besse offsite dose calculation manual, rev. 24

8/3/2019 Besse Offsite Dose Calculation Manual, Rev. 24.

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DAVIS-BESSE

OFFSITE DOSE CALCULATION MANUAL

Revision 24

Approval:

PORC Chairman

Plant Manager

3-/1-/0Date

Date


2/197

ODCM REV. 24 - LIST OF CHANGES

Page No.27

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TABLE OF CONTENTS1.0 INTROD UC TION ............................................................................................ . 12.0 LIQU ID EFFLU ENTS ..................................................................................... 2

2.1 Radiation Monitoring Instrumentation and Controls .......................... 22.1.1 Required Monitors .................................................................. . 32.1.2 N on-Required Monitors ......................................................... 4

2.2 Sampling and Analysis of Liquid Effluents ........................................ 42.2.1 B atch Releases ........................................................................ 52.2.2 Continuous Releases ............................................................... 52.2.3 Condensate Demineralizer Backwash ..................................... 62.2.4 Borated Water Storage Tank .............................. ................... 7

2.3 Liquid Effluent Monitor Setpoints ....................................................... 82.3.1 Concentration Lim its ............................................................... 82.3.2 Basic Setpoint Equation .......................................................... 82.3.3 Liquid Radwaste Effluent Line Monitor Setpoint

Calculations (RE-1770A & B, RE-1878A & B) ..................... 82.3.4 Storm Sewer Drain Monitor (RE-4686) ................................. 112.3.5 Alarm Setpoints for the Non-Required Radiation

M onitors ................................................................................. . 112.3.6 Alarm Response - Evaluating Actual Release Conditions ...... 12

2.4 Liquid Effluent Dose Calculation - 10 CFR 50 .................................. 132.4.1 Dose Limits to MEMBERS OF THE PUBLIC ............. 132.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents ......... 142.4.3 Simplified Liquid Effluent Dose Calculation ........................ 152.4.4 Contaminated TBS/SSD System - Dose Calculation ............. 16

2.5 Liquid Effluent Dose Projections ........................................................ 193.0 GASEOUS EFFLUENTS ........................................ 34

3.1 Radiation Monitoring Instrumentation and Controls .......................... 343.1.1 Alarm and Automatic Release Termination ............................ 353.1.2 Alarm Only ...................................... 36

3.2 Sampling and Analysis of Gaseous Effluents .................................... 373.2.1 Batch Releases ........................................................................ 373.2.2 Continuous Release ................................................................. 373.2.3 Releases Resulting from Primary-to-Secondary System

Leakage ................................................................................... 38

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TABLE OF CONTENTS (Continued)(3.0 GASEOUS EFFLUENTS - continued)

3.3 Gaseous Effluent Monitor Setpoint Determination ............................. 393.3.1 Total Effective Dose Equivalent Limits ................................ 393.3.2 Release Rate Lim its................................................................. 393.3.3 Individual Release Radiation Monitor Setpoints ................... 403.3.4 Conservative, Generic Radiation M onitor Setpoints .............. 413.3.5 Release Flow Rate Evaluation for Batch Releases .................. 41

3.4 Unrestricted Area Boundary Dose Rate Calculation - Noble Gas ....... 433.5 Unrestricted.Area Boundary Dose Rate Calculation - Radioiodine,

Tritium , and Particulates .................................................................... 443.5.1 Dose Rate Calculation ........................................................... 443.5.2 Simplified Dose Rate Evaluation for Radioiodine,Tritium and Particulates .......................................................... 44

3.6 Quantifying Activity Released ............................................................ 453.6.1 Quantifying Noble Gas Activity Released Using aGrab Sam ple or RE-4598 ...................................................... 453.6.2 Quantifying Noble Gas Activity Released WhileRE-4598 AA and BA, Channel 1, Are Inoperable ................ 463.6.3 Quantifying Radioiodine, Tritium, and ParticulateActivity R eleased ................................................................... 463.6.4 Quantifying Ground Level Releases Activity ........................ 47

3.7 Noble Gas Dose Calculations - 10 CF R 50 .......................................... 493.7.1 UNRESTRICTED AREA Dose - Limits .................. 493.7.2 Dose Calculations - Noble Gases ............................................ 493.7.3 Simplified Dose Calculation for Noble Gases ...................... 49

3.8. Radioiodine, Tritium and Particulate Dose Calculations -10 CF R 50 ............................................................................................ 5 13.8.1 UNRESTRICTED AREA Dose Limits .................................. 513.8.2 Critical Pathway ................................... 523.8.3 Dose Calculations - Radioiodine, Tritium and Particulates .... 523.8.4 Simplified Dose Calculation for Radioiodine, Tritium andParticulates ...................................... 53

3.9 Gaseous Effluent Dose Projection ....................................................... 544.0 SPECIAL DOSE ANALY SES ......................................................................... 104

4.1 Doses To The Public Due To Activities Inside theUNRESTRICTED AREA BOUNDARY ............................................. 104

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TABLE OF CONTENTS (Continued)(4.0 SPECIAL DOSE ANALYSES - continued)

4.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 ....................... 1064.2.1 Effluent Dose Calculations ...................................................... 1084.2.2 Direct Exposure Dose Determination - Onsite Sources .......... 1094.2.3 Dose Assessment Based on Radiological Environmental

M onitoring D ata ...................................................................... 1094.2.4 Use of Environmental TLD for Assessing Doses Due toNoble G as R eleases ................................................................. 111

5.0 ASSESSMENT OF LAND USE CENSUS DATA ........................................... 1135.1 Land U se Census Requirem ents ................ I......................................... 11 35.1.1 Data Com pilation . ................... ............... 1145.1.2 Relative Dose Significance ..................................................... 114

5.1.3 D ata Evaluation ....................................................................... 11 4

5.2 Land Use Census to Support Realistic Dose Assessment ................... 11 56.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .......... 11 6

6.1 Program D escription .......................................................................... 11 66.1.1 G eneral ................................................................................... 11 66.1.2 Program D eviations ................................................................. 11 66.1.3 Unavailability of Milk or Broad Leaf Vegetation Samples .... 11 66.1.4 Seasonal Unavailability, Equipment Malfunctions,

Safety.C o ncerns .................. .......... .......................................... 1176.1.5 Sam ple Analysis .... ................................................................ 117

6.2 Reporting L evels ................................................................................ . 1176.2.1 G eneral ................................................................................. 11 76.2.2 Exceedance of Reporting Levels ............................................. 1176.3 Interlaboratory Comparison Program .................................................. 11 8

7.0 ADMINISTRATIVE CONTROLS ... ............................................................ 13 17.1 Annual Radiological Environmental Operating Report ............. 1317.2 Radioactive Effluent Release Report ................................................... 13 17.3 Special Reports .................................................................................... 13 37.4 Major Changes to Radioactive Liquid and Gaseous WasteT reatm ent System s ............................................................................... 13 3

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TABLE OF CONTENTS (Continued)(7.0 ADMINISTRATIVE CONTROLS - continued)

7.5 Definitions .......................................................................................7.5.1 Batch Release ..........................................................................7.5.2 Composite Sample ..................................................................7.5.3 Gaseous Radwaste Treatment System ....................................7.5.4 Lower Limit of Detection (LLD) ............................................7.5.5 M ember of the Public .............................................................7.5.6 Purge-Purging .........................................................................7.5.7 Unrestricted Area Boundary ..................................................7.5.8 Source Check .........................................................................7.5.9 Unrestricted Area ...................................................................7.5.10 Ventilation Exhaust Treatment System ..................................7.5.11 Venting ..................................................................................

APPENDICES

13413 413 413413 413 513513513 513 513 5135

APPENDIX A -APPENDIX B -APPENDIX C -APPENDIX D -

Table 2-1 -Table 2-2 -Table 2-3 -Table 2-4 -

Table 2-5 -Table 2-6 -Table 2-7 -

Technical Basis for Simplified Dose Calculations, LiquidEffluent Releases .........................................Technical Basis for Effective Dose Factors Gaseous EffluentR eleases .............................................................................................Radiological Environmental Monitoring Program, SampleL ocation M aps ...................................................................................ODCM Subsections Related to Station Procedures ..........................

LIST OF TABLESRadioactive Liquid Effluent Monitoring Instrumentation ................Radioactive Liquid Effluent Monitoring InstrumentationV erification Requirem ents ................................................................Radioactive Liquid Waste Sampling and Analysis Program ............Limiting R adionuclide Concentrations in Secondary SideClean-up Resins for Allowable Discharges to Onsite SettlingB asin .................................................................................................Radionuclide Concentration Limits for the BWST ...........................Liquid Ingestion Dose Commitment Factors ....................................B ioaccum ulation Factors ..................................................................

A-1B-1C-1D-1

19

2123

26272830

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TABLE OF CONTENTS

LIST OF TABLESTable 2-8 -

Table 3-1 -Table 3-2 -

Table 3-3 -Table 3-4 -Table 3-5 -Table 3-6 -

Table 3-7 -Table 3-8 -Table 3-9 -Table 3-10 -Table 3-11-Table 3-12-Table 4-1 -Table 6-1 -Table 6-2 -Table 6-3 -Table 6-4 -

Table B- I -

Table B-2 -

Liquid Pathway Dose Commitment Factors for Release tothe Training Center Pond ..................................................................Radioactive Gaseous Effluent Monitoring Instrumentation .............Radioactive Gaseous Effluent Monitoring InstrumentationVerification Requirem ents ................................................................Radioactive Gaseous Waste Sampling and Analysis Program .......Land U se Census Sum mary ..............................................................Dose Factors for Noble Gases ..........................................................Exposure Pathways, Controlling Parameters, and AtmosphericDispersion for Dose Calculations ..............................Inhalation Pathway Dose Factors ....................................................Grass - Cow - Milk Pathway Dose Factors .......................Grass - Goat - Milk Pathway Dose Factors .......................................Grass - Cow - Meat Pathway Dose Factors ................ I.....................Vegetation Pathway Dose Factors ...................................................Ground Plane Pathway Dose Factors ...............................................Recommended Exposure Rates in Lieu of Site Specific Data .........Radiological Environmental Monitoring Program ...........................Required Sam pling Locations ...........................................................Lower Limits of Detection ..........................................................Reporting Levels for Radioactivity Concentrations inEnvironm ental Sam ples .....................................................................Default Noble Gas Radionuclide Distribution of GaseousE ffluents ...........................................................................................Effective Dose Factors - Noble Gas Effluents .................................

