5?13E+/-O1 NO DATA 4.50E+01 1.57E+00 1.76E+03 RU-103 5.10E+02 NO DATA 1.96E+02 NO DATA 1.28E+03 NO DATA 1.32E+04 RU-106 1.11E+04 NO DATA 1.38E+03 NO DATA 1.49E+04 NO DATA 1.72E+05 AG-II0m 2.50E+07, 1.69E+07. 1.35E+07 NO DATA 3.15E+07 NO DATA 2.01E+09 TE-125m 8.84E+06 :2.39E+06. 1.18E+06. 2.48E+06 NO DATA NO DATA 8.53E+06 TE-127m 2.49E+07 6.71E+06- 2.96E+06 5.96E+06 7.10E+07 NO DATA .2'.02E+07

'TE-129m 3.24E+07 9.06E+06 5.03E+06: 1.05E+07 9.52E+07 NO DATA 3.96E+07 1-130 2.06E+06 4.17E+06 2.15E+06 4.59E+08 6.23E+06 ,NO DATA 1.95E+06 1-131 1.56E+09 1.57E+09 8.94E+08 5.20E+11. 2.58E+09 NO DATA 1.40E+08 1-132 8.32E-01 1.52E+00 7.03E-01 7.09E+01 2.34E+00 NO DATA 1.80E+00 1-133 2.06E+07 2;55E+07 9.64E+06 4.73E+09 4.25E+07 NO DATA .1.03E+07 I--134 9.51E-12' 1.77E-11 8.13E-12 4.06E-10 2.,70E-11 NO DATA 1.17E-11 1-135 6.53E+04 1.17E+05 5.56E+04 1.04E+07. 1.80E+05 NO DATA 8.95E+04 CS134 6.76E+10: 1;IIE+II 2.34E+10 NO DATA 3-.44E+10 .1. 23E+10 5.98E+08 CS-136 3.03E+09: 8.33E+09 5.39E+09 NO DATA 4.44E+09 6.62E+08 2.93E+08 CS-137 9.65E+10 9.23E+10 1,.36E+10 NO DATA 3.01E+10 J.I08E+10. 5.78E+08 BA-140 CE-141 CE-144 1.40E+07 2.62E+/-03 1.94E+05 1.22E+04 1.31E+03 6.10E+04 8.15E+05 1.94E+02 1.04E+04 NO NO NO DATA DATA DATA 3.98E+03

5.73E+02 3.38E+04 7.29E+03 NO DATA NO DATA 7.07E+06 1.63E+06 1.59E+07 I

PR-143 8.61E+01, 2.58E+01 4.27E+00. NO DATA 1.40E+01 NO DATA 9.29E+04 ND-147 5.33E+01 4.32E+01 3.34E+00 NO DATA 2.37E+01. NO DATA 6.84E+04 3

• mrem/yr per gCi/m I

I I

CLINTON -- UNIT #1 12/09

• Rev.22 -

I

CY-CL-170-301 Revision 22 Page 125 of 195 TABLE 3.5-23 GOAT MILK PATHWAY FACTORS - RCija (TEEN')

(m2 mrem/yr per 4Ci)

ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 2 2.02E+03* 2.02E+'03* 2.02E+03* 2.02E+03* 2.02E+03* 2.02E+03*

P-32 3.78E+10 2.34E+09 1.47E+09 NO DATA NO DATA 'NO DATA "3.18E+09 CR-51 'NO-DATA NO DATA 5.94E+03 3.30E+031"/ 1.30E+03 8.48E+03 9.98E+05 MN-54 'NO DATA 1.68E+06 3.32E+05 NO DATA 5.00E+05 NO DATA 3.44E+06 FE-55 '5.79E+05 4.11E+05 9.57E+04 NO DATA NO DATA 2.60E+05 1.78E+05 FE-59 -6.75E+05 1.58E+06 6.08E+05 NO DATA ' NO DATA 4.97E+05 3.73E+06 CO-58 NODATA 9.51E+05 2.19E+06 NO DATA NO DATA NO DATA 1.31E+07 CO-60 ' NO DATA 3.32E+06 7.47E+06 NO DATA NO DATA NO DATA 4.32E+07 NI-63 1.42E+09 .I0E+08 4.81E+07 NO DATA . NO DATA NO DATA 1.60E+07 ZN-65 , 2.52E+08 8.76E+08 4.09E+08 NO DATA 5.61E+08 NO DATA 3.71E+08 RB-86 NO DATA - '5.66E+08 2.66E+08 NO DATA NO DATA NO DATA 8.38E+07 SR-89 5.59E+09 NO DATA 1.60E+08 NO DATA,'. NO DATA NO DATA 6.65E+08 SR-90 1.38E+11 NO 'DATA 3.40E+10 NO DATA " NO DATA NO DATA 3.87E+09 Y-90 1.56E+01 NO DATA - 4.21E-01 NO DATA NO DATA NO DATA 1.29E+05 Y-91 1.89E+03 NO DATA '5.07E+/-01 NO DATA NO DATA NO DATA 7.75E+05 ZR-95 1.98E+02 '6.24E+01 ý4.29E+01 NO *DATA ' 9.17E+01 NO DATA 1'.44E+05 NB-95 1.69E+04 9.37E+03 5.16E+03 NO DATA 9.08E+03 NO DATA 4.01E+07 MO-99 NO DATA 5.33E+06 1.02E+06 NQ 'DATA' 1.22E+07 NO DATA 9-55E+06 TC-99m 6.87E-01 1.92E+00 12.48E+01 NO 'DATA " 2.86E+01 1.06E+00 1.26E+03 RU-103 2.17E+02 NO DATA 9.27E+01 '.NO DATA 7.64E+02 NO DATA 1.81E+04 RU-106 4.47E+03 NODATA 5..63E+02 NO DATA , 8.62E+03 NO DATA 2.14E+05 AG-II0m 1.15E+07 1.09E+07 6.62E+06 'NO DATA 2.08E+07 NO DATA 3.06E+09 TE-125m 3.59E+06 1.29E+06 4.80E+05 1.OOE+06 NO DATA NO DATA 1.06E+07 TE-127m 1.01E+07 3.57E+06 1.20E+06 2.39E+06 _4.08E+07 NO DATA _2.51E+07

,TE-129m 1. 32E+07 4.89E+06 2 .08E+06 4.25E+06 5.51E+07 NO DATA 4.94E+07 1-130 8.82E+05 2. 55E+06 1.02E+06 2 .08E+08 3. 93E+06 NO DATA 1. 96E+06 1-131 6 .44E+08 9. 01E+08 4 .84E+08 2+.63E+11 1. 55E+09 NO DATA '1.78E+08 1-132 '3. 52E-01' 9.20E-01 3.30E-01 3.10E+01 1.45E+00 NO DATA 4.01E-01 1-133 8.48E+06 1.44E+07 4.39E+06 2.01E+09 2:52E+07 NO DATA 1.09E+07 1-134 4.03E-12 1.07E-11 3 .84E-12 1.78E-10 1. 68E-7I NO DATA 1.41E-13 1-135 2. 75E+04 7. 08E+04 2 .62E+04 4.56E+06 1.12E+05 NO DATA 7.85E+04 CS-134 2 .94E+10 6:91E+10 3 .21E+10 NO DATA 2.20E+10 8.39E+09 8.60E+08 CS-136 '1.34E+09 5.27E+09 3 .54E+09 NO DATA 2.87E÷0.9 4.52E+08 4.24E+08 CS- 137 4. 01E+10 5.33E+10 1. 86E+10 NO DATA 1. 82E+10 7.05E+09 7. 59E+08 BA- 14 0 5.82E+06 7.13E+03 3 .75E+05 NO DATA 2.42E+03 4.80E+03 8.98E+06 CE-141 1. 07E+03 7. 12E+/-02 8. 17E+01 NO DATA 3 .35E+02 NO DATA 2 .04E+06 CE-144 7.86E+04 3.25E+04 4.23E+03 NO DATA 1.94E+04 "NoDATA 1.98E+07 PR-143 3.47E+01 1.39E+01 1. 73E+00 NO DATA 8.06E+00 NO DATA 1.14E+05 ND-147 2.17E+01 2.36E+01 -1.41E+00, NO DATA- 1.38E+01' .NO DATA 8.50E+04

• mrem/yr per RCi/m3 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 126 of 195 I

TABLE 3.5-24 I GOAT MILK PATHWAY FACTORS (m2mrem/yr per JiCi/sec)

- RCija (ADULT) gI ORGAN:

ISOTOPE H-3 BONE NO DATA LIVER 1.55E+03*

T.BODY 1.55E+03*

THYROID 1.55E+03*

KIDNEY 1.55E+03*

LUNG

-1.55E+03*

GI-LLI 1.55E+03*

I P-32 2.05E+10 1.27E+09 7.91E+08 NO DATA NO DATA NO DATA 2.30E+09 CR-51 MN-54 FE-55 NO DATA NO DATA 3.27E+05 NO DATA 1.01E+06 2.26E+05 3.43E+03 1.92E+05

.5.27E+04 2.05E+03 NO DATA NO DATA 7.56E+02 2.99E+05 NO DATA 4.55E+03

.,NO DATA 1.26E+05 8.63E+05 3.08E+06 1.30E+05 it FE-59 3.85E+05 9..06E+05 3.47E+05 NO DATA ... NO DATA 2.53E+05 3.02E+06 CO-58 CO-60 NI-63 NO DATA NO DATA 8.05E+08 5.62E+05 1.96E+06

.5.58E+07 1.26E+06 4.33E+06 2.70E+07 NO DATA NO DATA NO DATA .

NO DATA NO DATA NO DATA

ýNO DATA NO DATA NO DATA

. 1.14E+07 3.69E+07 1.16E+07 U

ZN-65 1.64E+08 5.22E+08 2.36E+08 NO DATA 3.49E+08 NO DATA 3.29E+08 RB-86 SR-89 SR-90 NO DATA 3.04E+09 9.78E+10 3.10E+08 NO DATA NO DATA 1.45E+08.

8.73E+07 2.40E+10 NO"DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO: DATA NODATA 6.12E+07 4.88E+08 2.83E+09 I

Y-90 8.48E+00 NO DATA 2.28E-01 NO-DATA NO DATA NO DATA 9.00E+04 U

Y-91 1.03E+03 NO DATA ý2;.75E+01. NO:DATA NO DATA NO DATA 5.66E+05 ZR-95 1'.13E+02 3.63E+01 2.'46E+017 NODATA . 5.69E+01, NO DATA 1.15E+05 NB-95 9.90E+03 5.51E+03 .2.96E+03 NODATA 5.45E+03 NO DATA 3.34E+07 I

MO-99 NO DATA 2.96E+06 5.63E+05' NO DATA 6.71E+06 NO DATA 6.86E+06 TC-99m 3.95E-01 1.12E+00 ,1'.I42E+01 NO: DATA 1'.70E+01 5.47E-01 6ý61E+02 RU-103 1.22E+02 NO DATA 5.24E+01 NO DATA 4.64E+02 NO DATA 1. 42E+04 RU-106 2.44E+03 NO DATA .3..09E+02 NO DATA .4.72E+03, NO DATA 1.58E+05 AG-II0m TE-125m TE-127m 6.96E+06 1.95E+06 5.46E+06 6.44E+06 7.!07E+05 1.95E+06 3".,82E+06 2.261E+05 6.66E+05 NO DATA 5.87E+05 1.40E+06 1.27E+07 7.94E+06 2.22E+07 NO DATA NO DATA NO DATA 2.63E+09 7.79E+06 2-.83E+07 I

TE-129m 7.21E+06 2.69E+06.. 1.14E+06 2.48E+06 3.01E+07 NO DATA 3ý63E+07 1-130 1-131 1-132 5.00E+05 3.54E+08 1.98E-01 1.47E+06 5.06E+08 5.29E-01 5.82E+05 2.90E+08

.1.85E-01 1.25E+08 1.66E+51 1.85E+01 2.30E+06

-8.,68E+08 8.43E-01 NO DATA NO DATA NO DATA 1.27E+06 1.34E+08 9.93E-02 I

1-133 4.62E+06 8.03E+06 2.455+06 1.18E+09 1.40E+07 NO DATA 7.22E+06 1-134 1.-135 CS-134 2.27E+12 1.55E+04

-1.69E+10

.6.16E-12 4.06E+04

.4:.03E+10 2.20E-12.

1.50E+04 3.29E+10

1.07E-10 2.68E+06 NO DATA 9.80E-12 6.51E+04 1.30E+10 NO DATA NO DATA 4.432E+09 .

5.37E-15 4.59E+04 7<.04E+08 I

!CS-136 7.88E+08 3.11E+09 2.24E+09 NO DATA 1.73E+09 2.37E+08 3.53E+08

.CS7137 BA-140 CE-141 2.21E+10 3.23E+06

.5.80E+02 3.03E+10 4.05E+03 3.92E+02 1.98E+10 2.11E+05 4.45E+01 NO DATA NO DATA NO DATA 1.02E+10

-1.38E+03

ý1.82E+02 3.41E+09 2.32E+03 NO DATA 5.84E+08 6.65E+06 1.50E+06 I

CE-144 4.29E+/-04 1.79E+04 2.30E+03 NO;DATA 1.06E+04 NO DATA 1.45E+07 PR-143 1.89E+01 7.56E+00 9;35E-01 NO DATA 4.37E+00 NODATA 8.26E+04 ND-147 1.13E+01 1.30E+01 7.79E-01 NO DATA 7.64E+00 NO DATA 6.25E+04

• mrem/yr per .Ci/m 3 CLINTON -- UNIT #1 Rev.22 -

12/09

CY-CL-170-301 Revision 22 Page 127 of 195 TABLE 3.5-25

'MEAT PATHWAY FACTORS - RMija (CHILD)

(m2 mrem/yr per pCi/sec.)

