ML031290259

January - December 2002 Radioactive Effluent Release Report, Part II Through Figure D 5.1-2a

ML031290259
Person / Time
Site:	Nine Mile Point
Issue date:	05/01/2003
From:	Conway J Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031290259 (108)

Text

PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS Service Water A and B, Cooling Tower Blowdown and the Liquid Radioactive Waste Discharges comprise the Radioactive Liquid Effluents at Unit 2. Presently there are no temporary outdoor tanks containing radioactive water capable of affecting the nearest known or future water supply in an unrestricted area. NUREG 0133 and Regulatory Guide 1.109, Rev. 1were followed in the development of this section.

1.1 Liquid Effluent Monitor Alarm Setpoints 1.1.1 Basis The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure D 1.0-1) shall be limited to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained nobles gases, the concentration shall be limited to 2E-04 uCi/ml total activity.

1.1.2 Setpoint Determination Methodology 1.1.2.1 Liquid Radwaste Effluent Radiation Alarm Setpoint The Liquid Radioactive Waste System Tanks are pumped to the discharge tunnel which in turn flows directly to Lake Ontario. At the end of the discharge tunnel in Lake Ontario, a diffuser structure has been installed. Its purpose is to maintain surface water temperatures low enough to meet thermal pollution limits. However, it also assists in the near field dilution of any activity released. Service Water and the Cooling Tower Blowdown are also pumped to the discharge tunnel and will provide dilution. If the Service Water or the Cooling Tower Blowdown is found to be contaminated, then its activity will be accounted for when calculating the permissible radwaste effluent flow for a Liquid Radwaste discharge. The Liquid Radwaste System Monitor provides alarm and automatic termination of release if radiation levels above its alarm setpoint are detected.

The radiation detector is a sodium iodide crystal. It is a scintillation device. The crystal is sensitive to gamma and beta radiation. However, because of the metal walls of the sample chamber and the absorption characteristics of water, the monitor is not particularly sensitive to beta radiation. Actual detector response Y, (cGj/cFj , cpm, has been evaluated by placing a sample of typical radioactive waste into the monitor and recording the gross count rate, cpm. A calibration ratio was developed by dividing the noted detector response, Ad (CGI/CFi) cpm, by total concentration of activity Y, (CG,), uCi/cc. The quantification of the gamma activity was completed with gamma spectrometry equipment whose calibration is traceable to NIST. This calibration ratio verified the manufacturer's prototype calibration, and any subsequent transfer calibrations performed. The current calibration factor (expressed as the reciprocal conversion factor, uCi/ml/cpm), will be used for subsequent setpoint calculations in the determination of detector response:

-1 (CG 1 /CFj) = En (CG,) /CF Unit 2 Revision 23 II 2 December 2002

Where the factors are as defined above.

For the calculation of RDF = E MEC fraction = t (Cj/MECi) the contribution from non gamma emitting nuclides except tritium will be initially estimated based on the expected ratios to quantified nuclides as listed in the FSAR Table 11.2.5. Fe-55, Sr-89 and Sr-90 are 2.5, 0.25 and 0.02 times the concentration of Co-60. The contribution will be estimated using the results from the latest analysis of composite samples, when available.

Tritium concentration is assumed to equal the latest concentration detected in the monthly tritium analysis (performed offsite) of liquid radioactive waste tanks discharged.

Nominal flow rates of the Liquid Radioactive Waste System Tanks discharged is

< 165 gpm while dilution flow from the Service Water Pumps, and Cooling Tower Blowdown cumulatively is typically over 10,200 gpm. Because of the large amount of dilution the alarm setpoint could be substantially greater than that which would correspond to the concentration actually in the tank. Potentially a discharge could continue even if the distribution of nuclides in the tank were substantially different from the grab sample obtained prior to discharge which was used to establish the detector alarm point. To avoid this possibility of "Non representative Sampling" resulting in erroneous assumptions about the discharge of a tank, the tank is recirculated for a minimum of 2.5 tank volumes prior to sampling.

This monitor's setpoint takes into account the dilution of Radwaste Effluents provided by the Service Water and Cooling Tower Blowdown flows. Detector response for the nuclides to be discharged (cpm) is multiplied by the Actual Dilution Factor (dilution flow/waste stream flow) and divided by the Required Dilution Factor (total fraction of the effluent concentration in the waste stream). A safety factor is used to ensure that the limit is never exceeded. Service Water and Cooling Tower Blowdown are normally non-radioactive. If they are found to be contaminated prior to a Liquid Radwaste discharge then-an alternative equation is used to take into account the contamination. If they become contaminated during a Radwaste discharge, then the discharge will be immediately terminated and the situation fully assessed.

Normal Radwaste Effluent Alarm Setpoint Calculation:

Alarm Setpoint < 0.8

• TDF/PEF

• TGC/CF

• 1/RDF + Background.