3156

58606364

65667482909610211 211 9124127

13 0

B-5B-6

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Figure 2-1 -Figure 3-1 -

LIST OF FIGURESLiquid Radioactive Effluent Monitoring and Processing Diagram...Gaseous Radioactive Effluent Monitoring and VentilationSystem s D iagram ...............................................................................

34

104

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2.0 LIQUID EFFLUENTS2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS

This section summarizes information on the liquid effluent radiation monitoringinstrumentation and controls. More detailed information is provided in the Davis-BesseUSAR, Section 11.2, Liquid Waste Systems, and associated design drawings from which thissummary was derived. Location and control function of the monitors are displayed inFigure2-1.The radioactive liquid effluent instrumentation is provided to monitor and control, asapplicable, releases of radioactivity in liquid effluents during actual or potential releases.The radioactive liquid effluent monitoring instrumentation channels listed in Table 2-1 shallbe FUNCTIONAL with their alarm/trip setpoints set to ensure the limits specified in Section2.3.1 are not exceeded.Each radioactive liquid effluent monitoring instrumentation channel shall be demonstratedFUNCTIONAL by the performance of the CHANNEL CHECK, SOURCE CHECK,CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at thefrequencies shown in Table 2-2. Each of these operations shall be performed within thespecified time interval with a maximum allowable extension not to exceed 25 percent of thespecified interval.NOTE: The monitors indicated in 2. 1.1 a), b), and c) are nonfunctional if verifications are

not performed or setpoints are less conservative than required.With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint lessconservative than required, without delay suspend the release of radioactive liquid effluentsmonitored by the affected channel, or declare the channel nonfunctional, or change thesetpoint so it is acceptably conservative.With less than the required number of radioactive liquid effluent monitoring instrumentationchannels FUNCTIONAL, take the actions described in Table 2-1. Exert best efforts to returnthe instruments to FUNCTIONAL status within 30 days and, if unsuccessful, explain in thenext Radioactive Effluent Release Report, (Section 7.2), why the nonfunctionality was notcorrected in a timely manner.

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2.1.1 Required MonitorsThis section describes the monitoring required during liquid releases and the backupsampling required when monitors are nonfunctional.a) Alarm and Automatic Release Termination

Clean Radwaste Effluent Monitors (RE-1770 A & B)Discharges from the Clean Radwaste Monitor Tanks (2) are monitored byredundant radiation monitoring systems (RE-1770 A & B). These monitorsdetect gross gamma activity in the effluent prior to mixing in the CollectionBox. Measurements from each detector read out on the Victoreen panel inthe Control Room. Each monitoring system is capable of initiating an alarmand an automatic termination of the release by closing valve WC-1771. Themethod for determining setpoints for the alarms is discussed in Section 2.3.

ii. Miscellaneous Radwaste Effluent Monitors (RE-1878 A & B) Dischargesfrom the Miscellaneous Liquid Waste Monitor Tank and the DetergentWaste Drain Tank are monitored by redundant radiation monitoring systems(RE-i 878 A & B). These monitors detect gross gamma activity in theeffluent line prior to mixing in the Collection Box. Measurements from eachdetector read out on the Victoreen panel in the Control Room. Each monitoris separately capable of initiating an alarm and automatic termination of therelease by closing valve WM-1876. Setpoint determination for the alarms isdiscussed in Section 2.3.

b) Alarm (only)i. Storm Sewer Drain Line (RE-4686)

The monitor on the Storm Sewer Drain effluent line detects abnormalradionuclide concentrations in the storm sewer effluent. This monitor islocated near the end of the storm sewer drain pipe, upstream of the finaldischarge point into the Training Center Pond. The most probable source ofany non-naturally occurring radioactive material in the storm sewer would befrom the secondary system.To eliminate this potential source of radioactivity, the Turbine BuildingSump effluent is normally directed to the onsite Settling Basins. In thisconfiguration, the source of radioactivity in the Storm Sewer Drain line isfrom Turbine Building drains that are not routed to the Turbine BuildingSump, or from Storm Sewer drains. Evaluation of the alarm setpoint forRE-4686 is discussed in Section 2.3.4.

c) Flow Rate Measuring Devicesi. Clean Radwaste Effluent Line

Flow Indicator (FI) 1700 A & BFlow Totalizer (FQI) 1700 A & B

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ii. Miscellaneous Radwaste Effluent LineFlow Indicator (FI) 1887 A & BFlow Totalizer (FQI) 1887 A & B

iii. Dilution Flow to the Collection BoxComputer Point F201 consists of four points:* F147 Cooling Tower Blowdown* F890 Service Water Outflow* F200 Collection Bo x Dilution Flow0 F886 Unit Dilution Pump Flow

2.1.2 Non-Required MonitorsAdditional monitors, although not required by the ODCM, have been installed to monitorradioactive material in liquid. The monitors are:

Collection Box Outlet to the Lake (RE-8433) - monitors the final station effluent tothe lake,Component Cooling Water System (CCWS) (RE-1412 & 1413)-monitors the CCWSreturn lines. High alarm closes the atmospheric vent valves on the CCWS surgetank, and redirects the vent path to the Miscellaneous Waste Drain Tank,Service Water System (SWS) (RE-8432) - off-line detector monitors the SW S outletprior to discharge to the Collection Box, andIntake Forebay (RE-8434) - monitors the station intake water from intake forebay.

2.2 SAMPLING AN D ANALYSIS OF LIQUID EFFLUENTSAs a minimum, radioactive liquid wastes shall be sampled and analyzed according to thesampling and analysis program of Table 2-3. Table 2-3 identifies three potential sources ofliquid radioactive effluents. A fourth potential release point from the Turbine BuildingSump is discussed in Section 2.2.2.Th e results of the radioactivity analyses shall be used in accordance with the methodologyand parameters of this section to ensure that the concentrations at the point of release aremaintained within the limits of 10 CF R 20.1302.

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2.2.1 Batch ReleasesBATCH RELEASE is defined as the discharge of liquid waste of a discrete volume. Th ereleases from the Clean Waste Monitor Tanks 1-1 and 1-2, the Miscellaneous Liquid WasteMonitor Tank, and the Detergent Waste Drain Tank are classified as BATCH RELEASES.Th e following sampling and analysis requirements shall be met for all releases from thesetanks.

Prior to each release, analysis of a representative grab sample for principal gammaemitters.Once per month, as a minimum, analysis of one sample from a BATCH RELEASEfor dissolved and entrained gases (see note below).Once per month, analysis of a COMPOSITE SAMPLE of all releases that month fortritium and gross alpha activity. Samples contributed to the composite are to beproportional to the quantity of liquid discharged.Once per quarter, analysis of a COMPOSITE SAMPLE of all releases that quarterfor Strontium (Sr)-89, Sr-90, and Iron (Fe)-55.NOTE: Identification ofnoble gases that are principal gamma-emitting radionuclidesare included as a part of the gamma spectral analysis performed on all liquidradwaste effluents. Therefore, the Table 2-3 requirement fo r sampling andanalysis of one batch per month for noble gases need no t be performed as aseparate program.

2.2.2 Continuous ReleasesReleases from the Turbine Building Sump (TBS) and Storm Sewer Drains (SSD) areclassified as continuous releases.Because the Turbine Building Sump discharges may contain minute concentrations ofradionuclides due to primary-to-secondary system leakage, the Turbine Building Sumpdischarges are routed to the onsite Settling Basins instead of the SSD line. Screenwash waterfrom the Screenwash Catch Basin is also routed to the North Settling Basin. Overflow fromthe Settling Basins is pumped to the Collection Box where it is mixed with dilution flow andreleased to Lake Erie. Releases via this pathway are monitored by weekly analysis forprincipal gamma-emitting radionuclides and tritium, and by quarterly analysis of compositesamples for Fe-55, Sr-89 and Sr-90.Discharges to the Storm Sewer Drains are from Turbine Building drains that are not routed tothe TBS and from storm drains. The Storm Sewer discharges to the Training Center Pondwith the overflow discharging to the Toussaint River. For conservatism, it is assumed thatradioactive material released to the Training Center Pond is ultimately discharged to LakeErie (unless actions are taken to prevent this occurrence).

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Grab samples are collected weekly from the Settling Basins and analyzed by gammaspectroscopy. If activity is identified, additional controls are enacted to ensure that therelease concentrations are maintained below Effluent Concentration Limits and that thecumulative releases are a small fraction of the dose limits of Section 2.4.1. The followingactions will be considered for controlling any radioactive material releases via the TB S andSSD:Increase the sampling frequency of the TB S and SSD until the source of thecontamination is identified.Perform gamma spectral analysis on each sample for principal gamma emitters.Compare the measured radionuclide concentrations in the sample with EC (equation2-2) to ensure releases are within the limits.Based on the measured concentrations, a re-evaluation of the alarm setpoint for theSS D monitor (RE-4686) may be performed as specified in Section 2.3.4.Consider each sample representative of the releases that have occurred since theprevious sample. Determine the volume of liquid released from the TurbineBuilding Sump based on the Turbine Building Sump pump run times and flow rates.Determine the total radioactive material released from the sample analysis and the.calculated volume released. Determine cumulative doses in accordance withSection 2.4.

2.2.3 Condensate Demineralizer BackwashDischarges from the Condensate Demineralizer Backwash Receiving Tank (BRT) to theSouth Settling Basin are sampled in accordance with Table 2-3. Samples are collected priorto each release of the resin/water slurry and separated into the liquid phase (transfer water)and solid phase (resin). These samples are separately analyzed for principal gamma emitters.FirstEnergy Nuclear Operating Company (FENOC) has imposed guidelines onconcentrations of radionuclides that may be discharged to the onsite settling basin. Theseguidelines are presented in Table 2-4.The radioactive material contamination in the condensate demineralizer backwash will becontained on the powdered resin; soluble or suspended radioactive material associated withthe water phase is not expected. The resin and the water are analyzed separately thusallowing for a determination of the amounts retained onsite in the Settling Basin (the resin)and the amounts released to Lake Erie as an effluent (the decant).The BRT receives the spent resin from, the Condensate Polishing System. Low-levelradioactive material contamination of the spent resin is periodically expected due to minorleaks in the steam generators and the leaching of residual activity in the secondary system.During primary-to-secondary leakage, activity levels will be elevated and typically above thelimits imposed for acceptable discharge to the basin. Under these conditions, the powderedresins are retained within the plant and processed as solid radwaste for offsite transport anddisposal at a licensed radioactive waste disposal site. If within the criteria of Table 2-4, theBRT may be discharged to the onsite settling basin with the approval of the Manager - SiteChemistry.