ORGAN: BONE. LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 :NO DATA 2.33E+02* 2.33E+02* 2.33E+02* 2."33E+02* 2.33E+02* 2.33E+02*

P-32 7.43E+09 3.47E+08 2.86E+08 NO DATA 'NO DATA NO DATA 2.05E+08 CR-51 NO. DATA NO DATA 8.78E+03 4.88E+03 1*.33E+03 8.90E+03 4.66E+05 MN-54 NO DATA 8.03E+06 2.14E+06 NO DATA 2.25E+06 NO DATA 6.74E+06 FE-55 .14 58E+08 2.43E+08 , 7.52E+07' NO DATA NO DATA 1.37E+08 4.50E+07 FE-59 3-.76E+08 6.09E+08 3.03E+08 NO DATA NO DATA 1.76E+08 6.34E+08 CO-58 NO DATA 1.64E+07 5.03E+07 NO DATA NO DATA NO DATA 9.58E+07 CO-60 NO DATA 6.93E+07 2.04E+08 NO DATA NO DATA NO DATA 3:84E+08 NI-63 .2:91E+10 '1.56E+09 9.90E+08 NO DATA ' NO DATA NO DATA 1.05E+08 ZN-65 3.75E+08 .1.00E+09 6.22E+08 NO DATA 6.30E+08 NO DATA 1.76E+08 RB-86 -NO DATA .5.76E+08 '3.54E+08 NO DATA NO DATA NO DATA 3.71E+07 SR-89 4.80E+08 NO DATA .- ",*37E+07 .NO DATA NO DATA NO DATA 1.86E+07 SR-90 1.04E+10 -- '.NO DATA '"2.64.E+09 'NO DATA NO DATA NO DATA 1-.'40E+08 Y-90 1.73E+02 . 'NO DATA ,.4..,62E+00 ' NO.DATA NO DATA NO DATA 4.91E+05 Y-91 1.80E+06 . .NO DATA :4.81E+04. :NO DATA NO DATA NO DATA 2.40E+08 ZR-95 2.67E+06 5.87E+05 5'.22E+05 NO:DATA 8.40E+05 NO DATA 6.12E+08 NB-95 3.10E+06 . 1;21E+06 8.61E+05  :,NO DATA 1.13E+06 NO DATA 2.23E+09 MO-99 NO DATA 1.14E+05 2.83E+04 NO: DATA 2.44E+05 NO DATA ' 945E+04 TC-99m 6.01E-21 1.18E-20 1.95E-19 'NO DATA ,1.71E-19 5.98E-21 6.71E-18 RU-103 1.55E+08 NO DATA 5.96E+07'* NOi'[DATA " 3.90E+08 NO DATA 4.01E+09

,RU-106 4.43E+09 NO DATA 5.53E+08 NO:DATA 5.99E+09 NO DATA 6.90E+10 AG-II0m 8.41E+06 5.68E+06 4.54E+06 NO.DATA 1.06E+07 NO DATA 6.75E+08 TE-125m 5.69E+08 1.54E+08 7.58E+07 1.60E+08 NO DATA NO DATA 5.49E+08

• TE-127m 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 NO DATA 1.44E+09 TE-129m .1.79E+09 4.99E+08 2.77E+08 5.76E+08 5.25E+09 NO DATA 2.18E+09

.17130 2.91E-06 5.89E-06 3.03E-06 6.,49E-04 "8.80E-06 NO DATA 2.75E-06

.1-131 1.65E+07. 1.66E+07 .9.46E+06- 5.50E+09 .2.7'3E+07 NO DATA 1.48E+06 1-132 1.05E-58. 1.93E-58 8.86E-59' 8.93E-57 2'.95E-58 ' NO DATA 2.27E-58 I7133 5.,75E-01 7.10E-01 2.69E-01. 1.32E+02 1.18E+00 NO DATA 2.86E-01 1-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NO DATA '.0 OE+00 1-135 6.86E-17 1.23E-16 5.83E-17 1.09E-14 1.89E-16 NO DATA 9.38E-17 CS-134 9.20E+08 1.51E+09 3. 18E+08, NO DATA .4.:68E+08 1.68E+08 8.'14E+06 CS-136 1.62E+07 4.45E+07 ,2.88E+07' NO DATA 2..37E+07 ' 3'.53E+06 1.56E+06 CS 7 137 1.,33E+09 I..27E+09 .1.88E+08 NO DATA 4.15E+08 1.49E+08 7.98E+06

,BA-140 4.38E+07 -3.84E+04 2.56E+06 NO DATA 1.25E+04 - 2.29E+04 2.:22E+07 CE-141 2.22E+04 1.11E+04 1.64E+03 NO DATA 4.85E+03 NO DATA 1.38E+07

• CE-144 .2.31E+06 7.24E+05 1.23E+05 NO DATA 4.01E+05 NO DATA 1.89E+08

.PR-143 3.34E+04 ' 1.00E+04 I..66E+03 NO-DATA 5.43E+03 NO DATA 3.60E+07 ND-147 1.17E+04 9.47E+03 7.33E+02 NO DATA 5.20E+03 ' NO DATA 1.50E+07

• mrem/yr per gCi/m3 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 g

Revision 22 Page 128 of 195 g

TABLE 3.5-26 g MEATPATHWAY FACTORS - RMija (TEEN)

(m2 mrem/yr per pCi/sec) H ORGAN: BONE LIVER .T.BODY THYROID KIDNEY .LUNG 'GI-LLI ISOTOPE H-3 NO DATA 1 .93E+02* 1.93E+02* 1.93E+02* 1.93E+02". 1.93E+02* 1.93E+02*

P-32 3.95E+09 +2.45E+08 1.53E+08 NO DATA NO DATA NO DATA 3.32E+08 CR-51 NO DATA NO DATA 5.65E+03 3.14E+03 1.24E+03 8.0.7E+03 9.50E+05 MN-54 NO DATA 7.02E+06 1.39E+06 NO DATA 2.09E+06' NO DATA 1.44E+07 FE-55 2.38E+08 1.69E+08 3.94E+07 NO DATA NO DATA 1.07E+08 7.31E+07 FE-59 2.12E+08 4.95E+08 1.91E+08: NO DATA NO DATA 1:.56E+08 1.17E+09 CO-58 NO DATA 1.41E+07 3.25E+07 NO DATA NO DATA NO DATA ' 1.94E+08 CO-60 NI-63

• ZN-65 NO DATA 1.52E+10 2.50E+08 5ý84E+07 1.07E+09 8.69E+08

, 1.32E+0.8 5.15E+08 4.05E+08 NO NO NO DATA DATA DATA NO DATA NO DATA NO DATA NO DATA 5.56E+08;;-NO DATA 7.61E+08 1.71E+08 3.68E+08 I

RB-86 NO DATA 4.05E+08 1.90E+08 NO DATA NO DATA NO DATA 6.00E+07 SR-89 SR-90 Y-90 2.54E+08 8.04E+09 9.11E+01 NO DATA NO DATA NO DATA

-7.27E+06

.',1.99E+09 2.45E+00 NO NO NO DATA DATA DATA .,NO NO DATA NO DATA, DATA NO DATA NO DATA NO DATA 3.02E+07 2.26E+08 7.51E+05 U

Y-91 9.55E+05 NO DATA .2.56E+04 NO DATA NO, DATA NO DATA 3.91E+08 ZR-95 1.50E+06 4.74E+05 '3.,25E+05. NO. DATA. 6.93E+05 NO DATA 1.09E+09 NB-95 1.79E+06 9.94E+05 5.'47E+05 .NO DATA 9.64E+05, NO DATA 4.25E+09 MO-99 NO DATA 8.20E+04 1.56E+04 NO DATA 1.88E+05 NO DATA 1.47E+05 TC-99m 3.42E-21 9.54E-21 1.24E-19 NO DATA 1.42E-19 5.29E-21 6.26E-18 RU-103 8.575+/-07 NO DATA ,3.66E+07. NO DATA 3.02E+08 NO DATA .7.16E+09 RU-106 .2.36E+09 NO DATA ,2.97E+08 NO DATA .4.54E+09 NO DATA 1.13E+11 AG-II0m 5.04E+06 4.77E+06 .2.90E+06 NO DATA 9.10E+06 NO DATA. 1.34E+09 TE-125m 3.03E+08 1.0*9E+08 4.06E+07 8.47E+07 NO DATA NO DATA 8.'95E+08 TE-127m 9.40E+08 3.33E+08 1.12E+08 2.24E+08 3.81E+09 NO DATA . 2.34E+09 TE-129m 9.49E+08 3.52E+/-08 1.50E+08 3.06E+08 3.97E+09 NO DATA 3.56E+09 1-130 1.63E-06 4.71E-06 1.88E-06 3.84E-04 7.25E-06 NO DATA .3.62E-06 I-131 1-132 1-133 8.89E+06 5.78E-59 3.09E-01 1.24E+07 1.51E-58 5.25E-01 6.69E+06 5.42E-59 1.60E-01 3.63E+09 5,.09E-57 7..32E+01 2.14E+07 2*38E-58 9.20E+01 NO DATA .2.46E+06 NO DATA " 6.58E-59 NO DATA 3.97E-01 I

1-134 0.00E+00 .:005E+00 . 0.0E+00 0.OOE+00 0.00E+00 NO DATA 0-.OOE+00 1-135 CS-134; CS-136

,3.79E-17 5*22E+08 9.36E+06 9.75E-17 1.23E+09 3.68E+07 3.61E-17 5.70E+08 2.47E+07 6.27E-15 NO DATA NO DATA

.1.54E-16+

3.91E+08 2.01E+07 NO DATA 1.49E+08

3.16E+06 1.08E-16 1.53E+07 2.96E+06 U

CS-137 7.24E+08 9.63E+08 3.35E+08 .NO DATA 3.28E+08 .1.27E+08 .. 37E+07 BA-140 2.37E+07.- 2.91E+04 1.53E+06 NO DATA 9:.86E+03 1.96E+04 3.66E+07 CE-141 CE-144

.1.17E+04 '7.83E+03 1'.23E+06 5.10E+05 9.OOE+02 6.62E+04 NO NO DATA DATA 3.69E+03' 3.04E+05 NO DATA NO DATA 2.24E+07 3.10E+08 I

PR-143 1.77E+04 7.06E+03 8.80E+02 NO DATA .4.10E+03 ýNO DATA 5'82E+07 ND-147 6.22E+03 6.76E+03 4.05E+02 NO DATA 3.97E+03.. NO DATA 2.44E+07 [

U

• mrem/yr per .Ci/m 3 I g

I CLINTON -- UNIT #1 12/09 Rev.22 -

g

CY-CL-170-301 Revision 22 Page 129 of 195 TABLE 3.5L27 MEAT PATHWAY FACTORS' - RMija* (ADULT) 2 (m mrem/yr per 4Ci/sec)

ORGAN: BONE LIVER T..BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 3.24E+02* 3.24E+02* 3.24E+02* 3.24E+02*- 3.24E+02* 3.24E+02*

P-32 ... 65E+09 2.89E+08 1.80E+08 NO DATA "NO DATA NO DATA 5.23E+08 CR-51 - NO DATA NO DATA 7.05E+03 4.21E+03' 1.55E+03 9.35E+03 1.77E+06 MN-54 :NO DATA 9.19E+06 1.75E+06 NO DATA " 2.73E+06 NO DATA 2.81E+07 FE-55 2.94E+08 2.03E+08 .4.74E+07 NO DATA NO 'DATA 1.13E+08 1.17E+08 FE-59 22.66E+08 6.24E+08 2.39E+08 NO DATA -,NO DATA .1.74E+08 2.08E+09 CO-58  !-NO-DATA 1.83E+07 4.09E+07 NO DATA' NO-DATA NO DATA 3.70E+08 CO-60 *NO DATA 7.51E+07 1.66E+08 NO DATA- -NO DATA NO DATA 1.41E+09