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2.2.4 Borated Water Storage TankThe Borated Water Storage Tank (BWST) is an unprotected outdoor liquid storage tank andtherefore is part the Explosive Gas and Storage Tank Radioactivity Monitoring Program (TS5.5.1 .b as implemented by TRM 8.7.4).The quantity of radioactive material stored in the BWST shall be limited to ensure that anuncontrolled release of the tank contents would result in concentrations less than the limits of10 CF R 20, Appendix B, Table 2, column 2 at the nearest potable water supply and thenearest surface water supply in an unrestricted area.The concentration of radionuclides in the BWST shall be determined to be within theapplicable limits by analyzing a representative sample of the tank contents at least once per 7days when radioactive materials are being added to the tank.The method for limiting the BWST radionuclide concentration to meet the criteria above isdescribed below.1) Determine the limiting fraction of each radionuclide present in a liquid sample fromthe tank. This is the sample concentration in gCi/ml divided by the limiting activityfrom Table 2-5.2) Sum the limiting fractions of each radionuclide in the sample. This sum should beless than one (1) to meet the limiting criteria for offsite dose rates via the liquid

pathway.

If the sum of the limiting fractions of radionuclides in the BWST is equal to orexceeds one (1), then suspend all additions of radioactive material to the tank, reducetank contents to within the limits, and describe the events leading to this condition inthe next Radioactive Effluent Release Report. (TRM 8.7.4 requirements)The values in Table 2-5 were calculated specifically for the BWST.

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2.3 LIQUID EFFLUENT MONITOR SETPOINTS2.3.1 Concentration Limits

Th e concentrations of radioactive material released in liquid effluents to UNRESTRICTEDAREAS shall be limited to the concentrations specified in 10 CFR Part 20.1302 for.radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noblegases, the concentration shall be limited to 2.0 E-04 [tCi/ml. If the concentration ofradioactive material released in liquid effluents to UNRESTRICTED AREAS exceeds theselimits, then without delay restore the concentrations to within these limits.This limitation provides additional assurance that the levels of radioactive material in bodiesof water outside the site should not result in exposures exceeding the Section II.A designobjective of Appendix I, 10 CFR Part 50, to an individual, and the limits of 10 CFR Part20.1302 to the population.Th e concentration limit for noble gases is based upon the assumption that Xe-135 is thecontrolling radioisotope and its EC in air (submersion) was converted to an equivalentconcentration in water using the methods described in International Commission onRadiological Protection (ICRP) Publication 2.

2.3.2 Basic Setpoint EquationDuring the release of liquid radioactive effluents, radiation monitor setpoints shall beestablished to alarm and trip prior to exceeding the limits specified above. To meet thisrequirement, the alarm/trip setpoint for liquid effluent monitors measuring the radioactivityconcentration prior to dilution is derived in Section 2.3.3.

2.3.3 Liquid Radwaste Effluent Line Monitor S etpoint Calculations (RE-1770A & B, RE-1878A&B)Th e Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination ofreleases prior to exceeding the Effluent Concentrations (EC) of 10 CF R 20.1302 at theUNRESTRICTED AREA. As required by Table 2-3 and as discussed in Section 2.2.1, asample of the liquid radwaste to be discharged is collected and analyzed by gammaspectroscopy to identify principal gamma-emitting radionuclides. A maximum release ratefrom the tank is determined for the release based on the radionuclide concentrations and theavailable dilution flow rate.The maximum release rate is inversely proportional to the ratio of the radionuclideconcentrations to their EC values. This ratio of measured concentration to EC values isreferred to as the EC fraction (ECF) and is calculated by the equation:

ECF Ci (2-2)

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where:EC F sum of the fractions of the unrestricted area EC for a mixture of

radionuclides,Ci concentration of each radionuclide i measured in tank prior to release

(iiCi/ml), andEQ = unrestricted area EC (gCi/ml) for each radionuclide i from 10 CF RPart 20.1302. For dissolved and entrained noble gases an EC value of

2.OE-04 ptCi/ml shall be used.Based on the ECF, the minimum dilution factor (MDF) for the conduct of the release isestablished at 3.33 times larger than actually required. This safety factor (SF) providesconservatism, accounting for variations in monitor response and flow rates and also for thepresence of radionuclides that may not be detected by the monitors (i.e., non-gammaemitters). Th e following equation is used for calculating the required minimum dilutionfactor:

MDF = ECF/SF (2-3)where:MDF = minimum required dilution factor,SF = 0.3 administrative safety factor.The maximum release rate from the tank is then calculated by dividing the available dilutionflow rate (ADF) at the Collection Bo x by the MDF as calculated by equation' (2-4).

MAX RR = 0.9 (ADF/MDF) (2-4)where:MAX RR = maximum allowable release rate (gal/mim),0.9 - administrative conservatism factor, andADF available dilution flow rate at the Collection Box as measured byComputer Point F201 (gal/min).NOTE: Equations (2-3) and (2-4) are valid only for ECF >1. For EC F


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Since the actual release rate from the tank is derived such that 10 CF R 20.1302 limits willnot be exceeded given the radionuclide concentration in the tank and the available dilutionflow, setpoints must be established to ensure:1) radionuclide concentration released from the tank does not increase above the

concentration detected in the sample,2) available dilution flow does not decrease, and3) actual release rate from the tank does not increase above the calculated value.The setpoints for the predilution radiation monitor (RE-1770 A & B, or RE-1878 A & B) aredetermined as follows:

Alert Alarm SP = [2 * R * I (Ci * SENi)] + BkgHigh Alarm SP = [3 * R * Z (Ci * SENi)] + Bkg

(2-5)(2-6)

where:SP.Ci

SENi

= setpoint of the radiation monitor (cpm),= concentration of radionuclide i as measured by gamma spectroscopy(giCi/ml),

monitor sensitivity for radionuclide i based on calibration curve (cpm pergCi/ml),background reading of the radiation monitor (cpm), and

= MAX RR / actual release rateBkgRThe Cs-137 sensitivity may be used in lieu of the sensitivity values for individualradionuclides. The Cs-137 sensitivity provides a reasonably conservative monitor responsecorrelation for radionuclides of interest in reactor effluents. Coupled with the safety factorSF in equation (2-3), this assumption simplifies the evaluation without invalidating theoverall conservatism of the setpoint determination.The high flow setpoint should be set equal to the MAX RR calculated in equation (2-4) ordischarge pump capacity (whichever is smaller). Th e low flow setpoint for dilution flow rateshould be set at 0.9 times the available dilution flow rate.

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2.3.4 Storm Sewer Drain Monitor (RE-4686)The setpoint for the SSD radiation monitor, RE-4686, shall be established to ensure theconcentration in the effluent does not exceed the limits of 10 CFR 20.1302. The SSD is notnormally radioactively contaminated by other than naturally-occurring radionuclides.Therefore, the setpoint for this monitor has been established at a practical level to provide anearly indication of any abnormal conditions without causing spurious alarm due tofluctuations in background.Since discharge is to the Training Center Pond, exceeding the RE-4686 setpoint does notnecessarily mean Section 2.3.1 concentration limits have been exceeded atUNRESTRICTED AREAS. The verification of compliance with the limits on concentrationshould be based on actual samples of the effluent from the pond to the Toussaint River andLake Erie. (Refer to Section 2.3.6).

2.3.5 Alarm Setpoints for the Non-Required Radiation Monitorsa) Collection Box Outlet to the Lake (RE-8433)

The radiation monitor on the Collection Box outlet utilizes a single off-line detectorto continuously monitor all station liquid effluent discharges to the lake. Althoughthis is the final effluent monitor, it does not serve any control function. Controlfunctions have been placed on the upstream undiluted effluent line that willterminate the release prior to exceeding the effluent concentration forUNRESTRICTED AREAS in 10 CF R 20.1302. RE-8433 provides a final check ofthe total diluted effluent stream. Since this monitor views the diluted radwastedischarges, its response during routine operations will be minimal (i.e., typical ofbackground levels). Therefore, the alarm setpoint for this monitor should beestablished as close to background as possible without incurring a spurious alarmdue to background fluctuations. Th e setpoint is controlled in accordance with theRadiation Monitor Setpoint Manual.b) Component Cooling Water System (CCWS) (RE-1412 & 1413)

The monitors RE-1412 and 1413 provide indication of a breach in the CCWSintegrity that would allow reactor coolant water to enter.and contaminate the system.Therefore, the alarm setpoint is established to prevent incurring a spurious alarm dueto background fluctuations. The setpoint is controlled in accordance with theRadiation Monitor Setpoint Manual.c) Service Water System (SWS) (RE-8432)

No radioactive material is expected to be contained within the SW S during normaloperations. Therefore, the high alarm setpoint is established to prevent incurring aspurious alarm due to background fluctuations. The setpoirit is controlled inaccordance with the Radiation Monitor Setpoint Manual.

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d) Intake Forebay Monitor (RE-8434)The high alarm setpoint is established to prevent incurring a spurious alarm due tobackground fluctuations. Although highly unlikely, a verified alarm from thissystem would indicate a possible contamination of the station intake water. Thesetpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.

2.3.6 Alarm Response - Evaluating Actual Release ConditionsLiquid release rates are controlled and alarm setpoints are established to ensure that releasesdo not exceed the concentration limits of Section 2.3.1 (i.e., 10 CF R 20 ECs at the dischargeto Lake Erie). However, if any of the monitors (RE-1770 A & B, RE-1878 A & B, orRE-4686) alarm during a liquid release, it becomes necessary to re-evaluate the releaseconditions to determine compliance with the limits. After an alarm, the following actualrelease conditions should be determined:

verify radiation monitor alarm setpoint to ensure consistency with the setpointevaluation for the release;

re-sample and re-analyze the source of the releasere-determine the release rate and the dilution water flow.