.NI-63 .1.89E+10. 1.31E+09 6.32E+08 NO DATA - NO DATA- NO DATA 2.73E+08 ZN-65 .:3.56E+08 1.13E+09 5.12E+08 NO DATA "'7.57E+08 NO DATA 7.13E+08 RB-86 NO DATA, .. 4;87E+08 2.27E+08 MO DATA- NO DATA NO DATA 9.61E+07 SR-89 3.01E+08 NO DATA 8.64E+06 NO DATA NO DATA NO DATA 4.83E+07 SR-90 1.24E+10 NO-DATA .:,3.05E+09 NO DATA -NO DATA NO DATA 3.59E+08 Y-90 1.09E+02 NODATA - 2.92E+00 - NO DATA NO DATA NO DATA 1.15E+06 Y-91 1.13E+06-:1 NO DATA 3.03E+04 NO DATA NO' DATA " NO DATA 6.23E+08 ZR-95 1.87E+06 6.OOE+05 4.06E+05 NO DATA 9.41E+05 NO DATA 1.90E+09 NB-95 2.30E+0.6 1.28E+06 6.86E+05- NO DATA 1.26E+06 NO DATA 7.75E+09 MO-99 NO DATA 9.91E+04- 1.89E+04`-' -NO DATA 2.24E+05 NO DATA 2.30E+05 TC-99m 4.32E-21 1.22E-20 -1.56E-19 'NO DATA 1.86E-19 5.99E-21 7.23E-18 RU-103 1.05E+08 NO DATA 4.53E+07, NO DATA 4.02E+08 NO DATA 1.23E+10 RU-106 2.81E+09 NO DATA -... 3.55E+08 NO 'DATA 5.42E+09 NO DATA 1.82E+11 AG-I0mn 6.67E+06 6.17E+06 3.67E+06 :NO DATA. 1.21E+07 NO DATA 2.52E+09 TE-125m 3.59E+08 1.30E+08 4.81E+07 I*08E+08 1.46E+09 NO DATA 1.43E+09 TE-127m 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.54E+09 NO DATA 3.75E+09 TE-129m 1.13E+09 4.2-2E+08 1.79E+08 '3.89E+08 4.73E+09 NO DATA 5.70E+09 1-130 .2.03E-06 . 5.98E-06 .2.36E-06 5.07E-04 9.33E-06 NO DATA -5.15E-06 1-131 1.0:7E+07 1.54E+07 8.80E+06 5.03E+09 '::2.63E+07 NO DATA 4.05E+06 1-132 7.13E-59 1.91E-58 6;67E-59 6.67E-57: 3.04E-58 NO DATA 3.:58E-59 1-133 3.-70E-01 6.43E-01 1.96E-01 9.45E+01 1.12E+00 NO DATA 5.78E-01 1-134 0.00E+00 0.00E+00. 0.00E+00 0.OOE+00 0.00E+00 NO DATA 0.00E+00 1-135 4.65E-17 -1.22E-16' 4.49E-17 8.03E-15 -1.955-16 NO DATA 1.38E-16 CS-134 6.53E+08 1.55E+09 1.27E+09 NO DATA -5.03E+08 1.67E+08 2.72E+07 CS-136 1.20E+07, 4.75E+07 3.42E+07 NO DATA 2.65E+07 - 3.63E+06 5.40E+06 CS-137 8.69E+08 1i19E+09 7.78E+08 NO DATA .4.03E+08 1.34E+08 2.30E+07 BA-140 2.88E+07 3.62E+04 1.89E+06 NO DATA- 1.23E+04 2.07E+04ý 5.94E+07 CE-141 1.39E+04 '9.43E+03 1.07E+03 NO DATA 4.38E+03ý -NO DATA 3.61E+07 CE-144 - - 1.46E+06 6 IOE+05 7.83E+04 -NO DATA. 3.62E+05- NO DATA 4.93E+08 PR-143 2.09E+04 8.40E+03 -1.04E+03 NO DATA 4.85E+03 NO DATA 9.17E+07 ND-147 7.04E+03 8.14E+03 -4.87E+02 NO DATA 4.76E+03 1NO DATA 3.91E+07

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TABLE 3.5-28 I VEGETATION PATHWAY FACTORS (m2 mrem/yr per gCi/sec)

- RVija (CHILD)

I ORGAN: BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE g H-3 NO DATA 4.0iE+03*. 4.01E+03* 4.01E+03* 4.01E+03* 4.01E+03* 4.01E+03*

P-32 3.37E+09 .1.57E+08 1.30E+08 NO DATA NO DATA NO DATA 9.30E+07 CR-51 NO DATA NO DATA 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 NO DATA 6.64E+08 1.77E+08 NO DATA 1.86E+08 NO DATA 5.58E+08 FE-55 8.02E+08 4.25E+08 1.32E+08 NO DATA NO DATA 2.'40E+08 7.88E+07 FE-59 3.98E+08 6.43E+08 3.21E+08 NO DATA NO DATA l.87E+08 6.70E+08 CO-58 NO DATA 6.44E+07 1.97E+08 NO DATA NO DATA -NO:DATA 3.76E+08 CO-60 NI-63 ZN-65 NO DATA 3.95E+10 8.11E+08 3.79E+08 2.11E+09 2.16E+0'9

1.12E+09 1.34E+09 1.34E+09 NO DATA NO DATA

-NO DATA NO DATA NO DATA 1.36E+09

.'NO DATA NO DATA -

NO DATA N

2.10E+09 1.l2E+08 3.79E+08 I

RB-86 SR-89 SR-90 NO DATA

-3.59E+10 1.24E+12 4.53E+08 NO DATA NO DATA' 2.79E+08

-1.03E+09 3,.14E+÷I -

NO DATA NO DATA NO DATA NO DATA NODATA NO DATA NO DATA NO DATA

NO DATA

-2.91E+07 1.39E+09 1 .67E+10 5

Y-90 .2..31E+04 NO DATA 6.18E+02 NO DATA NO DATA NO DATA 6.58E+07 Y-91 1.86E+07 NO DATA 9'.97E+05. NO DATA NOIDATA NO DATA 2.48E+09 ZR-95 3.86E+06 8.49E+05 7.5-6E+05: NO DATA 1.22E+06 NO DATA 8.86E+08 NB-95 4.10E+05 1.60E+05 l,.14E+05., . NO DATA, 1.50E+05 NO DATA 2.95E+08 MO-99 NO DATA 7.67E+06 I.S90E+06" 'NO DATA 1.64E+07 NO DATA .6.35E+06 TC-99m 4.70E+00 9.21E+00 .,1%.53E+02 NO DATA 1.34E+02 4.68E+00 5.24E+03 RUý103 1.54E+07 NO DATA 5.90E+06, NO DATA 3.86E+07 NO DATA 3.97E+08 RU-106 7.45E+08 NO DATA -9.30E+07 NO DATA 1.01E+09 NO DATA .1.16E+10 AG-II0m. 3.21E+07 2.17E+07 1.73E+07 NO DATA 4.04E+07 NO DATA 2.58E+09 TE-125m 3.51E+08 9.52E+07 14.68E+07 9.86E+07 NO DATA NO DATA 3.39E+08 TE-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 NO DATA 1.07E+09 TE-129m 8.43E+08 2.35E+08,, 1.31E+08 2.72E+08 2.47E+09 NO DATA 1.03E+09 1-130 6.10E+05 1.23E+06 6.35E+05 1.36E+08 -1.84E+06 NO DATA 5.77E+05 1-131 1.43E+08. 1 44E+08 8.16E+07+ 4.75E+10 2.36E+08 'NO DATA 1.28E+07

.1-132 9.20E+01 1.69E+02 7.77E+01 7.84E+03 2.59E+02. NO DATA :1.99E+02 1-133 3.53E+06 4.36E+06 1.65E+06 8.11E+08 7.27E+06 NO DATA 1.76E+06 1-134 1.50E-04 2.79E-04 1.28E-04 6.41E-03 4.26E-04 NO'DATA 1.85E-04 1-135 CS-134 CS-136

'6.28E+04 1.60E+10 ,

8.23E+07 1-.13E+05 2.63E+10 2.,26E+08 5.34E+04 5.55E+09

%i.46E+08. NO DATA 1.OOE+07 NO DATA 1.73E+05 8.15E+09/

1.20E+08 NO DATA 2.92E+09 Ir.*80E+07--

8.61E+04 I. 42E+08 7.95E+06 I

CS-137 2.-39E+10 2.29E+10 3.38E+09 NO DATA 7.46E+09 .2.68E+09 1.43E+08 BA-140 CE-141 CE-144 2.77E+08 6.56E+05, 1.27E+08 2.42E+05 3.27E+05 3.99E+07 1.62E+07ý 4.85E+04 6.79E+06

-NO NO NO DATA DATA DATA 7.89E+04 1.43E+05 2.21E+07' 1.45E+05

-NO DATA NO DATA 1.40E+08 4.08E+08 1.04E+10 I

PR-143 1.45E+05 4.37E+04 7.22E+03 NO DATA 2.36E+04 NO DATA 1.57E+08 ND-147 7-.16E+04 5. . 80E+04 4.49E+03. NO DATA 3.18E+04 NO DATA 9.18E+07 ID

• mrem/yr per gCi/m 3 O

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CY-CL-170-301 Revision 22 Page 131 of 195 TABLE 3.5-29 VEGETATION PATHWAY FACTORS - RVija ý(TEEN)

(m 2mrem/yr per J.Ci/sec)

ORGAN: BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ISOTOPE H-3 NO DATA 2. 59E+03" 2. 59E+03* 2. 59E+03* 2. 59E+03* 2. 59E+03" 2. 59E+03*

P-32 1.61E+09 9. 97E+07 6 .24E+07 NO DATA NO DATA NO DATA 1.35E+08 CR-51 NO DATA NO DATA 6.12E+04 3.40E+04 i.34E+04 8.74E+04 1. 03E+07 MN-54 "NO'-DATA A4.54E+08 9. 01E+07 NO DATA 1.-36E+08 NO DATA 9.32E+08 FE-55 . ... '26E+08 2.31E+08 5.39E+07 'NO DATA .NO DATA 1.46E+08 1. OOE+08 FE-59 -'179E+08 4. 18E+08 1.61E+08 NO DATA NO DATA 1. 32E+08 9. 88E+08 CO-58 -NO DATA 4.36E+07 1. 01E+08 NO DATA NO DATA NO DATA 6. 02E+08 CO-60 - : NO DATA 2 .49E+08 5. 60E+08 NO DATA NO DATA NO DATA 3 . 24E+09 NI-63 1.61E+10 1. 14E+09 55.46E+08 NO DATA .NO :DATA NO DATA 1. 81E+08 ZN-65 4.2'3E+08. 1.47E+09 6. 86E+08 NO DATA '9.41E+08 NO DATA 6. 23E+08 RB-86 NO DATA 2.7.2E+08 1 .28E+08 NO, DATA :NO DATA NO DATA 4. 02E+07 SR-89 .1.51E+10O ,NO DATA 4 .32E+08 NO DATA .1NO DATA NO DATA 1. 80E+09 SR-90  ;,7.50E+II NO DATA 1.85E+I1 NO DATA .NO DATA NO DATA 2.11E+10 Y-90 1.25E+04 NO DATA 3. 37E+02 NO DATA NO DATA NO DATA 1. 03E+08 Y-91 7.84E+06 NO DATA -:2:. 10E+05' NO DATA NO DATA NO DATA 3. 21E+09 ZR-95 1.73E+06 5.46E+05 3. 75E+05 NO DATA '8.02E+05 NO DATA 1.26E+09 NB-95 1.92E+05 1. 07E+05 5.86E+04 NO DATAý 1. 03E+05 NO DATA 4. 56E+08 MO-99 NO DATA 5. 64E+06 1. 08E+06 NOI DATA 1. 29E+07' NO DATA 1 .01E+07

• 'TC-99m 2.73E+00 7. 61E+00 9. 86E+01 NO DATA 1. 13E+02 4. 23E+00 5 . OOE+03

.RU-103 6.81E+06 NO DATA 2. 91E+06 NO DATA 2 .40E+07 NO DATA 5. 69E+08 RU-106 3.09E+08 NO DATA 3. 89E+07 NO DATA 5. 95E+08 NO DATA 1.48E+10

,AG-IIrn 1.51E+07 1.43E+07 8 . 72E+06 NO DATA 2. 72E+07 NO DATA 4'.03E+09

• TE-125m 1'.49E+08 5.35E+07 1. 99E+07 4.15E+07 NO DATA NO DATA 4.38E+08 TE-127m 5.52E+08 1. 96E+08 6.57E+07 1.31E+08 2.24E+09 NO DATA 1.38E+09 TE-i29m 3.60E+08 1.34E+08 5. 70E+07 1. 16E+08 1. 51E+09. NO DATA 1.35E+09 1-130 3.50E+05 1. 01E+06 4.05E+05 8 .26E+07 .1.56E+06 NO DATA 7. 79E+05

.1-131 .7.66E+07 1. 07E+08 5. 76E+07 3. 13E+I0 1. 85E+08 NO DATA 2. 12E+07 I-132 5.19E+01 1. 36E+02 4.87E+01 4. 58E+03 2'. 14E+02 NO DATA 5. 91E+01 I-133 1.93E+06 3 .28E+06 :1. OOE+06 4. 58E+08 5. 75E+06 NO DATA 2 .48E+06 1-134 8.44E-05' 2 .24E-04 8.03E-05 3. 73E 3. 53E-04 NO DATA 2.95 E-06 1-135 3.53E+04 9.09E+04 3.37E+04 5. 85E+06 1.44E+05 NO DATA 1. 01E+05 CS-134 *7.10E+09 1.67E+10 7. 75E+09 NO DATA 5. 32E+09 2. 03E+09 2. 08E+08 CS-136 4.37E+07 1.72E+08 1. 16E+08 NO .DATA 9.37E+07 1.48E+07 1.38E+07 CS-137 1.0IE+I0 1.35E+10 4 .70E+09 NO DATA 4 .59E+09' 1'.78E+09 1. 92E+08 BA-140. 1.38E+08 1. 69E+05 8. 89E+06 NO DATA 5. 73E+04ý 1. 14E+05 2 :13E+08 CE-141 2.83E+05 -1. 89E+05 2. 17E+04- NO DATA 8.90E+/-04 NO DATA 5.41E+08 CE-144 5.29E+07 .'2.19E+07 2 . 84E+06 NO' DATA 1. 31E+07 NO DATA 1.33E+10 PR-143 7.OOE+04 2. 79E+04 3 . 48E+03 NO DATA 1.62E+04 NO DATA 2 .30E+08 ND-147 3.62E+04: 3-.94E+04 2 .36E+03 NO DATA 2 .31E+04 NO DATA 1.42E+08 3

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Revision 22 Page 132 of 195 It TABLE 3.5-30 I VEGETATION PATHWAY FACTORS -

(m2 mrem/yr per gICi/sec)

RVija (ADULT)

I ORGAN:

ISOTOPE H-3 BONE NO DATA.

LIVER

.2.26E+03*

T.BODY 2.26E+03*

THYROID 2.26E+03*

KIDNEY 2.26E+03*

LUNG 2.26E+03*

GI-LLI 2.26E+03*

I P-32 1.40E+09 8.70E+07 5.41E+07 NO DATA NO DATA NO DATA 1.57E+08 CR-51 NO DATA NO DATA 4.60E+04 2.75E+04 1.01E+04 6.11E+04 1.16E+07 MN-54 NO DATA 3.13E+08 5.96E+07 NO DATA 9.30E+07 NO DATA 9.58E+08 FE-55 2.10E+08 1..45E+08 3.38E+07 NO DATA NO DATA 8.10E+07 8.33E+07 FE-59 1.26E+08 2.96E+08 1.13E+08 NO DATA NO DATA 8.27E+07 9.86E+08 CO-58 NO DATA 3.,08E+07 6.90E+07 NO DATA NO DATA NO DATA 6.24E+08 CO-60 NO DATA 1.67E+08, 3.69E+08 NO DATA NO DATA NO DATA 3.14E+09 NI-63 1.04E+10 7.21E+08 3.49E+08 NO DATA NO DATA NO DATA 1.50E+08 ZN-65 3.18E+08 1.01E'+09 4.57E+08 NO DATA 6.76E+08 NO DATA 6.36E+08 RB-86 NO DATA 2.19E+08 1.02E+08 'NO DATA NO DATA ' NO DATA 4.33E+07 SR-89 9.95E+09 NO DATA 2.86E+08 NO DATA NO DATA NO DATA 1.60E+09 SR-90 6.04E+II NO DATA 1.48E+il NO DATA. NO DATA NO DATA 1.75E+10 Y-90 1.33E+04 NO DATA 3.56E+02 NO DATA NO DATA NO DATA 1.41E+08 Y-91 5.12E+06 NO DATA. j1.37E+05 NO DATA: NO DATA NO DATA 2.82E+09 ZR-95 1.18E+06 3.79E405 2.56E+05 -NO DATA . 5.94E+05 NO DATA 1.20E+09 NB-95 1.42E+05 7.91E+04 4.25E+04 NO DATA 7.82E+04 NO DATA 4.80E+08 MO-99 NO DATA 6.12E+06 1.16E+06 NO DATA 1.39E+07 NO DATA 1.42E+07 TC-99m 3.09E+00 8.73E+00 1.11E+02 NO DATA 1.33E+02 4.28E+00 5.16E+03 RU-103 4.77E+06 NO DATA 2.06E+06 NO DATA 1.82E+07 NO DATA 5.57E+08 RU-106 1.93E+08 NO DATA 2.44E+07 NO DATA 3.73E+08 NO DATA 1.25E+10 AG-II0m 1.05E+07 9.75E+06 5.79E+06 NO DATA 1.92E+07 NO DATA 3.98E+09 TE-125m 9.67E+07 3.51E+07 1.30E+07 2.91E+07 3.93E+08 NO DATA 3.86E+08 TE-127m 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 NO DATA 1.17E+09 TE-129m 2.51E+08 9.35E+07 3.97E+07 8.61E+07 1.05E+09 NO DATA 1.26E+09 1-130 3.91E+05 1.15E+06 4.55E+05 9.77E+07 1.80E+06 NO DATA 9.93E+05 1-131 8.07E+07 1.15E+08 6.62E+07 3.78E+10 1.98E+08 NO DATA 3.05E+07 1-132 5.77E+01 1.54E+02 5.40E+01 5.40E+03 2.46E+02 NO DATA 2.90E+01 1-133 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.34E+06 NO DATA 3.26E+06 1-134 9.33E-05 2.53E-04 9.06E-05 4.39E-03 4.03E-04 NO DATA 2.12E-07 1-135 3.91E+04 1.02E+05 3.77E+04 6.75E+06 1.64E+05 NO DATA 1.16E+05 CS-134 4.67E+09 1.11E+10 9.08E+09 NO DATA 3.59E+09 1.19E+09 1.94E+08 CS-136 4.26E+07 1.68E+08 1.21E+08 NO DATA 9.35E+07 1.28E+07 1.91E+07 CS-137 6.36E+09 8.70E+09 5.70E+09 NO DATA 2.95E+09 9.82E+08 1.68E+08 BA-140 1.29E+08 1.62E+05 8.43E+06 NO DATA 5.50E+04 9.26E+04 2.65E+08 CE-141 1.97E+05 1.33E+05 1.51E+04 NO DATA 6.19E+04 NO DATA 5.09E+08 CE-144 3.28E+07 1.37E+07 1.76E+06 NO DATA 8.14E+06 NO DATA 1.11E+10 PR-143 6.26E+04 2.51E+04 3.10E+03 NO DATA 1.45E+04 NO DATA 2.74E+08 ND-147 3.33E+04 3.85E+04 2.31E+03 NO DATA 2.25E+04 NO DATA 1.85E+08

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• CY-CL-170-301 Revision 22 Page 133 of 195 TABLE 3.5-31 GROUND PLANE PATHWAY FACTORS'- RGi 2

(m mrem/yr per ý.Ci/sec)

TOTAL TOTAL ISOTOPE BODY SKIN ISOTOPE BODY SKIN H-3 0. 00E+00 0.OOE+00 ZR-95 *2.45E+08 2 .85E+08 P-32 0. OOE+00 0. OOE+00 NB-95 1.37E+08 1.61E+08 CR-51 4. 65E+06 5. 50E+06 TC-99mr 1. 84E+05 2.11E+05 MN-54 1.38E+09 1. 62E+09 RU-103 1. 08E+08 1.26E+08 MO-99 3. 99E+06 4 62E+06 RU-106 4.22E+08 5. 06E+08 FE-55 0. 00E+00 0. 00E+00 TE-127m 9.16E+04 1. 08E+05 FE-59 2. 73E+08 3. 20E+08 1-131 1.72E+07 2. 09E+07 CO-58 3. 80E+08 4 . 45E+08 1-132 1.25E+06 1.47E+06 CO-60 2 32E+10* 2. 73E+10 1-135 . 21. 53E+06 2. 95E+06 NI-63 0 00E+00 0. 00E+00 CS- 134 6 .87E+09 8.01E+09 AG-iI0m 3. 44E+09 4. 01E+09 CS-136 1. 51E+08 1.71E+08 TE-125m 1. 56E+06 2 . 13E+06 BA-140 2. 05E+07 2.35E+07 ZN-65 7. 48E+08 8 . 60E+08 CE-141' 1. 37E+07 1. 54E+07 TE-129m 1. 98E507 .2.31E+07 CE-144 6. 96E+07 8. 05E+07 RB-86 8. 98E+06 1. 03E+07 PR-1433 0 .00E+00 0. OOE+00 1-130 5 . 50E+06 6 . 68E+06 ND-147 8. 39E+06 1. 01E+07 SR-89 2 .16E+04 2. 50+/-E04 SR-90 NO DATA NO DATA 1-133 2 .45E+06 2.98E+06 1-134 4 .46E+05 5.30E+05 Y-90 4. 50E+03 5.31E+03 Y-91 1. 07E+06 1.21E+06 CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 134 of 195 4.0 COMPLIANCE WITH 40CFR190 ft 4.1 Total Dose Operation and Surveillance Requirements OPERATION, REQUIREMENT I The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium 'fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. This I

requirement is applicable at all times.

REMEDIAL REQUIREMENT: U

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 2.4.1(a),

2.4.1(b), 3.5.1(a), 3.5.1(b), 3.5.2(a), and 3.5.2(b), calculations shall be made including direct radiation contributions from the reactor unit I

and from outside storage tanks to determine whether the above limits of Section 4.1 have been exceeded.

If such is the case, prepare and submit to the I]

Regional Administrator of the Regional Office of the NRC within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special['

Report, as defined in 10CFR20 Part 2203(4), shall include the following information:

1. An estimate of each individuals dose.

2. The levels of radiation and concentrations of radioactive material involved. i

3. The cause of the elevated exposures, dose rates, or concentrations.[]

4. Corrective steps taken or planned to ensure against a recurrence, including the schedule for achievingconformance with applicable limits, ALARA constraints, generally applicable environmental standards, and associated. licensei conditions.

I CLINTON -UNIT 12/09

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CY-CL-170-301 Revision 22 Page 135 of 195 SURVEILLANCE REQUIREMENTS 4.1.1 Cumulative dose contributions from liquidand gaseous effluents shall be determined in accordance with Sections 2.4.1.1, 3.5.1.1, and 3 5.2.1, and in accordance with the methodology and parameters described or specified in this manual.

4.1.2 Cumulative dose contributions from direct radiation from

- *the reactor and from radwaste storage tanks shall be determined in accordance with the methodology and parameters described or specified inthis manual. This requirement is applicable only under conditions set forth in the Remedial Requirement specified above (Section 4.1)

1. The total body and organ doses resulting from liquid effluents will be summed with the doses resulting from gaseous effluents (including non-noble gases) and the doses to the maximum exposed individual from other operations of the uranium fuel cycle. The effluent doses will be based upon releases from CPS during the previous three quarters and from the quarter in which the Section 4.1 OPERATION REQUIREMENT was exceeded.

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5.0 RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM

/4 The primary requirements for the Clinton Power Station Radiological Environmental Monitoring Program (REMP) are set forth in Table 5.1-1 and shown by location in Figures I

5.0-1,5._0-2, 5.0-3 and 5.0-4.

In addition to the required sampling program, CPS will perform supplemental periodic and long term sampling and analyses in order to better monitor environmental exposure pathways. These samples will not be listed in this manual:

I I

CLINTON -- UNIT #1 Rev.22 -

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m CY-CL-170-301 Revision 22 Page 137 of 195 5.1 Monito'ring Program Operation and Surveillance Requirements OPERATION REQUIREMENT.

The Radiological Environmental Monitoring Program shall be conducted as specified in Table 5.1-1. This requirement applies at all times.,

REMEDIAL REQUIREMENT:

a. With the radiological environmental monitoring program not being conducted as specified in Table 5.1-1 prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of N plant effluents in an environmental sampling medium at a specified location exceeding the report levels of Table 5.1-2 when averaged over any calendar quarter prepare and submit to the Regional Administrator of the Regional Office of the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 2.4.1, 3.5.1, and 3.5.2. When more than one of the radionuclides in Table 5.1-2 are detected in the sampling medium, this report

,p shall be submitted if:

concentration (1) + concentration (2) + >1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 5.1-2 are detected and the result of plant effluents, this report bE shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Section 2.4.1, 3.5.1, and 3.5.2.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological f! 'Environmental Operating Report.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

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CY-CL-170-301 I

Revision 22 Page 138 of 195 1

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 5.1-1, identify locations for II obtaining replacement samples and add, them to the radiological environmental monitoring program within 30 days. The specific locations from which samples ill were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.5.1, identify the cause of the I

unavailability of samples and identify the new location(s) for obtaining replacement samples in the next annual Radiological Environmental Operating Report and also include in the report a revised II figure(s) and, table for this manual reflecting the new location(s).. 11 5.1.1 SURVEILLANCE REQUIREMENTS The radiological environmental monitoring samples shall I

be collected pursuant to Table 5.1-1 from the.specific locations given in Table 5.1-1 and Figures 5.0-I, 5,.0-2, 5.0-3, and 5.0-4 and shall be analyzed pursuant to the II requirements of Table 5.1-1 and the detection capabilities required by Table 5.1-3.

I I

It 1

I II II II II CLINTON -- UNIT #1 Rev.22 -

12/09 II

-- vwý go ow* m m m m am-, ow, !a OW*m Aw a-Jm CY-CL-170-301 Revision 22 Page 139 of 195 TABLE 5.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

1. DIRECT RADIATION' 40 routine monitoring stations Quarterly Gamma dose quarterly either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

(1) an inner ring of stations,..

one in each meteorological sector in the general area' of the SITE BOUNDARY; SECTOR CODE DISTANCE from station (miles)

N CL-36 0.6 NNE CL-5 0.7 NE CL-22 0.6 ENE CL-23 0.5 E CL-24 0.5 -

ESE CL-42 2.8 SE CL-43 2.8.