Based on available data, the following equation may be used for evaluating the actual releaseconditions:

E Ci RR


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2.4 LIQUID EFFLUENT DOSE CALCULATION - 10 CF R 502.4.1 Dose Limits to MEMBERS OF THE PUBLIC

The limits for dose or dose commitment to MEMBERS OF THE PUBLIC from radioactivematerials in liquid effluents from Davis-Besse are:

during any calendar quarter:< 1.5 mrem to total body< 5.0 mrem to any organduring any calendar year:< 3.0 mrem to total body< 10.0 mrem to any organ

With the calculated dose from the release of radioactive materials in liquid effluentsexceeding any of the above limits, in lieu of a Licensee. Event Report, prepare and submit tothe Commission within 30 days, pursuant to Section 7.3, a Special Report that identifies thecause(s) for exceeding the limit(s) and defines the corrective actions that have been taken toreduce the releases and the proposed corrective actions to be taken to assure that subsequentreleases will be in compliance with the above limits.Cumulative dose contributions from liquid effluents for the current calendar quarter and thecurrent calendar year shall be determined in accordance with the methodology andparameters in the ODCM at least once per 31 days.This requirement is provided to implement the requirements of Sections II.A, III.A and IV.Aof Appendix I, 10 CFR Part 50.This action provides the required operating flexibility and at the same time implements theguides set forth in Section IV.A of Appendix I, 10 CFR Part 50 to assure that the releases ofradioactive material in liquid effluents will be kept "as low as is reasonably achievable."NOTE: For fresh water sites with drinking water supplies which can be potentially affected

by plant operations, there is reasonable assurance that the operation of the facilitywill not result in radionuclide concentrations in the finished drinking water that arein excess of the requirements of 40 CFR 141. The dose calculations in the ODCMimplement the requirements of Section III.A of Appendix I, 10 CFR Part 50.Conformance with the guides of Appendix I is to be shown by calculationalprocedures based on models and data such that the actual exposure of an individualthrough appropriate pathways is unlikely to be substantially underestimated. Theequations specified in the ODCM for calculating the doses due to the actual releaserates of radioactive materials in liquid effluents are consistent with the methodologyprovided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man fromRoutine Releases of Reactor Effluents for the Purpose of Evaluating Compliancewith 10 CFR Part 50 , Appendix I," Revision 1, October 1977.

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2.4.2 MEMBER OF TH E PUBLIC DOSE - Liquid EffluentsThe calculation of the potential doses to MEMBERS OF THE PUBLIC is a function of theradioactive material releases to the lake, the subsequent transport and dilution in theexposure pathways, and the resultant individual uptake. At Davis-Besse, the combined fishconsumption and drinking water pathway has been modeled to provide a conservative doseassessment for exposures to MEMBERS OF THE PUBLIC. For the fish pathway, it hasbeen conservatively assumed that the maximum exposed individual consumes 21 kg per yearof fish taken in the immediate vicinity of the Davis-Besse discharge to the lake. For thedrinking water pathway, the conservative modeling is based on an individual drinking 730liters per year of water from the Carroll Township Water Intake located 3.0 miles to the NWof the site discharge.The equation for assessing the maximum potential dose to MEMBERS OF TH E PUBLICfrom liquid radwaste releases from Davis-Besse is:

Do=1.67E - 02 *VOL*Z C*Ai)(28O - l. 7 ~O O*x2(Ci *Ai) (2-8)DF*Z

where:Do dose or dose commitment to organ ."o" including total body (mrem),Aio site-specific ingestion dose commitment factor to the total body or any organ"o" for radionuclide "i" given in Table 2-6 (mremihr per tlCi/ml),Ci = average concentration of radionuclide i in undiluted liquid effluentrepresentative of the volume VOL (gCi/ml),VOL total volume of undiluted liquid effluent released (gal),DF = average dilution water flow rate during release period (gal/min) (typically20,000 gpm),Z = 10 (near field dilution factor)*1.67E-02 = 1 hr/60 min.

Near field dilution factor and dilution to Carroll Township water intake is based on USARSection 11.2.7.2 and a study performed by Stone & Webster for Toledo Edison entitled "AquaticDilution Factors within 50 Miles of the Davis-Besse Unit 1 Nuclear Power Plant", June 1980.

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The site-specific ingestion dose/dose commitment factors (Aio) represent a composite dosefactor for the fish and drinking water pathway. The site-specific dose factor is based on theNRC's generic maximum individual consumption rates. Values of Ajo are presented in Table2-6. These values were derived in accordance with the guidance ofNUREG-0 133 using thefollowing equation:Aio = 1.14E+05 (Uw / D, + UF * BFi) DFi (2-9)where:U = 21 kg/yr adult fish consumption,Uw 730 liters/yr adult water consumption,Dw 175 additional dilution from the near field to the Carroll Township waterintake (net dilution of 1750),BFi bioaccumulation factor for radionuclide "i" in fish from Table 2-7 (pCi/kgper pCi/1),DFj = dose conversion factor for nuclide "i" for adults in organ "o" from Table

E- 11 of Regulatory Guide 1.109 (mrem/pCi), and1.14E+05 = 106 (pCi/iCi) * 103 (ml/kg) / 8760 (hr/yr).The radionuclides included in the periodic dose assessment required by Section 2.4.1 arethose identified by gamma spectral analysis of the liquid waste samples collected andanalyzed per the requirements of Table 2-3. In keeping with the NUREG-0 133 guidance, theadult age group represents the maximum exposed individual age group. Evaluation of dosesfo r other age groups is not required for demonstrating compliance with the dose criteria ofSection 2.4.1. Th e dose analysis for radionuclides requiring radiochemical analysis will beperformed after receipt of results of the analysis of the composite samples. In keeping withthe required analytical frequencies of Table 2-3, tritium dose analyses will be performed atleast monthly; Sr-89, Sr-90 and Fe-55 dose analyses will be performed at least quarterly.

2.4.3 Simplified Liquid Effluent Dose CalculationIn lieu of the individual radionuclide dose assessment presented in Section 2.4.2, thefollowing simplified dose calculation may be used for demonstrating compliance with thedose limits required by Section 2.4. 1. Radionuclides included in this dose calculation shouldbe those measured in the grab sample of the release (principal gamma emitters measured bygamma spectroscopy). H-3 should not be included in this analysis. Refer to Appendix A forthe derivation of this simplified method.

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Total Body

Dtb =9.67E + 02*VOL (2-10)DFDmax l.18E + 03*VOL*c, (2-11)

DFwhere:Ci = average concentration of radionuclide i excluding H-3 in undiluted liquid

effluent representative of the release volume (jiCi/ml),VOL = volume of liquid effluent released (gal),DF = average dilution water flow rate during release period (gal/min),Dtb = conservatively evaluated total body dose (mrem),Dmax conservatively evaluated maximum organ dose (mrem),9.67E+02 0.0 167 (hr/min) * 5.79E+05 (mrem/hr per pCi/ml, Cs-134 total body

dose factor from Table 2-6) / 10 (near field dilution), and1.18E+03 0.0167 (hr/min) * 7.09E+05 (mrem/hr per jtCi/ml, Cs-134 liver dose

factor from Table 2-6) / 10 (near field dilution).2.4.4 Contaminated TBS/SSD System - Dose Calculation

All non-naturally occurring radioactivity released from the SSD must be included in theevaluation of the cumulative dose to a MEMBER OF THE PUBLIC. Although thedischarges are via the Training Center Pond to Pool 3, and then to the Toussaint River(instead of directly to Lake Erie), the modeling of equation (2-8) remains reasonablyconservative for determining a hypothetical maximum individual dose. The followingassumptions should be applied for the dose assessment of any radioactive material releasesfrom the SSD into the Training Center Pond and subsequently to the Toussaint River:

If no additional controls are taken, then it should be assumed that any radioactivematerial released to the Training Center Pond will ultimately be discharged to thelake environment;If actions are taken to limit any release, then the assessment of dose should be madebased on an evaluation of actual releases; andThe dilution flow should consider additional dilution of the SSD discharge fromother sources into the Training Center Pond prior to release to the river.

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2.5 LIQUID EFFLUENT DOSE PROJECTIONS10 CF R 50.36a requires licensees to maintain and operate the radwaste system to ensurereleases are maintained ALARA . This Section implements the requirements of 10 CF R Part50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objectiveSection II.D of Appendix I to 10 CFR Part 50. Based on a cost analysis of treating liquidradwaste, the specified limits governing the use of appropriate portions of the liquid radwastetreatment system were specified as the dose design objectives as set forth in Section II.A ofAppendix I, 10 CFR Part 50, for liquid effluents. This requirement is implemented throughthis ODCM.The liquid radioactive waste processing system shall be used to reduce the radioactivematerial levels in the liquid waste prior to release when the projected doses in any 31-dayperiod would exceed:

0.06 mrem to the total body, or0.20 mrem to any organ.

This dose criteria for processing is established at one quarter of the design objective rate(i.e., 1/4 of 3 mrem/yr total body and 10 mrem/yr any organ over a 31-day projection).With radioactive liquid waste being discharged without treatment and in excess of the abovelimits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30days, pursuant to Section 7.3, a Special Report that includes the following information:

explanation of why liquid radwaste was being discharged without treatment,identification of any nonfunctional equipment or subsystems, and the reason for thenonfunctionality;action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status; andsummary description of action(s) taken to prevent a recurrence.

In any month in which radioactive liquid effluent is being discharged without treatment,doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per31 days in accordance with the methodology and parameters in the ODCM.The following equations may be used for the dose projection calculation:

Dtbp = Dtb (3 1 Id) (2-12)Dmaxp = Dmax (31 / d) (2-13)

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where:Dtbp

Dtb

Dmaxp

Dmax

d31

the 31-day total body dose projection (mrem),the cumulative total body dose for current calendar month including releaseunder consideration as determined by equation (2-8) or (2-10) (mrem),the 31-day maximum organ dose projection (mrem),

= the maximum organ dose for current calendar month including release underconsideration as determined by equation (2-8) or (2-11) (mrem),= the number of days into current month, and= the number of days in projection.

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Table 2-1RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

REQUIREDCHANNELSNSTRUMENT1. Gross Radioactivity Monitors Providing Alarms and Automatic

Termination of Releasea. Liquid Radwaste Effluent Line (either Miscellaneous(RE 1878A, B) or Clean (RE 1770A, B), but not bothsimultaneously)*

2. Flow Rate Measurement Devicesa. Liquid Radwaste Effluent Lineb. Dilution Flow to Collection Boxc. FE 4687 Storm Sewer

3. Gross Beta or Gamma Radioactivity Monitors Providing Alarm Bu tNot Providing Automatic Termination of Releasea. Storm Sewer Drain (RE 4686)

APPLICABILITY ACTION

I (1) A

II

(1)(1)(1)

BBB

I (1) C

* Only one release (either MWMT or CWMT) at a time can be in progress.

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Table 2-1 (continued)TABLE NOTATION

(1) During radioactive releases via this pathwayACTION A With less than the number of required channels FUNCTIONAL, effluent releasesmay be resumed, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Table 2-3for analyses performed with each batch;2. At least two independent verification of the release rate calculations are

performed;3. At least two independent verifications of the discharge valving areperformed;Otherwise, suspend release of radioactive effluents via this pathway.With less than the number of required channels FUNCTIONAL, effluent releases viathis pathway may continue provided the flow rate is estimated at least once per 4hours during actual releases. Pump curves may be used to estimate flow.With less than the number of required channels FUNCTIONAL, or if high alarm islocked in on RE , effluent releases via this pathway may continue provided that duringeffluent releases, grab samples are collected, at least once per 12 hours, and analyzed,at least once per 12 hours, for gross radioactivity (beta or gamma) at a lower limit ofdetection no greater than 1.OE-07 ptCi/ml or a gamma isotopic analysis meeting theLL D Requirement of Table 2-3.

ACTION B

ACTION C

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Table 2-2RADIOACTIVE LIQUID EFFLUENT MONITORINGINSTRUMENTATION VERIFICATION REQUIREMENTS

CHANNELINSTRUMENT CHECK SOURCECHECK CHANNELCALIBRATIONCHANNELFUNCTIONAL

TEST1. Gross Beta or Gamma Radioactivity MonitorsProviding Alarm and Automatic Isolation, if

applicable.a. Liquid Radwaste Effluents Linesb. Storm Sewer Discharge Line

PM

Q()Q()(3)

2. Flow Rate Monitorsa. Liquid Radwaste Effluent Linesb. Dilution Flow to Collection Bo x

N/AN/AN/A

EE

QQ

c. Storm Sewer

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(1) During releases via this pathway.(2) If applicable, the CHANNEL FUNCTIONAL TEST shall also demonstrate that automaticisolation of this pathway and control room alarm annunciation occurs if the instrumentindicates measured levels above the alarm/trip setpoint.(3) Th e initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shallbe performed using one or more of the reference standards certified by the National Institute

of Standards and Technology or using standards that have been obtained from suppliers thatparticipate in measurement assurance activities with NIST. These standards should permitcalibrating the system over its intended range of energy and rate capabilities. For subsequentCHANNEL CALIBRATION, sources that have been related to the initial calibration shouldbe used, at intervals of at least once per eighteen months. Fo r high range monitoringinstrumentation, where calibration with a radioactive source is impractical, an electroniccalibration may be substituted for the radiation source calibration.(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL CHECK shall be made at least once daily on any day on which continuous,periodic, or BATCH RELEASES are made.

(D) At least once per 24 hours.(M) At least once per 3 1 days.(P) Prior to each release.(E) At least once per 18 month (550 days).(Q) At least once per 92 days.(R) At least once per 24 months (730 days)

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Table 2-3RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM

Minimum Type of Lower Limit ofLiquid Release Type Sampling Analysis Activity Detection (LLD)Frequency Frequency Analysis (qlCi/ml)yA. Batch Waste P P PrincipalRelease Tanksd Each Batch Each Batch Gamma 5.OE-07bEmittersf1- 31 f 1.0E-06

P M Dissolved andOne Batch/M Entrained 1.OE-05Gases

P MEach Batch Compositec H-3 1.OE-05Gross Alpha 1.OE-07P QEach Batch Compositec Sr-89, Sr-90 5.OE-08Fe-55 1.OE-06

B. Storm Sewer Drain PrincipalContinuously Se Gamma 5.OE-07bmonitored Emittersf1-131f 1.0E-06

C. Condensate P P PrincipalDemineralizer Each Batch Each Batch Gamma 5.OE-07bBackwash when when Emittersfdischarged to discharged tothe settling the settling 1-13f 1.OE-06basin basin

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a. The LLD is the smallest concentration of radioactive material in a sample that will bedetected with 95% probability with 5% probability of falsely concluding that a blankobservation represents a "real" signal.Fo r a particular measurement system (which may include radiochemical separation):

LLD =E * V * 2.22 * Y * exp (-,At)

whereLL D is the 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 blanksample as appropriate (as counts per minute);E is the counting efficiency (as counts per transformation);V is the sample size (in units of mass or volume);2.22 is the number of transformations pe r minute per picocurie;Y is the fractional radiochemical yield (when applicable);k is the radioactive decay constant for the particular radionuclide;

At for plant effluents is the elapsed time between the midpoint of sample collection and timeof counting.It should be recognized that the LLD is defined as an a priori (before the fact) limitrepresenting the capability of a measurement system and no t as an a posteriori (after the fact)limit for a particular measurement.

b. Th e principal gamma emitters for which the LLD specification will apply are exclusively thefollowing radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, andCe-141. Fo r Ce-144, the LLD is 2.0E-06 pCi/ml. Other peaks which are measured andidentified shall also be reported.Nuclides which are below the LLD for the analysis should not be reported as being present atthe LLD level. When unusual circumstances result in LLDs higher than required, the reasonsshall be documented in the Rad ioactive Effluent Release Report.

c. A COMPOSITE SAMPLE is one in which the method of sampling employed results is aspecimen which is representative of the liquids released.

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d. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume.e. When the monitor is out of service or monitor is locked in high alarm, a grab sample shall betaken and analyzed once every 12 hours if there is flow from the Storm Sewer line.f. If an isotopic analysis is unavailable, gross beta or gamma measurement of BATCHRELEASE may be substituted provided the concentration released to the UNRESTRICTEDAREA does not exceed 1.OE-07 gCi/ml and a COMPOSITE SAMPLE is analyzed forprincipal gamma emitters when instrumentation is available.g. Frequency notation:

P - Prior to each release.M - At least once per 31 days.Q - At least once per 92 days.S - At least once per 12 hours (when the monitor is nonfunctional or high alarm is locked in).

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Table 2-4Limiting Radionuclide Concentrations* In Secondary-SideClean-Up Resins for Allowable D ischarges to Onsite Settling Basin

RadionuclideCr-51Mn-54Fe-59Co-58Co-60Y-91Zr-95Nb-95Mo-99Ru-103Ru-106Ag-il0mTe-125mTe-127mTe-129mTe-131mTe-1321-1311-1331-135Cs-134Cs-136Cs-137Ba-140La-140Ce-141Ce-144Pr-143

Limiting Concentration**(,Ci/cm3)3.3E-026.2E-055.1E-043.OE-045.4E-062.1E-034.1E-041.OE-037.8E-03***1.OE-031.6E-051.6E-055.4E-051.5E-056.2E-05.3.1E-03***3.5E-03***1.1E-043.8E-041.5E-031.1E-052.3E-03***1.OE-053.1E-03***3.5E-03***5.8E-034.1E-051.9E-02

* Concentration limits based on the study, Disposal of Low-Level Radioactively ContaminatedSecondary-Side Clean-up Resins in the On-site Settling Basins at the Davis-Besse Nuclear PowerStation, J. Stewart Bland, May 1983. The limits represent a hypothetical maximum individualdose of less than 1 mrem per year due to an inadvertent release to the offsite environment. Theallowable release limits as presented in Table 2 of the above reference report have been reducedby a factor of 10 for added conservatism - representing a hypothetical dose of less than 0.1 mrem.

** With more than one radionuclide identified in a resin batch, the evaluation for acceptabledischarge to the onsite settling basin shall be based on the "sum of the fractions" rule as follows:Determine for each identified radionuclide the ratio between the measured concentration and thelimiting concentration; the sum of these ratios for all radionuclides should be less than one (1) fordischarge to the basin.

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Table 2-5Radionuclide C oncentration Limits for the BWST

Maximum PermissibleIsotope Concentration, jiCi/ml

H-3 1.35Cr-51 6.76E-01Mn-54 4.06E-02Fe-59 1.35E-02Co-57 8.12E-02Co-58 2.70E-02Co-60 4.06E-03Zn-65 6.76E-03Rb-88 5.40E-01Sr-89 1.08E-02Sr-90 6.76E-04Sr-91 2.70E-02Sr-92 5.40E-02Y-90 9.46E-03Y-91 1.08E'02Y-93 2.70E-02Zr-95 2.70E-02Zr-97 1.22E-02Nb-95 4.06E-02Nb-97 4.06E-01Mo-99 2.70E-02Tc-99m 1.35Ru-103 4.06E-02

Ru- 106 4.06E-03Ag-110m 8.12E-03Sn-1 13 4.06E-02Sb-124 9.46E-03Sb-125 4.06E-021-131 1.35E-031-132 1.35E-011-133 9.46E-031-134 5.40E-011-135 4.06E-02Cs-134 1.22E-03Cs-136 8.12E-03Cs-137 1.35E-03Cs-138 5.40E-01Ba-139 2.70E-01Ba-140 1.08E-02La-140 1.22E-02Ce- 141 4.06E-02Ce-144 4.06E-03