SSE CL-44 2.3 S CL-45 2.8 SSW CL-46 2.8 SW CL-47 3.3 WSW CL-48 2.3 W CL-I 1.8 WNW CL-34 0.8 NW CL-35 0.7 NNW CL-63 1.3 CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 Revision 22 Page 140 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE.PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

1. DIRECT RADIATIONb (2) an outer ring of stations, (continued) one in each meteorological sector in the 6 to 8 km (3.7 miles to 5.0 miles) range from the site; SECTOR CODE DISTANCE from station (miles)

N CL-76 4.6 NNE CL-77 4.5 NE CL-78 4.8 ENE CL-79 4.5 E CL-53 4.3 ESE CL-54 4.6 SE CL-55 4.1 SSE CL-56 4.1 S CL-57 4.6 SSW CL-58 4.3 SW CL-60 4.5 WSW CL-61 4.5 W CL-80 4.1 WNW- CL-81 4.5 NW CL-51 4.4 NNW CL-52 . 4.:.3 CLINTON -- UNIT #1 Rev.22 - 12/09 wa~

aw wi Nie 20-w N'm

CY-CL-170-301 Revision 22 Page 141 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

1. DIRECT RADIATION (3) the balance of the stations (continued) to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.

SECTOR CODE DISTANCE from station (miles)

N CL-37 3.4 N CL-75 0.9 ENE CL-65 2.6 E CL-41 2.4 S (control) CL-1l 16 W CL-49 .3.5 W CL-74 1.9 WNW CL-64 2.1 CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 Revision 22 Page 142 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

2. AIRBORNE Radioiodine and Samples from5 ,locations: Continuous sampler Radioiodine Canister: I-Particulates operations with sample 131 analysis weekly.

a. 3 samples from close to collection weekly, or, the 3 SITE BOUNDARY more frequently if Particulate Sampler:

locations in different required by dust Gross beta radioactivity sectors of the highest loading. analysis following filter

-d calculated annual average change.; Gamma isotopic ground-level D/Q. analysise of composite (by location) quarterly.

SECTOR CODE DISTANCE from station (miles)

NNE CL-2 0.7 NE CL-3 N CL-15 0.9

b. 1 samplefrom the vicinity of a community having the highest-calculated annual average ground-level D/Q.

SECTOR CODE DISTANCE from-station (miles) 7-- CL- 8 2 2-.. -2 CLINTON -- UNIT #1 Rev.22 - 12/09 ft ol a 100WK06wAm M-n -0 10 mo 1-

No-w -w Ow- O*e l "t, 0- 10 M am CY-CL-170-301 Revision 22 Page 143 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

2. AIRBORNE (continued) c. 1 sample from a control locatibn, as for example 15-30 km (9.3 miles to 18.6 miles) distant and in the least prevalent wind directionc.

SECTOR CODE DISTANCE from station (miles)

S (control) CL-li .16

3. WATERBORNE

a. Surf acef 1 sample upstream Composite sample over Gamma isotopic analysise 1 sample downstream 1 month periodg monthly. Composite for tritium analysis quarterly.,

SECTOR CODE DISTANCE from station (miles)

ENE (upstream) CL-91 6.1 SE. (downstream) CL-90 0.4 CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 Revision 22 Page 144 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF ANALYSIS

3. WATERBORNE (continued)

b. Ground Samples from 1 or 2 sources, Quarterly Gamma isotopice and only if likely to be tritium analysis h

affected.. quarterly.

SECTOR' CODE DISTANCE from station (miles)

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 edgeofQ-the lake.

c. Drinking 1-sample of each of 1 to 3 of Composite sample over I-131 analysis on each the nearest water supplies 2-week periodg when I- composite when the dose that could be affected by its 131 analysis is calculated for the discharge.* performed, monthly consumption of the water composite otherwise. is greater than 1 mrem per year.' Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.

SECTOR CODE -DISTANCE from station (miles)

WNW CL-14 within Service Buildin9

• No municipal or public drinking water supplies are taken from.Clinton Lake or downstream for 200 miles.ý Drinking water for Clinton Power Station is supplied by Clinton Lake.

1 sample from a control location**

• • No control location necessary CLINTON -- UNIT #1 Rev.22 - 12/09

-~Wi -- am ENO~

CY-CL-170-301 Revision 22 Page 145 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

3. WATERBORNE (continued)

d. Sediment from 1 sample from downstream area Semiannually Gamma isotopic analysise shoreline with existing or potential semiannually.

recreational value.

SECTOR CODE DISTANCE from station (miles)

SE CL-7B 2.1

4. INGESTION

a. Milk Samples-from milking animals Semimonthly When Gamma isotopice and 1-131 in 3 -locations within 5-km animalsare on analysis semimonthly when distance having the highest pasture, monthly at animals are on-pasture; dose potential. If there are ,other times monthly at other times.

none, 1 sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be in greater than-1 mrem per year. k,'

• This sample requirement is checked annually as part of the annual land use survey.

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CY-CL-170-301 Revision 22 Page 146 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

4. INGESTION (continued)

a. Milk 1 sample from milking animals (continued) at a control .locationj 1-5-30 km (9.3 miles to 18.6 miles) distant and in the least prevalent wind direction (c)

SECTOR CODE -DISTANCE from station (miles)

WSW (control) CL-116 14

b. Fish and 1 sample each of 3 important Sample in season, or Gamma isotopic analysise Inverte- species (such as bass, semiannually if they on edible portions.

brates crappie, carp, or bluegill) are not seasonal in vicinity of plant-discharge area.

SECTOR CODE DISTANCE from station (miles)

E CL-19 3.4 1 sample of same species in areas not influenced by plant discharge.,

SECTOR-. CODE DISTANCE from station (mile's)

S (control) CL-105l 50 CLINTON -- UNIT #1 Rev.22 - 12/09 owtw-f/4ý10,alfa

S - - -" IN&

an mW w m N *a -

CY-CL-170-301 Revision 22 Page 147 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND. TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION FREQUENCY OF ANALYSIS LOCATIONSa

4. INGESTION (continued)

c. Food Products 1 sample of each principal At time of harvestj Gamma isotopic analysise class of food products from on edible portion.

any area that is irrigated by water in which liquid plant wastes-have been discharged.*

• 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.

Samples of 3 different Monthly'during growing Gamma isotopice and 1-131 kinds of broad leaf season analysis.

vegetation (such as lettuce, cabbage, and swiss chard) grown nearest. each of two di fferent- offsite locations of highest predicted annual average ground-level .D/Q if milk sampling-is nOt performed.

SECTOR, CODE DISTANCE from station (miles)

NE CL-115 0.7 N CL-117 0.9 NNE CL-118 0.7 CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 Revision 22 Page 148 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY'- NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE. SAMPLES AND SAMPLE LOCATIONSa COLLECTION FREQUENCY OF ANALYSIS

4. INGESTION (continued)

c. Food Products 1 sample of each of the Monthly during growing .Gamma isotopice and 1-1-31 (continued) similar broad leaf vegetation- season grown 15Z30 km (9.3 miles to 18.6 miles) distant in the least prevalent wind direction(c) if milk. sampling is not performed.

SECTOR CODE DISTANCE from station (miles)

SSE (Control) CL-114 12 .5 CLINTON -- UNIT #1 Rev.22 - 12/09

- -w4~ ~ ~~o onk. - -/ -6

CY-CL-170-301 Revision 22 Page 149 of 195

.TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS aRefer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be. documented in the Annual Radioactive Release Report pursuant to Technical Specification 5.6.3. It is recognized that, at times, it may not be possible or practicable totcontinue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway'in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program given in the ODCM. Pursuant to-Technical Specification 5.5.1, identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next annual Radiological Environmental Operating Report an* also include in the report a revised figure(s) and table f6r the ODCM reflecting the new location(s).

bOne or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stations is not an absolute number. The number of direct radiation monitoring stations may be 'reduced according to geographical limitations; e.g.., at an ocean site, some sectors will be over water so that the number of dosimeters may~be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

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Revision 22 Page 150 of 195 TABLE 5..1-1 (Continued) j RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (Continued) 1 CThe purpose of this sample is-to obtain background information.

If it is not practical to establish control locations, in ,

accordance with the di.stance and wind direction. criteria,,-other sites that proyide valid background data may be substituted.

dAirborne particulate-. sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to. allow, for radon and thoron daughter decay. If gross beta activity in air particulate samples ,is greater than ten times the yearly'mean of control samples, gammaisotopic analysis shall:be-performed on the individual samples. - .

eGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. I fThe "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone.

I "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.

gA composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid (or time) and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

hGroundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic.

gradient or recharge properties are suitable for contamination.

The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in Section 2.4.2.

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CY-CL-170-301 Revision 22 Page 151 of 195 TABLE 5.1-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (Continued)

JIf harvest.:occurs more than once a-year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and-root food products.

k The dose;shall be calculated for the maximum organ and age group, ,using the methodology andparameters in Section 3.5.4.

1Where access to green leafy vegetables from'private gardens is not possible, non-edible plants with similar leaf characteristics from the same vicinity may be substituted..-

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CY-CL-170-301 Revision 22 Page 152 of 195 TABLE 5.1-2 REPO)RTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/l) OR GASES (pCi/m3) (pCi/kg, wet) (pCi/i) (pCi/kg, wet)

H-3 20, 000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400***

1-131 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 5b 20 2,000 70 2,000 Ba-La-140 200*** 300

• For drinking water samples. This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

• • If no drinking water pathway exists,-.a value of 20 pCi/l may be used.

• • • Total for parent and daughter.

CLINTON -- UNIT #1 Rev.22 - 12/09 oft - m w '60 M, (m , Aw anam #WCWo

- - - m am 4 CY-CL-170-301 Revision 22 Page 153 of 195 TABLE 5.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISa'b LOWER LIMIT OF DETECTION (LLD)c WATER AIRBORNE PARTICULATE 3 FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/i) OR GAS (pCi/m ) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry)

Gross beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15" 1-131 0.07 1 60 15 Cs-134 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 is 15

• If no drinking water pathway exists, a value of 3000 pCi/l may be used.

• • If no drinking water pathway exists, a value of 15 pCi/l may be used.

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Revision 22 Page 154 of 195 TABLE 5.1-3 (Continued) .

DETECTION FOR ENVIRONMENTAL SAMPLE ANALYSISab, TABLE NOTATIONS .

aThis list does not mean that only these nuclides are to.'be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report:

pursuant to Technical Specification 5.6.2. I bRequired detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, Rev. 1, July 1977.

CThe LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be S

detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66sb/[E V " 2.22 Y exp(-kAt)]

Where: I LLD is the "a priori' lower limit of detection as defined above, as picocuries per unit mass or volume, I Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E if the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, E 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec- 1 ), and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation.

CLINTON--UNIT #1 Rev.22 12/09 j

CY-CL-170-301 Revision 22 Page 155 of 195 It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori. (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

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CY-CL-170-301 Revision 22 Page 156 of 195 5.2 Land Use Census - Operation and Surveillance Requirements OPERATION REQUIREMENT A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location'in each I of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation. For'elevated or mixed-mode releases as

'I defined in Regulatory Guide 1.111, Revision 1, Juily 1977, the land use census shall also identify within a distance of 5 km (3 miles) the location in each-of the 16.

meteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad leaf vegetation.1 This requirement applies at'all times.

l REMEDIAL REQUIREMENT: 4

a. With a land use census identifying a location(s) that yields a.calculated.dose or dose commitment greater thanthe values .currently being'.calculated in Section 3.5;.2.l,'. identify the new location(s) in I

the next Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3..

'I

b. With a land use census identifying a location(s) that yields .a.calculated dose or dose commitment (via the same exposure pathway) 20 percent greateri than at a location from which samples are currently being obtained in accordance with Section 5.1, add the new location(s) to the radiological.

environmental monitoring program within 30 days.

The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure.

pathway, may be deleted from this monitoring program after October 31 of the year in which this,!and use census was conducted. Pursuant to Technical Specification 5.5.1, identify the new location(s) in the next Radioactive Effluent Release Report and also include in the-report a revised figure(s) and table for this manual reflecting the new location(s).

• Broad leaf vegetation sampling of at least-three different kinds of vegetation may be performed at the site boundary in each of two' different'direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.1-1.4c shall be followed, including analysis of control samples.

a CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 157 of 195 SURVEILLANCE REQUIREMENTS 5.2.1 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the annual Radiological

_Environmental Operating Report pursuant to Technical Specification 5.6.2.

5 .3 Interlaboratory Comparison Program ACorporate approved, Fleet wide Vendor performs all analyses for the CPS Radiological Environmental Monitoring Program.

The Fleet wide Vendor shall participate in a interlaboratory comparison. (cross-check) program to demonstrate compliance vtith,a-.Quality Control Program.

Programsthat will have been operated by agehcies that supplies environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing laboratory but nottto lth6 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.

Participant laboratories measure the cbncentrations of specified radionuclides and report the.m to the issuing laboratory. Several months later, the issuing laboratory reports the known values to the particdipant:laboratories and specifies the range the results should fall within.

Results consistehtly higher or lower than the known values and results outside.the specific ranges indicate a need to check the instruments or procedures used.

If the results of a determination in the cross-check program are outside the control limits specified, CPS will require the Vendor t'o investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report. .

Operation and Surveillance Requirements for the Interlaboratory Comparison Program are prescribed in Section 5.3.1 (which follows).