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Table 2-6Davis-Besse Site-Specific Liquid Ingestion Dose Commitment Factors, Ajo(mrem/hr pe r iCi/ml)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 O.OOE+01 2.76E-01 2.76E-01 2.76E-01 2.76E-01 2.76E-01 2.76E-01C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03Na-24 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02 4.08E+02P-32 1.39E+06 8.62E+04 5.36E+04 O.OOE+01 O.OOE+01 O.OOE+01 1.56E+05Cr-51 O.OOE+01 O.OOE+O1 1.27E+00 7.62E-01 2.81E-01 1.69E+00 3.21E+02Mn-54 O.OOE+01 4.38E+03 8.35E+02 O.OOE+01 1.30E+03 O.OOE+01 1.34E+04Mn-56 O.OOE+01 1.1OE+02 1.95E+O1 O.OOE+01 1.40E+02 O.OOE+01 3.52E+03Fe-55 6.60E+02 4.56E+02 1.06E+02 O.OOE+01 O.OOE+O1 2.54E+02 2.61E+02Fe-59 1.04E+03 2.45E+03 9.38E+02 O.OOE+01 O.OOE+O1 6.84E+02 8.16E+03Co-57 O.OOE+O1 2.1OE+O1 3.50E+-O1 O.OOE+01 O.OOE+O1 O.OOE+01 5.34E+02Co-58 O.OOE+O1 8.95E+O1 2.01E+02 O.OOE+01 O.OOE+01 O.OOE+01 1.81E+03Co-60 O.OOE+O1 2.57E+02 5.67E+02 O.OOE+01 O.OOE+01 O.OOE+01 4.83E+03Ni-63 3.12E+04 2.16E+03 1.05E+03 O.OOE+01 O.OOE+O1 O.OOE+O1 4.51E+02Ni-65 1.27E+02 1.65E+01 7.51E+00 O.OOE+01 O.OOE+01 O.OOE+01 4.17E+02Cu-64 O.OOE+01 1.OOE+O1 4.70E+00 O.OOE+01 2.52E+01 O.OOE+01 8.53E+02Zn-65 2.32E+04 7.37E+04 3.33E+04 O.OOE+01 4.93E+04 O.OOE+01 4.64E+04Zn-69 4.93E+01 9.43E+O1 6.561+00 O.OOE+01 6.13E+O1 O.OOE+01 1.42E+O1Br-82 O.OOE+O1 O.OOE+01 2.27E+03 O.OOE+01 O.OOE+O1 O.OOE+01 2.61E+03Br-83 O.OOE+01 O.OOE+01 4.04E+O1 O.OOE+01 O.OOE+O1 O.OOE+01 5.82E+O1Br-84 O.OOE+O1 O.OOE+01 5.24E+O1 O.OOE+01 O.OOE+O1 O.OOE+01 4.11 E-04Br-85 O.OOE+O1 O.OOE+01 2.15E+00 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01Rb-86 O.OOE+O1 1.O1E+05 4.71E+04 O.OOE+01 O.OOE+01 O.OOE+01 1.99E+04Rb-88 O.OOE+O1 2.90E+02 1.54E+02 O.OOE+01 O.OOE+01 O.OOE+01 4.OOE-09Rb-89 O.OOE+01 1.92E+02 1.35E+02 O.OOE+O1 O.OOE+01 O.OOE+01 1.12E- 1ISr-89 2.23E+04 O.OOE+01 6.39E+02 O.OOE+O1 O.OOE+01 O.OOE+O1 3.57E+03Sr-90 5.48E+05 O.OOE+01 1.34E+05 O.OOE+O1 O.OOE+O1 O.OOE+O1 1.58E+04Sr-91 4.1OE+02 O.OOE+01 1.66E+01 O.OOE+01 O.OOE+01 O.OOE+01 1.95E+03Sr-92 1.55E+02 O.OOE+01 6.72E+00 O.OOE+O1 O.OOE+01 O.OOE+01 3.08E+03Y-90 5.80E-01 O.OOE+01 1.56E-02 O.OOE+01 O.OOE+01 O.OOE+01 6.15E+03Y-91m 5.48E-03 O.OOE+01 2.12E-04 O.OOE+01 O.OOE+01 O.OOE+01 1.61E-02Y-91 8.51E+00 O.OOE+0I 2.27E-01 O.OOE+01 O.OOE+O1 O.OOE+01 4.68E+03Y-92 5.1OE-02 O.OOE+01 1.49E'03 O.OOE+01 O.OOE+O1 O.OOE+01 8.93E+02Y-93 1.62E-01 O.OOE+O1 4.46E-03 O.OOE+01 O.OOE+O1 O.OOE+01 5.13E+03Zr-95 2.55E-01 8.17E-02 5.53E-02 O.OOE+01 1.28E-01 O.OOE+01 2.59E+02Zr-97 1.41E-02 2.84E-03 1.30E-03 O.OOE+01 4.29E-03 O.OOE+01 8.79E+02Nb-95 4.47E+02 2.48E+02 1.34E+02 O.OOE+01 2.46E+02 O.OOE+01 1.51E+06Nb-97 3.75E+00 9.48E-01 3.46E-01 O.OOE+01 1.11E+00 0.00E+O1 3.50E+03Mo-99 O.OOE+O1 1.05E+02 2.OOE+O1 O.OOE+01 2.38E+02 O.OOE+01 2.44E+02Tc-99m 8.99E-03 2.54E-02 3.23E-01 O.OOE+01 3.86E-01 1.24E-02 1.50E+01Tc-101 9.24E-03 1.33E-02 1.31E-01 O.OOE+01 2.40E-01 6.80E-03 4.OOE-14Ru-103 4.52E+00 O.OOE+O1 1.95E+00 O.OOE+O1 1.72E+01 O.OOE+O1 5.27E+02Ru-105 3.76E-01 O.OOE+O1 1.48E-01 O.OOE+01 4.86E+00 O.OOE+O1 2.30E+02Ru-106 6.71E+01 O.OOE+01 8.50E+00 O.OOE+01 1.30E+02 O.OOE+O1 4.35E+03

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Table 2-6 (Continued)Davis-Besse Site-Specific Liquid Ingestion Dose(mrem/hr per [XCi/ml) Commitment F actors, Aio

Nuclide BoneRh-103mRh-106Ag-110mSb- 124Sb-125Te-125mTe-127mTe-127Te-129mTe- 129Te-131mTe-131Te-1321-1301-1311-1321-133

"1-1341-135Cs-134Cs-136Cs-137Cs-138Ba-139Ba-140Ba-141Ba-142La- 140La- 142Ce- 141Ce-143Ce- 144Pr- 143Pr- 144Nd-147W-187Np-239

0.00E+01O.00E+019.57E-018.03E+005.14E+002.57E+036.49E+031.05E+02

1.10E+043.01E+011.66E+031.89E+012.41E+032.75E+011.5 1E+027.39E+005.17E+013.86E+001.61E+012.98E+053.12E+043.82E+052.64E+029.75E-012.04E+024.73E-012.14E-011.51E-017.72E-032.69E-024.73E-031.40E+005.55E-011.82E-033.79E-012.96E+022.9 1E-02

Liver0.00E+O 10.00E+018.85E-011.52E-015.74E-029.30E+022.32E+033.78E+O14.1 1E+031.13E+0 18.11E+027.88E+001.56E+038.11 E+012.16E+021.98E+018.99E+O11.05E+014.22E+0 17.09E+051.23E+055.22E+055.22E+026.95E-042.56E-013.58E-042.20E-047.60E-023.51E-031.82E-02

3.50E+005.85E-012.23E-017.54E-044.39E-012.47E+022.86E-03

T.Body Thyroid Kidney Lung GI-LLI0.00E+O 1O.00E+0 15.26E-013.19E+00

1.22E+003.44E+027.90E+022.28E+011.74E+037.33E+006.75E+025.96E+001.47E+033.20E+011.24E+026.9 1E+002.74E+013.75E+001.56E+O15.79E+058.86E+043.42E+052.59E+022.85E-021.34E+011.60E-021.35E-022.01E-028.75E-042.06E-033.87E-047.52E-022.75E-029.23E-052.62E-028.65E+011.57E-03

0.OOE+0 1O.OOE+0 10.OOE+0 11.95E-025.22E-037.72E+02

1.66E+037.81E+013.78E+032.3 1E+011.28E+031.55E+011.72E+036.88E+037. 1OE+046.91E+021.32E+041.82E+022.78E+03

O.OOE+0 10.OOE+0 10.OOE+0 10.00E+0 10.OOE+0 1O.OOE+0 10.OOE+0 10.OOE+010.OOE+010.OOE+010.OOE+010.OOE+0 10.OOE+010.OOE+0 10.OOE+010.OOE+010.OOE+0 10.OOE+0 1

0.OOE+010.OOE+011.74E+000.OOE+010.OOE+0 11.04E+042.63E+044.29E+024.60E+041.26E+028.21E+038.27E+0 I1.50E+041.27E+023.7 1E+023.15E+011.57E+021.67E+016.77E+012.29E+056.85E+041.77E+053.84E+026.49E-048.71E-023.33E-041.86E-040.00E+010.00E+018.44E-031.54E-033.47E-011.28E-014.25E-042.56E-01

0.OOE+018.91E-03

0.00E+0 10.00E+0 10.OOE+0 16.26E+003.96E+00O.OOE+010.OOE+010.OOE+010.00E+010.OOE+010.OOE+010.OOE+010.OOE+010.OOE+0 10.00E+0 10.00E+010.00E+0 10.00E+010.00E+0 17.6 1E+049.39E+035.89E+043.79E+013.94E-041.47E-012.03E-041.25E-040.00E+O 1

0.00E+0 10.00E+0 10.OOE+010.00E+0 1O.00E+0 10.OOE+0 1O.00E+0 1O.00E+0 10.00E+0 1

0.OOE+010.OOE+013.6 1E+022.28E+025.65E+011.03E+042.17E+048.32E+035.55E+042.27E+018.05E+042.67E+007.39E+046.99E+O 15.71E+013.71E+008.08E+0 19.13E-034.77E+011.24E+041.40E+041.01E+042.23E-031.73E+004.20E+022.23E-103.02E- 195.58E+032.56E+016.94E+0 11.3 1E+024.73E+022.43E+032.61E-102.1 1E+038.1OE+045.86E+02

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Table 2-7Bioaccumulation Factors (BFi)(pCi/kg per pCi/liter)*

Element Freshwater FishH 9.OE-01C 4.6E+03Na 1.OE+02P 3.OE+03Cr 2.OE+02Mn 4.OE+02Fe 1.OE+02Co 5.OE+01Ni 1.OE+02Cu 5.OE+01Zn 2.OE+03Br 4.2E+02Rb 2.OE+03Sr 3.OE+01Y 2.5E+01Zr 3.3E+00Nb 3.OE+04Mo 1.OE+01Tc 1.5E+01Ru 1.OE+01Rh 1.OE+01Ag 2.3E+00Sb 1.OE+00Te 4.OE+02I 1.5E+01Cs 2.OE+03Ba 4.OE+00La 2.5E+01Ce 1.OE+00Pr 2.5E+O1Nd 2.5E+01W 1.2E+03Np 1.OE+01

* Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which is adaptedfrom NUIREG/CR-1336 and silver and antimony which are taken from UCRL 50564, Rev. 1,October 1972.