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CY-CL-170-301 I

Revision 22 Page 158 of 195 5.3.1 Interlaboratory Comparison Program - Operation and Surveillance Requirements OPERATION REQUIREMENT Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that corresponds to samples required by Table 5.1-1.

This requirement applies at all times.

REMEDIAL REQUIREMENT:

II

a. With analyses not being performed as required above, report-thieacorrective actions taken-to.prevent a recurrence to the Commission in the. Annual II Radiological Environmental Operating Report pursuant to TechnicaaI Specification 5.6.2._:

SURVEILLANCE REQUIREMENTS 5.3.1.1 The Interlaboratory Comparison Program is described in Section 5.3. A summary.of the. results, obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological ,I Environmental Operating Report pursuant to Technical Specification 5.6.2.

I II I

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CY-CL-170-301 Revision 22 Page 159 of 195 FIGURE 5.0-1 REMP LOCATIONS WITHIN 1 MILE OF CPS CLINTON -- UNIT #1 Rev.22 -

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I CY-CL-170-301 Revision 22 Page 160 of 195 i

FIGURE 5.0-2 I

REMP LOCATIONS 1-2 MILES FROM CPS II I

I I

I I

U I

I I

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CY-CL-170-301 Revision 22 Page 161 of 195 FIGURE 5.0-3 REMP LOCATIONS 2-5 MILES FROM CPS CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 162 of 195 FIGURE 5.0-4 REMP, LOCATIONS GREATER THAN 5 MILES FROM.-CPS CLINTON -- UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 UPage 163 of 195 3 6.0 BASES FOR OPERATION AND SURVEILLANCE REQUIREMENTS 6.1 General:Operation and Surveillance:Requirements The requirements of Sections 1.2 and 1.3 provide general requirements applicable to each of the Operation I*Requirements and Surveillance Requirements specified within Sections 2.0 through 5.0.

1.2.1 This requirement is provided to emphasize when

,i each Operation Requirement is applicable and when the associated REMEDIAL REQUIREMENT should be.met.

,1.2.2 This requirement'defines,.those conditions

• ,: necessary to constitute compliance:,with the terms of an individual Operation Requirement and-associated REMEDIAL REQUIREMENT.'

S1."3. 1 This "requirement pro0ides, that surveillance activities, necessary.to.ensure the-Operation

. Requirements are met, will.' be performed during the conditions 'for which Oh~iOperation Requirements are applicable./. Some surveillance activities may be required

..,to be performed without regard-ltb the applicable

.conditions specified in the associated Operation

'Requirement.

1.3.2 The provisions of this requirement provide

-.'alowable tolerances for..performing surveillance activities beyond those specified inv the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.. The phrase "at least"

.,associated with~a surveillance frequency does not negate thi's allowable tolerance; instead, it permits the more frequent performance of surveillance activities.-

'The tolerance values, taken either individually or

cos6ýtielyove treetes 'intervals, are sufficiently restrictive~to ensure that thereliability associated wi~ththe surveiilance-activity is'not significantly degraded beyond that obtained from the nominal specified 5interval.

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Revision 22 Page 164 of 195 1.3.3 The provisions of this requirement set forth the criteria for determination of compliance with .the OPERABILITY requirements of the Operation Requirements.

I Under these criteria, equipment, systems,. Or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed,:within the I

specified time interval. Nothing in this provision is to be construed as defining equipment, systems.or components OPERABLE, when ,such items are found or known to .be I

inoperable although still meeting the. Surveillance Requirements.* ..

6.2 Monitoring. Instrumentation II Section 2.7: Radioactive Liquid Effluent Monitoring Instrumentation. . .

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

I The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in this manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10CFR Part 50. 3 Section 3.9.1: Offgas Radiation Monitoring Instrumentation i The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is I

consistent with 10CFR Part 50, Appendix A, General Design Criteria 19, 60, 61, 63 and 64.

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CY-CL-170-301 Revision 22 Page 165 of 195 Section 3.9.2- Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as appl'icable, the releaselof radioactive-materials in gaseoU's'effluents during actual or potential releases of-gaseous -effluents.

The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in thins manual to'ensure that the alarm/trip will occur prior to exceeding the-limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64-of Appendix A to 10CFR Part 50. The sensitivity of any noble gas activity monitors- used to show compliance with the gaseous effluent release requirements of Section 3.5.1 shall be such that concentrations as low as 1 x 10- gCi/ml are mea.surable.

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Revision 22 Page 166 of 195 6.3 RadioactiveEffluents 3 6.3.1 Liquid Effluents Section 2.3.1: Liquid Effluent Concentration, This requirement is provided to ensure that the concentration of radioactive materials released. in liquid waste effluents to UNRESTRICTED AREAS will be less than 1

ten times the concentration levels specified in 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of,.

radioactive materials in bodies of water in'UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of IOCFR Part I

20.1301 to-the'population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that'Xe'135 is the controlling radioisotope "

and its. ECL in air .(submersion) was converted to an equivalent concentration in,.water using the methods described in International Commission on Radiological Protection (ICRP) - Publication 2.

I This requirement applies to the release of radioactive materials in liquid effluents from the site. I The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms I

of the lower limits of detection (LLDs) Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection:

Definition and-Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"

5 NUREG/CRZ4007 (September 1984), and in-the HASL Procedures-Manual, HASL-3.00 (revised.annually).

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CY-CL-170-301 Revision 22 Page 167 of 195 Section 2.4.1: 10CFR50, Appendix I Dose Limits This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A Of Appendix I to assure that'the releases of radioactive material'in liquid effluents to UNRESTRICTED AREAS will be kept "as low as

,is reasonably achievable." Also, for fresh water sites

.with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in.radionuclide concentrations in the finished drinking water that are in excess, of the requirements of

• 40CFRPart 141. The dose calculation methodology and parameters in this manual implement the requirements in Section III.A of Appendix I that~conformance with the guides of Appendix I 'be shown by calculational procedures based on models and data, su6h'*:that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is

'unlikely to be substantially.underest'imated. The equations specified in this manual for calculating the doses due to the actual release rates of radioactive materials,'in liquid effluents are consistent with the methodology provided in RegulatoryGuide .1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effl~uents for the Purpose .of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.1.13, "Estimating Aquatic; Di~spersion of Effluents from Accidental and Routine Reac~tor Releases for the Purpose of Implementing Appendix I," April 1977.

This requirement applies to the release of radioactive materials in liquid effluents from the one reactor unit on the site.

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Section 2.5.1: Liquid Radwaste Treatment <System I The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use

.whenever liquid effluents require treatment prior to I

release to the environment. The requirements that the appropriate portions of this system be used when.

specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10CFR Part 50.36a,..:General Design Criterion 60 of Appendix A to 10CFR .Part 50 and the design objective given in Section II.D of appendix I to 10CFR Part 50. The specified limits governing* the use of appropriate p6rt'ions of the liquid radwaste treatment system were specified as a suitable fraction 'of the dose S

design objectives set forth in Section II.A '6f Appendix I, 10CFR Part 50,1 for liquid effluents.

This requirement applies to the release of radioactive

,l materials in liquid eff.luents, from the one, reactor unit on the site. I II II U

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CY-CL-170-301 Revision 22 Page 169 of 195 6.3.2 Gaseous Effluents Section 3.4.1: Tech Spec Release Rate-Limits This requirement is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY'from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR Part 20 t0 UNRESTRICTED AREAS,. The annual dose limits are the doses associated with the concentrations of 10CFR Part'20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF

°THE.PUBLIC in an UNRESTRICTED AREA, either within or

ýoutside the SITE BOUNDARY, to annual average concentrations exceeding the limits: specified in Appendix B, Table 2 of.10CFR Part 20' For MEMBERS OF THE PUBLIC who may at *times.be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate'for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of such MEMBERS OF THE PUBLIC, with the appropriate occupancy,'factors Ishall be given in this manual. Doses for such MEMBERS OF THE PUBLIC are provided in the Radioactive Effluent Release Report. The specified release rate limits restrict, at all times, the corresponding gamma and-beta dose rates above background to a MEMBER OF THE PUBLIC, at or-beyond the SITE BOUNDARY, to less than or equal to 500 mrem/year to the whole body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

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Revision 22 Page 170 of 195 This requirement applies to the. release of radioactive materials in gaseous effluents from the one reactor unit on the site.

The required.detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in Currie, L. A., "Lower Limit of Detection:

I Definition.land Elaboration of a Proposed Position for Radiological Effluent .and Environmental Measurements,"

NUREG/CR-4.007,(September 1984), and in the HASLI Procedures Manual, HASL-300 (revised annually).

Section 3.5.1: Noble Gas Dose I This requirement is provided to implement the requirements-of.Sections II.B, III.A and IV.A of Appendix I, 10CFR Part 50.:*: The Limiting Condition for Operation implements the-guides set forth in Section II.B~of Appendix I. The ACTION statements provide the required operating flexibility and.,at the. same time implement the

-guides set forth.. in,Section IV.A of Appendix.I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as-low as is reasonably achievable." The Surveillance' Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such I

that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation I

methodology, and parameters established in this manual for calculating the doses due to the actual release rates forI radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from I

Light-Water Cooled Reactors" Revision:l, July 1977.

This requirement applies to the release of radioactive materials in gaseous effluents from the site. I I

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CY-CL-170-301 Revision 22 Page 171 of 195 Section 3.5.2: Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form This requirement is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10.CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in.Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low 'as is reasonably achievable.". The calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that. COnformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that,.the actual exposure of a MEMBER OF THE. PUBLIC through-appropriate pathways is unlikely to be substantially underestimated. The calculational methodology and parameters for calculating the doses..due to the:actual re'lease.:rates of the. subject materials are consistent-vwith the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October::1977 and.Regulatory Guide 1i.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous-Effluents in Routine Releases from, Light-Water Cooled Reactors" Revision 1, July 1977. These equations also provide for determining the actual doses based upon the annual average atmospheric conditions..: The release rate-specifications for iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these 'calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation:with subsequent consumption.by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with" subsequent exposure of man.

This requirement applies to the release of radioactive materials in gaseous effluents from one reactor unit on the site.

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Page 172 of 195 Sections 3.6 and 3.7-: Gaseous Radwaste (Offgas) Treatment and Ventilation Exhaust Treatment System The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the I

systems'will'be available for use whenever gaseous effluents require treatment prior to release to the environment. The.requirement that the appropriate I

portions of these systems be used, when specified, provides:reasonable assurance that the releases;of radioactive materials in gaseous effluents will be kept I "as low as reasonably achievable." This requirement implements the requirements of 10CFR Part 50 36a,:.General Design Criterion 60 of Appendix A to. 10CFR Part 50 and the design objectives given in Section II..D. of Appendix I iI to 10CFR Part:.50.. The specified limits governing-the use of appropriate portions of the systems were' specified as a suitable fraction of the dose design objectives set I

forth in Section II.B and II.C,of Appendix I,, 10CFR Part 50, for gaseousjeffluents. i This requirement:applies to the release of radioactive materials in gaseous effluents from the oneereactor unit on the site. , I I

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CY-CL-170-301 Revision 22 Page 173 of 195 6.3.3 Total. Dose.

Section 4.1: Total Dose This requirement is provided to meet the dose limitations of 40CFR Part 190 that have been' incorporated into

• 10CFR2:0.1301. Dose monitoring requirements of 40CFR190 may be met through direct measurement (i.e.,' TLDs'),

determined from survey measurements, or calculated from shielding codes. CPS determines the 40CFR190 dose through calculation and by use of TLDs maintained and reported on as part of the Radiological Environmental Monitoring Program (REMP). The requirement requires the preparation and submittal of a Special:Report whenever

.- the calculated doses from plant generated radioactive effluents and direct'radiation exceed 25 mrem to the total .body or any organ, except the thyroid, which shall be limited to less than or equal to. 75 mrem. For sites containing up to 4 reactors; it ishighly unlikely that the resultant dose to a MEMBER OF-THE'PUBLIC will exceed the dose limits of 40CFR Part 190 if the individual reactors remain within twice the) dose design objectives of Appendix I; and if direct radiation doses from the reactor units and outside storage tanks are kept small.

The Special Report will describe a course of action that should result in the limitation of the annual dose to a

-MEMBER OF THE PUBLIC to within the 40CFR Part 190 limits.

For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycles sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR Part 190 have not already been corrected), in accordance with the provisions of 40CFR

.Part 190.11 and 10CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits-of 40CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10CFR Part 20, as addressed in Sections 2.3 and 3.4. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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CY-CL-170-301 Revision 22 Page 174 of 195 6.4 Radiological Environmental Monitoring I Section 5.1: Monitoring Program

• The radiological environmental monitoring program required by this requirement provides representative I

measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of l

MEMBERS OF THE. PUBLIC resulting from the.station..

operation. This monitoring program implements Section I IV.B.2 of Appendix I to 10CFR Part 50 and thereby supplements~the radiological effluent monitoring program by verifyingothat.the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluentý measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is. provided by: the Radiological Assessment Branch I

Technical.Position on Environmental Monitoring, Revision 1, November 1979.-: The.%initia:lly specified.monitoring program will be effective!for at. leastthe first three l

years of commercial operation. Following this period, program changes.,may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by.Table 5.1-3 are considered optimum for routine environmental measurements in industrial laboratories.. It-should be recognized.,that the LLD is defined as an-a priori (before the fact) limit representing the. capability.-of a-.

measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

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CY-CL-170-301 Revision 22 Page 175 of 195 Section 5.2: Land Use Census This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to' the radiological environmental monitoring program are made if required by theresults of this census. The land use census shall be performed using the best informationavailable (e.g., a

,door-to-door survey, from aerial surveys, questionnaire, or ,from consulting with local agricultural authorities).