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Table 2-8Davis-Besse Site-Specific Liquid Pathway Dose Commitment Factors, Ashore,IFor Releases to the Training Center Pond(mrem/hr per gtCi/ml)Nuclide BoneH-3C-14Na-24P-32Cr-51Mn-54Mn-56Fe-55Fe-59Co-57Co-58Co-60Ni-63Ni-65Cu-64Zn-65Zn-69Br-82Br-83Br-84Br-85Rb-86Rb-88Rb-89Sr-89Sr-90Sr-9 ISr-92Y-90Y-91mY-91Y-92Y-93Zr-95Zr-97Nb-95Nb-97Mo-99Tc-99mTc-101Ru- 103Ru- 105Ru-106

0.OOE+000.OOE+002.1OE+000.OOE+001.388E+004.02E+021.08E-020.OOE+008.18E+019.49E+O 11.14E+026.43E+030.OOE+003.28E-039.50E-022.23E+020.OOE+009.08E+004.58E-059.29E-090.OOE+002.64E+005.52E- 152.OOE-166.43E-030.OOE+002.77E-011.08E-021.18E-031.39E-063.21E-015.11 E-032.46E-027.41E+015.38E-014.05E+O11.14E-041.07E+001.37E-023.33E-183.24E+O12.93E-021.26E+02

Liver0.OOE+00O.OOE+002.1OE+000.OOE+001.38E+004.02E+021.08E-020.OOE+008.18E+0 1'9.49E+O 11.14E+026.43E+03O.OOE+003.28E-039.50E-022.23E+020.OOE+009.08E+004.58E-059.29E-090.OOE+002.64E+005.52E-152.OOE-166.43E-030.OOE+002.77E-011.08E-021.18E-031.39E-063.21E-015.11E-032.46E-027.4 1E+015.38E-014.05E+011.14E-041.07E+001.37E-023.33E-183.24E+012.93E-021.26E+02

T.Body Thyroid KidneyO.OOE+000.OOE+002.10E+000.OOE+001.38E+004.02E+021.08E-020.OOE+008.18E+019.49E+0 11.14E+026.43E+030.OOE+003.28E-039.50E-022.23E+020.OOE+009.08E+004.58E-059.29E-090.OOE+002.64E+005.52E- 152.OOE-166.43E-030.OOE+002.77E-0 11.08E-021.1 8E-031.39E-063.21 E-0 15.11E-032.46E-027.41E+015.38E-014.05E+0 11.14E-041.07E+001.37E-023.33E-183.24E+012.93E-021.26E+02

0.OOE+000.OOE+002.1OE+000.OOE+001.38E+004.02E+02.1.08E-020.OOE+008.18E+019.49E+0 11.14E+026.43E+030.OOE+003.28E-039.50E-022.23E+020.OOE+009.08E+004.58E-059.29E-090.OOE+002164E+005.52E-152.OOE-166.43E-030.OOE+002.77E-011.08E-021.18E-031.39E-063.2 1E-015.1 1E-032.46E-027.41 E+O 15.38E-014.05E+011.14E-041.07E+001.37E-023.33E-183.24E+012.93E-021.26E+02

0.OOE+000.OOE+002.1OE+000.OOE+001.3 8E+004.02E+021.08E-020.OOE+008.18E+019.49E+0 11.14E+026.43E+030.OOE+003.28E-039.50E-022.23E+020.OOE+009.08E+004.58E-059.29E-090.OOE+002.64E+005.52E-152.OOE-166.43E-030.OOE+002.77E-0 11.08E-021.1 8E-031.39E-063.21E-015.11E-032.46E-027.41E+015.38E-014.05E+0 I1.14E-041.07E+001.37E-023.33E-183.24E+0 12.93E-021.26E+02

Lung0.OOE+000.OOE+002.1OE+000.OOE+001.38E+004.02E+021.08E-020.OOE+008.18E+0 19.49E+0 11.14E+026.43E+030.OOE+003.28E-039.50E-022.23E+02O.OOE+009.08E+004.58E-059.29E-090.OOE+002.64E+005.52E-152.OOE-166.43E-030.OOE+002.77E-011.08E-021.18E-031.39E-063.21E-015.11 E-032.46E-027.41E+015.3 8E-0 14.05E+011.14E-041.07E+001.37E-023.33E-183.24E+012.93E-021.26E+02

GI-LLI0.OOE+000.OOE+002.1 OE+000.OOE+001.38E+004.02E+021.08E-020.OOE+008.18E+019.49E+0 11.14E+026.43E+030.OOE+003.28E-039.50E-022.23E+020.OOE+009.08E+004.58E-059.29E-090.OOE+002.64E+005.52E-152.OOE-166.43E-030.OOE+002.77E-011.08E-021.18E-031.39E-063.21E-015.11E-032.46E-027.41E+015.38E-014.05E+O I1.14E-041.07E+001.37E-023.33E-183.24E+012.93E-021.26E+02

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Table 2-8 (Continued)DaviszBesse Site-Specific Liquid Pathway Dose Commitment Factors, AshoreI

For Releases to the Training Center Pond(mrem/hr per pCi/ml)

Nuclide Bone

Rh-103mRh-106Ag-110mSb-124Sb-125Te-125mTe-127mTe-127Te-129mTe- 129Te-131mTe-131Te-1321-1301-1311-1321-1331-1341-135Cs-134.Cs-136Cs-137Cs-138Ba-139Ba-140Ba-141Ba-142La-140La-142Ce-141Ce-143Ce-144Pr- 143Pr- 144Nd-147W-187Np-239

0.OOE+000.OOE+001.04E+033.13E+021.26E+034.62E-0 12.74E-023.7 1E-045.94E+005.62E-061.82E+001.97E- 1I1.14E+008.48E-014.95E+001.OOE-024.99E-0 11.07E-052.22E-0 1.2.02E+034.35E+O13.08E+032.OOE-087.96E-055.99E+001.08E-147.48E-234.66E+009.95E-044.04E+005.41E-012.08E+01O.OOE+001.58E-162.44E+004.99E-0 14.41E-01

Liver0.OOE+00O.OOE+001.04E+033.13E+021.26E+034.62E-0 12.74E-023.7 1E-045.94E+005.62E-061.82E+001.97E-1 11.14E+008.48E-014.95E+001.OOE-024.99E-0 11.07E-052.22E-0 12.02E+034.35E+013.08E+032.OOE-087.96E-055.99E+001.08E-147.48E-234 66E+009.95E-044.04E+005.4 1E-012.08E+010.OOE+001.58E-162.44E+004.99E-0 14.4 1E-01

T.Bodv Thyroid Kidney0.OOE+000.OOE+001.04E+033.13E+021.26E+034.62E-0 12.74E-023.7 1E-045.94E+005.62E-061.82E+001.97E-1 11.14E+008.48E-0 14.95E+001.OOE-024.99E-011.07E-052.22E-012.02E+034.35E+013.08E+032.OOE-087.96E-055.99E+001.08E-147.48E-234.66E+009.95E-044.04E+005.41E-012.08E+0 10.00E+001.58E-162.44E+004.99E-0 14.41E-01

O.OOE+000.OOE+001.04E+033.13E+021.26E+034.62E-012.74E-023.71E-045.94E+005.62E-061.82E+001.97E- 1I1.14E+008.48E-014.95E+001.OOE-024.99E-0 11.07E-052.22E-0 12.02E+034.35E+013.08E+032.OOE-087.96E-055.99E+001.08E-147.48E-234.66E+009.95E-044.04E+005.41E-012108E+010.OOE+001.58E-162.44E+004.99E-0 14.41E-01

O.OOE+000.OOE+001.04E+033.13E+021.26E+034.62E-0 I2.74E-023.71 E-045.94E+005.62E-061.82E+001.97E- 1I1.14E+008.48E-014.95E+001.OOE-024.99E-0 11.07E-052.22E-0 12.02E+034.35E+O13.08E+032.00E-087.96E-055.99E+001.08E-147.48E-234.66E+009.95E-044.04E+005.41E-012.08E+010.OOE+001.58E-162.44E+004.99E-0 14.41E-01

Lung0.OOE+000.00E+001.04E+033.13E+021.26E+034.62E-0 12.74E-023.71E-045.94E+005.62E-061.82E+001.97E-111.14E+008.48E-014.95E+001.OOE-024.99E-0 11.07E-052.22E-0 12.02E+034.35E+013.08E+032.OOE-087.96E-055.99E+001.08E-147.48E-234.66E+009.95E-044.04E+005.41E-012.08E+010.OOE+001.58E-162.44E+004.99E-0 14.41E-01

GI-LLI0.OOE+000.OOE+001.04E+033.13E+021.26E+034.62E-012.74E-023.71E-045.94E+005.62E-061.82E+001.97E-111.14E+008.48E-014.95E+001.OOE-024.99E-0 11.07E-052.22E-0 12.02E+034.35E+O13.08E+032.OOE-087.96E-055.99E+001.08E-147.48E-234.66E+009.95E-044.04E+005.41E-012.08E+01O.OOE+001.58E-162.44E+004.99E-0 14.41E-01

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LEGEND

INTAKE

O TANK( RADIATIONMONITOR.9 PUMPREQUIRED* RAD MONITORISOLATIONVALVE

0

00~1

~100

It

;;.


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3.0 QASEOUS EFFLUENTS3.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS

This Section specifies the gaseous effluent monitoring instrumentation required atDavis-Besse fo r controlling and monitoring radioactive effluents. Location and controlfunction of these monitors are displayed in Figure 3-1. More information is provided in theDavis-Besse USAR, Section 11.3, Gaseous Waste System.Th e radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-1shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Section3.3 are not exceeded. The alarm/trip setpoints of these channels shall be determined andadjusted in accordance with the methodology and parameters in Section 3.3.With a radioactive gaseous effluent m onitoring instrumentation channel alarm/trip setpointless conservative than required, without delay suspend the release of radioactive gaseouseffluents monitored by the affected channel, or declare the channel nonfunctional, or changethe setpoint so it is acceptably conservative.

With less than the required number of radioactive gaseous effluent monitoringinstrumentation channels FUNCTIONAL, take the actions shown in Table 3-1. Exert bestefforts to return the instruments to FUNCTIONAL status within 30 days and, if unsuccessful,explain in the next Radioactive Effluent Release Report (Section 7.2) why the non-functionality was not corrected in a timely manner.Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstratedFUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNELCALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shownin Table 3-2. Each of these operations shall be performed within the specified time intervalwith a maximum allowable extension not to exceed 25 percent of the specified interval.NOTE: The monitors specified in Table 3-2 are nonfunctional if verifications are notperformed or setpoints are less conservative than required.The radioactive gaseous effluent instrumentation is provided to monitor and control, asapplicable, the releases :of radioactive materials in gaseous effluents during actual or potentialreleases. The alarm/trip setpoints for these instruments shall be calculated in accordance withmethods in Section 3.3 to ensure thatthe alarm/trip will occur prior to exceeding the limits of10 CF R Part 20. The FUNCTIONALITY and use of this instrumentation is consistent withthe requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CF R Part 50.

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3.1.1 Alarm and Automatic Release Terminationa) Waste Gas Decay System Monitor (RE- 1822 A&B)

The radioactive waste gas discharge line is continuously monitored by two off-linedetectors, each measuring gross activity. The monitors' control function willterminate the waste discharge prior to exceeding the release rate limits of Section3.3.2. Table 3-1 requires that the Waste Gas Decay System contain as a minimum thefollowing instrumentation:

noble gas activity monitor (RE-1822 A or B), andeffluent system flow rate measuring device (FT-1821 or 1821 A).