This.census satisfies the requirements of-Section IV.B.3 of Appendix I to 10CFR Part 50. 2Restricting the census togardens of'greater than 50 m provides assurance that significant, exposure pathways via leafy Vegetables will

. *be;identified and monitored since a garden of this size is the minimum required *to produce 'the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide i.1.09 for consumption by a' child.- To determine this minimum g'arden size, the'foi'lowin-'assumptions were made:

(1) 20% of the garden 'was u'sed for.growing broad leaf vegetation .(i.el., similarlY'tolettuce and 'cabbage) and (2) a vegetation yield of:2 kg/M2 .

Section 5.3.1: Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on' the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program

• for environmental monitoring in order t0:.demonstrate that the' results. are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR-Part 50.

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Revision 22 Page 176 of 195 7.0 REPORTING REQUIREMENTS 3 7.1 Annual Radiological Environmental Operating: Report Routine Radiological Environmental Operating Reports covering the operation of the unit duringthe previous calendar year shall be submitted prior to May 1 of each year pursuant toTechnical Specification 5.6.2. .

The Annual Radiological Environmental Operating Reports shall include the following information:

1. Summaries, interpretations, and an analysis of trends of the-results of the radiological, .

environmental surveillance activities< for-the report period, including a comparison with preoperational I

studies, with operational controls as appropriate, and with-previous environmental surveillance reports, and an assessment of-the observed impacts U

of the plant operation on the environment.

2. The results of landuse censuses- required by Section 5.2.

3. Results of,.:analysis of all radiological environmental:samples and of all environmental radiation measurements taken during the period pursuant to-the locations specified in the Tables and-Figures in this manual, as well as summarized and tabulated results of--these analyses and measurements in the format of the-tablein the Radiological Assessment Branch Technical Position, I

Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as

-,soon as possible in a supplementary report.

4. A summary description of the radiological environmental monitoring program.

5. At least, two legible maps-* covering all sample locations keyed to a table giving distances and directions from the HVAC stack.

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• One map shall cover stations near the site boundary and a second map shall include the more distant stations.

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CY-CL-170-301 Revision 22 Page 177 of 195

6. The results of licensee participation in the Interlaboratory Comparison Program, required by Section: 5.3.1.

7. Discussion of all deviations from the sampling

-schedule of Table 5.1-1.

8. Discussion of all analysis in which'the LLD required by Table 5.1-3 was not achievable.

7.2 Radioactive Effluent Release Report Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted by May 1 of each year pursuant to Technical Specification:5.6.3.

The Radioactive.;Effluent Release"Report shall include the following information-

1. A summary of the quantities of radioactive liquid and gaseous effluents'and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and GaseOus:Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendixf B thereof. For solid wastes, the format for Table.3 in Appendix B shall be supplement'ed with 3 additional categories:

• class of solid wastes (as defined by*10CFR Part 61),

• type of container (e.:g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g.; cement, urea formaldehyde).

2. The following information for each class of solid waste (as defined by 10CFR Part 61) shipped offsite during the report period:

a. Total container volume,

b. Total curie quantity (specify whether determined by 'measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Source of waste and processing employed (e..g.,

dewatered spent resin, compacted dry waste, evaporator bottoms).

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CY-CL-170-301 Revision 22 Page 178 of 195

3. A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive

materials in gaseous and liquid effluents made during the reporting period.

4. Ajlisting of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Section 5.2.

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5. Changes to the ODCM pursuant to Technical Specification 5.5.1. I

6. Major changes to radioactive liquid, gaseousj,'and solid waste treatment systems . The discussion of each change shall contain:

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a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR Part 50.59.

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b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental I

c.

information; A detailed description of the equipment, components and processes involved and the I

interfaces with other plant systems;

d. An evaluation of the change, which shows the I predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and I

amendments thereto;

e. An evaluation'of the change, which shows the expected minimum exposures to a MEMBER OF THE I

PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application I

and amendments thereto; U

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CY-CL-170-301 Revision 22 Page 179 of 195 fl. A comparison of the predicted releases of radioactive materials, in liquid'and gaseous effluents and in solid waste, to the actual releases for the period:prior *to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable.- by the Plant Operations Review Committee.(PORC)..

Licensees may choose to submit the information called for in this requirement Changes as part of its annual USAR';update.'

described by this requirement shall become effective upon review by the PORC.

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7. An annual summary of hourly meteorological data I collected over the previous-year. This annual summary may be either in.the form of an hour-by-hour listing onmagnetic tape of wind speed, wind direction,. atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

8. An assessment of the radiation doses due to the radioactive liquid and gaseous effluents reieased from the unit or station during the previ6us' I

calendar year. Beta and gamma air*dose due-to the release of noble gas in gaseous effluents is calculated at the CPS site boundary in each of the I

16 geographical directions surrounding CPS. Dose due to the release of radioactive iodines and particulates in gaseous effluents is calculated at the critical receptor location in each of the 16 geographical sectors surrounding CPS to a distance of 5 miles. Dose summaries based on these I calculations are provided in the Radioactive Effluent Release Report. 3

9. An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 2.1-1 and 3.1-1) during the report period.

Note:

All assumptions used in making the following assessments, i.e., specific activity, exposure time and location, shall be included in these reports. Annual average meteorological conditions or meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurements, may be used for determining the gaseous pathway doses. The assessment of radiation I

doses shall be performed in accordance with the methodology and parameters in this manual.

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CY-CL-170-301 Revision 22 Page 181 of 195 10... An assessment of radiation doses to the likely most

.exposed MEMBER OF THE PUBLIC'from reactor releases and other nearby uranium fuel cycle's urces, including doses from primary effluent pathways and

.direct radiation, for the previous calendar year to

show conformance with .40CFR Part 190, Environmental Radiation Protection Standards for,.Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide'1.109, Rev. 1 October 1977 CLINTON -- UNIT #1 Rev.22 -

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8.0 ADJUSTMENT OF THE CPS ODCM METHODOLOGY I Consistent with the NRC Commissioners' opinion on 10CFR50 Appendix I dated April 30, 1975, CPS will use environmental monitoring data to improve dose i

calculational- models and to request CPS ODCM:changes on the basis of such operating experience data. Such adjustments-are recognized as being especially, important U

for the radioiodine-milk pathway where conservative regulatory guide assumptions have been made.- By using environmental monitoring data, uncertainties associated I with plume behavior, radioiodine chemical form; deposition and retention of forages, and milk consumption patterns may, oe- circumvented or. reduced.. - I I

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CY-CL-170-301 Revision 22 Page 183 of 195 9.0 ATMOSPHERIC TRANSPORT AND DISPERSION MODEL:

9.1 Introduction The atmospheric transport and dispersion model~used by AmerGen Energy Company LLC is a. straight-line, sector-averaged Gaussian model designed to estimate average relative concentrations at various receptor points.

The model was developed in accordance-with routine

%releaseanalysis procedures specified by Regulatory

Guide 1'.111 (Revision 1 July.1977), Section C.l.c "Constant Mean Wind Direction Model's".

All meteorological and dose calculations prescribed in this manual are based on meteorological data concurrent with the time of release or the annual average values.

Near-real time meteorological data processing is described in Section 9.2.

9.2 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 four output arrays are generated for each dose receptor location as follows:

0 Relative undecayed, undepleted plume concentration (X/Q) 0 Relative decayed and depleted radioiodine and particulate concentration (D2DPXQ) [8 day decay]

0 Relative decayed noble gas concentration (DlXQ)

[2.26 day decay]

0 Relative particulate and radioiodine deposition (D/Q)

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Revision 22 Page 184 of 195 I

Since the Regulatory Guide 1.111 depletion .and deposition curves are defined only within the range I

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, 9.2.1 Determination of Pasquill Stability Class The Pasquill Stability Class is determined by I categorizing the temperature gradient, AT; into one of several ranges between -0.900 and 0.900 °C/meter according to:the following equation: I where AT = (TU - T,.)/(Hu 'HL), °C/meter (1)

I T= Meteorological (met)f tower upper leVel temperature, oC i

TL = Meteorological tower lower level temperature, °C I Hu = Meteorological tower upper level instrumentation

=

height 60 meters', I HL =

=

Meteorological tower level instrumentation height 10 meters I AT is then classified according tolthe following scheme: I Pasquili Stability' Defining Condition A (Extremely Unstable)

B

-0.900 <

-0..019 <

AT AT

< -0.019

< -0.017 I

C D (Neutral)

-0.017 <

-0.015-<

AT AT

< -0.015

< -0.005 U E -0.005 <A T < 0.015 G (Extremely Stable) 0.015, < AT <

0.040 < AT <

.0.040 0.900 U

Invalid AT < -0.900 or AT > 0.900 I

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CY-CL-170-301 Revision 22 Page 185 of 195 9.2.2 Calculation of *Stack Height Wind Speed The wind speed at the release point (HVAC Exhaust Stack or Standby Gas Treatment System Exhaust Stack) height, STACWS, is calculated using the expressions:

STACWS = WSPU (STACKH/Hu)P, meter/sec (2) where WSPu = Upper met tower level wind speed, meter/sec WSPL = Lower met tower level wind speed, meter/sec STACKH = Physical release point stack height P = Wind power law exponent, 0.25ý for stabilities A, B, C; 0.33 for stability D; 0.5 for stabilities E, F, G, dimensionless. These coefficients come from The Recommended Guide for the Prediction of the Dispersion of.Airborne Effluents, May 1968.

All other parameters are as defined for equation (1).

9.2.3 Determination of Release Mode and the Entrainment Coefficient The mode of release can be elevated, ground or mixed; the latter being a combination of the first two. The mode of release, as well as an entrainment coefficient, TCORR, are determined from the stack, height, STACH, building height, BLDGHT, stack exit velocity, EXITV, and wind speed at the stack height, .STACWS.

For effluents exhausted from release points that are

.. higher than twice the height of adjacent solid structures, STACKH > 2'(BLDGHT), TCORR = 0.0 (3) the release is considered completely elevated and the entrainment coefficient is zero. For effluents released from points less than the height of adjacent solid structures, a ground-level release is assumed STACKH < BLDGHT, TCORR = 1.0 (4) and the entrainment coefficient is unity. For effluents released from points or vents at the level of, or above, adjacent solid structures, but lower than elevated release points, CLINTON--UNIT #1 Rev.22 -

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Revision 22 Page 186 of 195 2(BLDGHT) > STACKH > BLDGHT the release is treated as elevated, ground or mixed (5) 3 according to the following relationships:.3 ELEVATED: TCORR = 0.00 if EXITV >5(STACWS) (6)

GROUND: TCORR = 1.0 if EXITV < STACWS (7)

MIXED: TCORR = 0.30-0.06(EXITV/STACWS) if 5(STACWS) > EXITV > 1.5 (STACWS)

(8) 3 TCORR = 2.58-1.58(EXITV/STACWS) if (9) 1.5(STACWS) > EXITV > (STACWS)

In the mixed mode, the release is considered to occur as an elevated release 100 (I-TCORR) percent of the time and as..*,aground release.100 (TCORR)-per.cent of the time. Eachobf these cases are then evaluated separately and, the concentration X/Q. calculated I

according to the fraction,- of-,the-.time each release occurs.

9.2.4 Calculation of Vertical Standard Deviation The vertical plume spread (vertical standard deviation), oz is a function of the distance from the I

release point to:thereception point for.a given Pasquill-stability class. The numerical value of (z is obtained'by linear interpolation of the. values in the I

following table which are taken from Regulatory Guide 1.145: "-

TABLE 9.2-1 Distance Gz Values Stability Class 3

(meters)

A B *C D E F G 200 31 '21 15 10 6 4 3 500 120 55 34 19 13 8 5 1000

-2000 3000 530 1000 1000 124 340 800 64 120 170 32 52 68 21 34 44 13 20 25 8

13 16 I

'6000 1000 100-0 300 '110 71 35 23 10000 1000 1000 450 147 85 45 28 30000 1000 1000 1000 275 130 65 40 50000 1000 1000 1000 350 155 75 50 80000 1000 1000 1000 460 180 85 55 The values in this table are limited by the "mixing height lid" which is specified at 1000m.

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CY-CL-170-301 Revision 22 Page 187 of 195 9.2.5 Calculation of the Building Wake- Correction For ground-based and mixed-mode releases, an adjustment is made in the calculation of X/Q that takes into consideration initial mixing of the effluent plume within the building wake. This adjustment is an additional factor added in quadrature to the vertical plume spread equation (10):

I [oz2 + 0.5 (BLDGHT) 2/7r] (10) with the requirement that 1, is restricted to values YEz: < (3) ((z77; (i 9.2.6 cal.ulation of Momentum Plume Rise.,

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 classes A,B,C. andD, AH is calculated per section 9.2.6.1; for classes-E,F and G, section 9.2.6.2 is used.