If both noble gas monitors are declared nonfunctional, then the contents of the tankmay be released provided that prior to the release:

at least two independent gas samples are collected and analyzed by gammaspectroscopy for principal gamma emitters (noble gases),at least two independent verifications of the release rate calculations areperformed, andat least two independent verifications of the discharge valve line-up areperformed.

If the flow rate device is nonfunctional, effluent releases may continue provided thatthe flow rate is estimated at least once per 12 hours. Flow rates may be estimatedbased on fan curves or discharge valve header positioning.

b) Containment Purge Exhaust Filter Monitor (RE-5052 AB&C)This detector monitors the containment atmosphere for radioactivity duringContainment VENT or PURGE. The noble gas activity monitor (Channel C) isrequired by Table 3-1. It provides an automatic termination of the release prior toexceeding the release rate limits of Section 3.3.2. Although not required in order tocomply with Table 3.1, Channels A and B provide indications of increasing levels ofparticulate and radioiodine releases and terminate the release if their high alarmsetpoint is exceeded.

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3.1.2 Alarm Onlya) Station Vent Monitor (RE-4598 AA , BA)

The Station Vent is designed as the final release point for all gaseous radioactiveeffluents. Three separate channels (1, 2, and 3) are provided for each monitoringsystem. Channel 1 is a beta scintillation detector viewing a fixed air volumemeasuring for noble gases. Channel 2 is a beta scintillation detector viewing a fixedparticulate filter sampler. Channel 3 is a gamma scintillation detector viewing a fixedcartridge sampler (e.g., charcoal). Only the Channel 1 radiation detector is requiredby Table 3.1.The Channel 2 and Channel 3 detectors provide information on potential particulateand radioiodine releases. However, those monitors experience wide variations inresponse due, in part, to the much more abundant noble gases in the effluent streamrelative to the particulate or radioiodines being sampled. Therefore, while Channels 2and 3 provide useful information for identifying particulate and radioiodine releases,they are not required by Table 3.1 for quantifying the release rate. Refer to Section3.5.The following sampling and/or monitoring instrumentation on the Station Vent isrequired by Table 3-1:

noble gas activity monitor (Channel 1),particulate sampler filter,iodine sampler cartridge,sampler flow rate measuring device, and

unit vent flow rate measuring device (computer points F883 or F885).The hydrogen purge line serves as a Containment pressure relief route to the StationVent. A separate radiation monitor on this line is not required. Any release throughthe hydrogen purge line will be monitored by the Station Vent monitor, RE-4598.

b) Waste Gas System Oxygen Monitors (AE 5984 and 6570)The Waste Gas System is provided with two oxygen monitors (with an alarmS function) as required by Table 3-1 to alert operators in the unlikely event of oxygenleakage into the waste gas header. The concentration of oxygen is limited to less thanor equal to 2% by volume whenever the hydrogen concentration exceeds 4% byvolume. An oxygen concentration above the specified limit will actuate a local andcontrol room alarm (TS 5.5.1 .a as implemented by TRM 8.7.5).

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3.2 SAMPLING AND ANALYSIS OF GASEOUS EFFLUENTSRadioactive gaseous wastes shall be sampled and analyzed in accordance with Table 3-3.This sampling and analysis ensures that the dose rates and doses from gaseous effluentsremain below the release rate limits of Section 3.3.2, and the dose limits of Sections 3.7.1 and3.8.1.

3.2.1 Batch ReleasesTable 3-3 requires that a grab gas sample be collected and analyzed prior to each BATCHRELEASE from the Waste Gas Decay Tanks (WGDT) or a Containment PURGE. Theanalysis shall include the identification of all principal gamma emitters (noble gas) andtritium. Although not required by Table 3-3, Containment Pressure releases, Integrated LeakRate Tests of Containment, and other tank venting operations are batch releases and shall besampled similarly.Th e results of the sample analysis are used to establish the acceptable release rate inaccordance with Section 3.3.5. This evaluation is necessary to ensure compliance with thelimits of Section 3.3.2.

3.2.2 Continuous ReleaseAll releases from the Station Vent are required to be continuously sampled for radioactivity.As specified in Table 3-3, the following minimum samples and analyses are required:- once per week, analysis of an absorption media (e.g., charcoal cartridge) for 1-131,

once per week, analysis of a filter sample for all principal gamma emitters (particulateradioactive material),once per month, analysis of a grab gas sample for all principal gamma emitters (noblegas) and tritium,once per month, analysis of a composite of the particulate samples of all releases forthat month for gross alpha activity,once per quarter, analysis of a composite of the particulate samples for all releases forthat quarter for Sr-89 and 90, andcontinuous monitoring for noble gases (gross beta and gamma activity).

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3.2.3 Releases Resulting from Primary-to-Secondary System LeakageDue to secondary coolant system contamination, there are several additional gaseous releasepoints to consider:

The Atmospheric Vent Valves (AVVs) weepage - continuous ground level releaseMain Steam System Relief Valves (MSSVs) - batch ground level releaseAuxiliary Feed Pump Turbines (AFPTs) - batch ground level releaseAuxiliary Steam System Relief Valves (235#, 15#, 50#, 5# Relief Valves )- batchground level releaseAuxiliary Boiler Relief Valve - batch ground level release

Steam may be released via any of these points due to improper valve seating. Steam may bereleased via the MSSVs and AVVs if the plant trips, or via the AVVs during a condenseroutage. Steam is released through the AFPTs during their operation. Steam may be releaseddue to overpressurization of the Auxiliary Steam System via the relief valves on the varioussteam headers.Fo r secondary coolant system release pathways, the following minimum samples and analysesare required:

once per week, analysis of a secondary system off-gas sample for principal gammaemitters (noble gases) and tritium;- once pe r week, analysis of condensate sample for principal gamma emitters (iodinesand particulates) and tritium;

once pe r quarter, analysis of a composite of condensate samples for strontium-89 andstrontium-90.To supplement the above requirements, the moisture separator drain tank liquid may beanalyzed for principal gamma emitters (iodines and particulants)Liquid samples are analyzed from Condensate during normal operations, and from theAuxiliary Boiler during Modes 5 and 6. Fo r Auxiliary Steam System Relief lifts that occurwhen the Auxiliary Boiler is the source of Auxiliary Steam, liquid samples from the AuxiliaryBoiler are analyzed for principal gamma emitters (iodines and particulates) and tritium.If only-one steam generator has a primary-to-secondary leak, then radionuclides other thantritium are released through the valves on the leaking steam generator's main steam line.Demineralizing and gas stripping remove some radionuclides from the condensate prior to itsreturn to the steam generator as feedwa ter. How ever, these processes do not remove tritium.

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3.3 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION3.3.1 Total Effective Dose Equivalent Limits

10 CFR 20.1301 limits the total effective dose equivalent, (TEDE), to individual members ofthe public from all licensed operations to 100 mrem in a year. At Davis-Besse, the totaleffective dose equivalent due to radioactive materials released in gaseous effluents at theboundary of the unrestricted area shall be limited to 50 mrem in a year.3.3.2 Release Rate Limits

All releases of gaseous radioactive effluents are designed to occur via the Station Vent.Station Vent alarm setpoints shall be established to initiate Control Room isolation when theactivity level exceeds the Derived Air Concentration limits of 10 CF R 20 and to ensurerelease rate of noble gas, radioiodine and particulates effluent does not exceed any 10 CF Rlimit.This may be demonstrated by ensuring that:a. The annual average gaseous effluent concentrations at the boundary of theunrestricted area do not exceed the values specified in Table 2 of Appendix B of

10 CF R 20.For batch and intermittent releases (e.g. containment purges, etc.), compliance may bedemonstrated by ensuring that:b. Airborne effluent concentrations at the boundary of the unrestricted area do notexceed ten times the values specified in Table 2 of Appendix B of 10 CF R 20

averaged over one hour.or

Noble gas: to less than or equal to 500 mrem/year, averaged over one hour, to thetotal body, (Deep Dose Equivalent, DDE) and to less than or equal to 3000 mrem/yearaveraged over one hour to the skin, (Skin Dose Equivalent, SDE), andIodine 131, Tritium and all radionuclides in particulate form with half-lives greaterthan 8 days: to less than or equal to 1500 mrem/year averaged over one hour to anyorgan.

Should dose rate(s) exceed the above limits of a. or b., without delay restore the release rate towithin the above limit(s).These requirements ensure that the total effective dose equivalent at the UNRESTRICTEDAREA BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CF RPart 20 for individual members of the public.For INDIVIDUAL MEMBERS OF THE PUBLIC who may at times be within theUNRESTRICTED AREA BOUNDARY, the occupancy of that MEMBER OF TH E PUBLICwill be sufficiently low to compensate for any increase in the atmospheric diffusion factorabove that for the UNRESTRICTED AREA BOUNDARY.

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3.3.3 Individual Release Radiation Monitor SetpointsAlthough generic radiation monitor setpoints are normally used at Davis-Besse (see Section3.3.4), setpoints may be established from a sample analysis of the applicable source (i.e.,Station Vent, Waste Gas Decay Tanks, or Containment atmosphere), and the followingequations:

Z Ci *5004 7 2 *x/QNG * VF* X(Ci * Kj)

SPs = ZC* 3000 (3-2)472*z/QNG *VF* E(Ci *(Li +1.1Mj))

where:SPTB = monitor setpoint corresponding to the release rate limit for the totalbody dose rate of 500 mrem per year (pCi/ml),SPs = monitor setpoint corresponding to the release rate limit for the skin

dose rate of 3000 mrem per year (IiCi/ml),500 = total body dose rate limit (mrem/yr),3000 = skin dose rate limit (mrem/yr),X/QNo = atmospheric X/ Q value for direct exposure to noble gas at theUNRESTRICTED AREA BOUNDARY given in Table 3-6 (sec/mi3),VF = ventilation system flow rate for the applicable release point and

monitor (ft3/minute),Ci = concentration of noble gas radionuclide "i" as determined by gammaspectral analysis of grab sample (IiCi/ml),Ki = total body dose conversion factor for radionuclide "i" (mrem/yr per

PCi/m 3) from Table 3-5,Li = beta skin dose conversion factor for radionuclide "i" (mrem/yr per

1 tCi/m 3) from Table 3-5,Mi = gamma air dose conversion factor for radionuclide "i" (mrad/yr per

jiCi/m3) from Table 3-5,1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad), and472 = 28,317 (ml/ft3) * 1/60 (min/sec).

The lesser value of SPT or SPs is used to establish the monitor setpoint.

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The Station Vent monitor (RE-4598) efficienc

besse offsite dose calculation manual, rev. 24

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