9.2.6.1 AH For Pasquill Class A,B,C and D AH is calculated using both equations (12),and (13) and the minimum value is selected for use.

AH, = 1.44(STACD) (EXITV/STACWS)2/ 3(X/STACD)1/ 3 (12)

AH2 = 3.0(STACD),(EXITV/STACWS), meter (13) where STACD = Internal release point stack diameter

= 3.77 meters (HVAC Exhaust Stack)

= 0.44 meters (SGTS Exhaust Stack)

EXITV = Stack exit velocity, meter/second X = Distance to specified receptor, meter All other parameters are as defined previously.

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Revision 22 Page 188 of 195 9.2.6.2 AH For Pasquill Class E,F and G AH is determined by selecting the minimum value calculated by equations (12) and (13) above and equations (14) and (15) below:

AH 3 = 4.0[(0.5(EXITV) (STACD)) 2 /S]Y, meter (14)

AH 4 = 1.5 [(0.5(EXITV) (STACD))

meter 2,/STACWS]I 1 3

/ (S- 1 6

/ ,

(15) 3 where S Restoring acceleration per unit vertical displacement for adiabatic motion, sec-2

= 9.8"* Tz/(273+Tar b)

T T,

="0.025 0

= 0.05 (E stability - default value)

(F stability - default value)

I T, = 0.075 (G stability - default value)

Where Ta* = Ambient air temperature (°C) [If temperature is missing, the defaultvalue will be used]

All other parameters are'as defined in section 9.2.6.1.

9.2.7 Calculation of 'the Effective Plume Height The effective plume height, H, is determined using section 9.2.6 results for the momentum plume rise, AH, I and the terrain height, TERAIN:

H = STACKH + AH - TERAIN, meter (16) where TERAIN Difference between the plant base-height above mean sea level (MSL) and the. receptor point height above MSL, meter >0.0.

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CY-CL-170-301 Revision 22 Page 189 of 195 9.2.8 Determination of Affected Sectors The wind direction for the hour determined which sector will be affected. Sectors are 22.50 arcs and are classified according to the following scheme:

TABLE 9.2-2 WIND DIRECTION TABLE Sector Compass Wind Direction (WD)

Number DirecticDn 1 N 0.00 < WD < 11 .250 or 348.750 < WD < 360.000 2 NNE 11.25.0 < WD < 33.75° 3 NE 33.750 < WD < 56.250 4 ENE 56.250 < WD < 78.750 5 E 78 .750 WD< 101.250 6 ESE 101.250 < WD < 123 .750 7 SE 123.750 , WD ,< 146.250 8 SSE 1,46. 25° < WD.< 168.750 9 S 168.750 < WD < 191.250 10 SSW 191.250 < WD < 213 .750 11 SW 213 .750 < WD .< 236.250 12 WSW 236.250 < WD < 258 750 13 W 258.7505 < WD< 281.250 14 WNW 281.250 < WD < 303.750 15 NW 303.750 < WD., < 326 .250 16 NNW 326.250 < WD < 348 750 For elevated releases, the wind speed at the upper met tower level is used; ground releases use the speed of the wind at the lower met tower level. The wind direction is the same at both levels. During periods of calm wind, the wind speed is set at 0.5 meters/second the anemometer threshold value and assigned the directibn measured for the hour.

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9.2.9 Calculation of Depletion and Deposition Factors The depletion, DPF, and deposition, DPSF, factors are I

taken from the tables below which have been derived from curves found in Regulatory Guide 1.111,. Both the DPF and DPSF values depend on the effectiv.e plume I

height, H, the stability class, S, and the ýdistance, X, to the receptor.

I The Regulatory Guide 1.111 curves represent plumes that are 100, 60, 30, and 0 (ground-level) meters above the ground. For plume heights and receptor distances other than those listed, the factors are interpolatea from I

the tables. The model assumes that, after-fulll plume rise is achieved, the plume cannot get. 'higher from the ground. The derivation of these curves assutmed no I

change in terrain height with downwind,'disltance.. Since topography does change with distance,, as does :the vertical distance between the, plume centerline and the I

ground, use more than one depletion or deposition value as the plume travels away from .the plant with distance.

TABLE 9.2-3 I

Height of Pasquill DPF - DEPLETION FACTORS FROM FIGURES 2THROUGH 5 OF REGULATORY GUIDE 1.111 Distance (meters) ._ _

I Release Stability 200 I

500 1,000 2,000 3,000 6,000 10,000 30,000 50,000 80,000 (W) Class ....

Ground All 0.970 0.936 0.900 0.860 0.832 0.770 0.714 0.590 0.517 0.440 30 A,B,C, 0.990 0.964 0.935 0.900 0.875 0.828 0.793 0.680 0.590 0.478 30 D 1.000 0.985 0.960 0.920 0.900 0.850  : 0.810 0.707 0.650 0.593 30 60 60 E,F,G AB,C D

1.000 1.000 1.000 1.000 0.985 1.000 1.000 0.967 1.000 1.000 0.942 0.970 1.000 0.928 0.950.

1.000 0.878 0.910 0.970 0.839 0.870

'0.792 0.700

0:767 0.664 0.617

.0.707 0.546 0.500 0.646 I

60 EF,G 1.000 1.000 1.000 1.000 1.000 1.000 J1.000. 1.000 .1.000 0.977 100 100 100 ABC D

EF,G 1.000 1.000 1.000 1.000 1.000 1.000 0.978 1.000 1.000 0.950 0.989 1.000 0.932 0.982.

1.000 0.885' 0.946 1.000 0.850

'0.910

.1.000 0.725 0.807 1.000 1.0.628 0.746 1.000 0.500 0.685 1.000 I

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- m m- m - m -u m -n CY-CL-170-301 Revision 22 Page 191 of 195 TABLE 9.2-4 DPSF - DEPOSITION FACTORS FROM FIGURES 6 THROUGH 9 OF REGULATORY GUIDE 1.111 (M*e)* ,

Height of Pasquill - ___Distance (meters) _ -_ _ :_ "

Release (m) Stability Class 200 500 1,000 2,000 3,000 6,000 10,000 30,000, 50,000 80,000 Ground All__ 1.25E-04 8.OOE-05 5.40E-05 3.20E-05 2.60E:05 1.50E-05 9.90E-06 4.50E-06 3.OOE-06 2.OOE-06 30 A,B,C, 11OE--04 '8.00E-05 4.20E-05 2.40E-05 1.80E&05 1.10E:05 8.OOE-06 4.80E-06 4.OOE-06 3.50E-06 30 D 5.50E-06 4;OE-06 4.80E-05 3.OOE-05 2.40E-05 1.30E-05 8.OOE-06 3.40E-06 2.30E-06 1.60E-06 30 E,F,G 1.00E-11 1.00E-10 1.OOE-09 1.00E-08 LOOE-07 2.OOE-06 6.30E-06 8.80E-06. 5.30E-06 3.OOE-06 60 A,B,C 1.80E 4.40E-05 3.80E-05 2.40E-05 1.80E-05 1.10E-05 8.20E-06 5.OOE-06 '4.20E-06 3.50E-06 60 D 2.80E-07, 5:50E-06 1.60E-05 2.OOE-05 1.80E-05 1.30E-05 8.90E-06 3.60E-06 2.50E-06 1.70E-06 60 E,F,G 1.OOE-14 1.OOE-13 1.00E-12 1.OOE-11 -O1.OE-10 1.00E-09 1.OOE-08 1.60E-08 2.OOE-07 6.80E-07 100 A,B,C 4.OOE-06 2.60E-05 3.30E-05 2.40E-05 1.70E-05,. 1.10E-05 8.10E-06 5.OOE-06 4.50E-06 3.70E-06 100 D 1.OOE-08 2.60E-07 2.50E-06 .9.OOE-06 - 1 OE-05 1.00E-05 7.50E-06 3.90E-06 2.80E-06 1.90E-06 100 E,F,G 1.OOE-15 1.OOE-15 1.OOE-18 1.00E-15 -! l.00E-i5 1.OOE-15 1.OOE-15 1.OOE-15 1.OOE-15 1.OOE-15 CLINTON -- UNIT #1 Rev.22 - 12/09

CY-CL-170-301 Revision 22 Page 192 of 195 9.2.10 Ground Level X/Q, D2DPXQ, DIXQ, D/Q Analysis 9.2.10.1 Undecayed, Undepleted Plume Relative Concentration, X/Q The atmospheric concentration of effluent: at ground level, normalized by the source term Q, is given by the following equation:

X/Q = 2.032(TCORR)/WSPL(X)Amin, sec/M3 (17) where Amin =.The lesser of the two value'slobtained by equations (10) and (11), meter 2.032 .=The constant (2/7) divided by the width in radians of a 22.50 sector ('i.e., R/8, dimensionless X = Distance between release point to receptor, 9.2.10.2 Decayed, Depleted Radioiodine.,and Particulate Relative Concentration, .-D2DPXQ The decayed, depleted radioiodine concentration, D2DPXQ, is calculated in accordance with the following equation:

D2DPXQ = DPF(DC2)X/Q, sec/M3 (18) where DPF = The depletion factor calculated per section 9.2.9, dimensionless DC2 = The radioiodine 8 day decay factor, dimensionless exp[-0.693 (X)/t<<(WSPL)]

exp[-0.693(X)/(8 day)(24 hr/day) (3600 sec/hr) (WSPL)]

- exp[-i.00E-06(X/WSPL)]

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CY-CL-170-301 Revision 22 Page 193 of 195 9.2.10.3 Decayed Noble Gas Plume Relative Concentration, D1XQ The decayed noble gas plume relative concentration, DlXQ, is calculated in accordance with the following equation:

DCi 3 D1XQ = (X/Q), sec/m (19) where

, DCl = The noble gas decay factor, dimensionless

= exp [-0.693(X)/t<<(WSPL)]

. exp [-0.693(X)/(2.26 day) (24 hr/day)

.(3600 sec/hr) (WSPL)]

= exp [-3.55E-06 (X/WSPL)]

9.2.10.4 Radioiodine and Particulate Relative Deposition, D/Q The relative deposition for radioiodines and:

particulates, D/Q is calculated in accordance with the following equation:

D/Q = [DPSF(DC2) (TCORR)]/[(2i/i6)X], m-2 (20) where DPSF = The deposition factor calculated per section 9.2.9, m 9.2.11 Elevated X/Q, D2DPXQ, DlXQ, D/Q Analysis 9.2.11.1 Undecayed, Undepleted Plume Relative Concentration, X/Q The atmospheric concentration of effluent at elevated level, normalized by the source term Q, is given by the following equation:-

X/Q = [2.032(I-TCORR)exp[-0.5(H/az)2 ))/[STACWS(X) az],

sec/m3 (21) where all parameters are as previously defined.

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CY-CL-170-301 Revision 22 Page 194 of 195 9.2.11.2 Decayed, Depleted Radioiodine and Particulate Relative Concentration, D2DPXQ I- . -

The calculation of D2DPXQ for elevated releases follows section 9.2.10.2 methodology with the exception that the WSPL value used in the calculation of DC2 in equation (21) is replaced by the STACWS value and the equation (24) X/Q is used.

D2DPXQ = DPF(DC2)X/Q, sec/M3 (22) where DPF = The depletion factor calculated per section 9.2.9, dimensionless, DC2 T The radioiodine 8-day decay factor, dimensionless exp 693.(X)/t<

60. (STACwS)] 3 exp[ 0'..693 (X)/(8. day)(24.hr/day) (3600 sec/hr)

STACWS)]

= exp[-I'.00E106 (X/ S ACWS)] I 9.,2'.11.3 Decayed Noble Gas Plume Relative Concentration, D1XQ The calculation of D1XQ, for elevated releases' follows section .9.2.10.3 methodologyby substituting the equation (24) X/Q value into equation (22) and STACWS for WSPL in the calculation of DC1.

D1XQ = DCl (X/Q), sec/M3 where DCl = The noble gas decay factor, dimensionless (23)

I

= exp [-0.693(X)/t<<(STACWS)1 3

= exp [-0.693(X)/(2.26 day)(24 hr/day)

(3600 sec/hr) ( STACWS)] 5

= exp [-3.55E-06 (X/STACWS)]

9.2.11:4 Radioiodine and Particulate Relative Deposition, D/Q 3 The calculation of D/Q for elevated releases follows section 9.2.10.4 methodology by substituting (l-TCORR) for the TCORR term in equation (23) and STACWS for WSPL in the calculation of DC2.

where D/Q = [DPSF(l-TCORR)]/[(27t/16)X], m2 (24) 3 DPSF = The deposition factor calculated per section 9.2.9, m CLINTON--UNIT #1 Rev.22 -

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CY-CL-170-301 Revision 22 Page 195 of 195 Table 9.2-5 GASEOUS EFFLUENT RELEASE POINT CHARACTERISTICS HVAC Exhaust SGTS Exhaust Stack Stack (m), 61 61 Release Point Height 58 58 Building Height (m)

Duct Pipe Release Point Geometry 2 11.15 0.15 Release Point Area (M )

3.77* 0.44 Release Point Diameter (m) 3 111.71 1.89 Annual Average Flow Rate (m /sec) 10 .02 12.49 Vertical Exit Velocity (m/sec)

• Effective 2 (A/it)<<diameter Rev.22 -

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