Where:

Alarm Setpoint = The Radiation Detector Alarm Setpoint, cpm 0.8 = Safety Factor, unitless TDF = Nonradioactive dilution flow rate, gpm. Service Water Flow (ranges from 30,000 to 58,000 gpm) +

Blowdown flow (typically 10,200 gpm) - Tempering Unit 2 Revision 23 II 3 December 2002

C; = Concentration of isotope i in Radwaste tank prior to dilution, tCi/ml (gamma + non-gamma emitters)

CF2 = Detector response for isotope i, net ZCi/ml/cpm See Table D 2-1 for a list of nominal values PEF = The permissible Radwaste Effluent Flow rate, gpm, 165 gpm is the maximum value used in this equation MEC, = Maximum Effluent Concentration, ten times the limiting effluent concentration for isotope i from 10 CFR 20 Appendix B, Table 2, Column 2, ptCi/ml Background = Detector response when sample chamber is filled with nonradioactive water, cpm CF = Monitor Conversion Factor, tCi/ml/cpm, determined at each calibration of the effluent monitor CG, Concentration of gamma emitting nuclide in Radwaste tank prior to dilution, tCi/ml TGC = YCGi = Summation of all gamma emitting nuclides (which monitor will respond to)

E (CGj/CFj = The total detector response when exposed to the concentration of nuclides in the Radwaste tank, cpm RDF = Yt (Cj/MEC,) = The total fraction of ten times the 10 CFR.20, Appendix B, Table 2, Column 2 limit that is in the Radwaste tank, unitless. This is also known as the Required Dilution Factor (RDF), and includes non-gamma emitters TGCICF - An approximation to Yj (cG/cFi) using CF determined at each calibration of the effluent monitor TDF/PEF = An approximation to (TDF + PEF)/PEF, the Actual Dilution Factor in effect during a discharge.

Tempering = A diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control, gpm.

Permissible effluent flow, PEF, shall be calculated to determine that the maximum effluent concentration will not be exceeded in the discharge canal.

PEF = TDF (RDF) 1.5 If Actual Dilution Factor is set equal to the Required Dilution Factor, then the alarm points required by the above equations correspond to a concentration of 80% of the Radwaste Tank concentration. No discharge could occur, since the monitor would be in alarm as soon as the discharge commenced. To avoid this situation, maximum allowable radwaste discharge flow is calculated using a multiple (usually 1.5 to 2) of the Required Dilution Factor, resulting in discharge canal concentration of 2/3 to 1/2 of the maximum effluent concentration prior to alarm and termination of release. In Unit 2 Revision 23 II 4 December 2002

performing the alarm calculation, the smaller of 165 gpmn (the maximum possible flow) and PEF will be used.

To ensure the alarm setpoint is not exceeded, an alert alarm is provided. The alert alarm will be set in accordance with the equation above using a safety factor of 0.5 (or lower) instead of 0.8.

1.1.2.2 Contaminated Dilution Water Radwaste Effluent Monitor Alarm Setpoint Calculation:

The allowable discharge flow rate for a Radwaste tank, when one of the normal -

dilution streams (Service Water A, Service Water B, or Cooling Tower Blowdown) is contaminated, will be calculated by an iterative process. Using Radwaste tank concentrations with a total liquid effluent flow rate, the resulting fraction of the maximum effluent concentration in the discharge canal will be calculated.

FMEC = F. [Fs/s (Fs)Yi (cit + MEC)J Then the permissible radwaste effluent flow rate is given by:

PEF = Total Radwaste Effluent Flow FMEC The corresponding Alarm Setpoint will then be calculated using the following equation, with PEF limited as above.

TGC/CF Alarm Setpoint < 0.8 + Background FMEC Where:

Alarm Setpoint = The Radiation Detector Alarm Setpoint, cpm 0.8 - Safety Factor, Unitless F. = An Effluent flow rate for stream s, gpm C, = Concentration of isotope i in Radwaste tank prior to dilution, gCi/ml Cs, = Concentration of isotope i in Effluent stream s including the Radwaste Effluent tank undiluted, 1Ci/ml CF - Average detector response for all isotopes in the waste stream, net ,Ci/ml/cpm MEC, = Maximum Effluent Concentration, ten times the effluent concentration limit for isotope i from 10CFR20 Appendix B, Table 2, Column 2, 9Ci/ml PEF - The permissible Radwaste Effluent Flow rate, gpm Background = Detector response when sample chamber is filled with nonradioactive water, cpm Unit 2 Revision 23 II 5 December 2002

TGC/CF = = The total detector response when exposed to the Y (CGi/CF) concentration of nuclides in the Radwaste tank, cpm S EF.ciA = The total activity of nuclide i in all Effluent streams, pCi-gpm/ml

.[F 5 = The total Liquid Effluent Flow rate, gpm

• (Service Water & CT Blowdown & Radwaste) 1.1.2.3 Service Water and Cooling Tower Blowdown Effluent Alarm Setpoint These monitor setpoints do not take any credit for dilution of each respective effluent stream. Detector response for the distribution of nuclides potentially discharged is divided by the total MEC fraction of the radionuclides potentially in the respective stream. A safety factor is used to ensure that the limit is never exceeded.

Service Water and Cooling Tower Blowdown are normally non-radioactive. If they are found to be contaminated by statistically significant increase in detector response then grab samples will be obtained and analysis meeting the LLD requirements of Table D 3.1.1-1 completed so that an estimate of offsite dose can be made and the situation fully assessed.

Service Water A and B and the Cooling Tower Blowdown are pumped to the discharge tunnel which in turn flows directly to Lake Ontario. Normal flow rates for each Service Water Pump is 10,000 gpm while that for the Cooling Tower Blowdown may be as much as 10,200 gpm. Credit is not taken for any dilution of these individual effluent streams.

The radiation detector is a sodium iodide crystal. It is a scintillation device. The crystal is sensitive to gamma and beta radiation. However, because of the metal walls in its sample chamber and the absorption characteristics of water, the monitor is not particularly sensitive to beta radiation.

Detector response Ei (ci/cFi) has been evaluated by placing a diluted sample of Reactor Coolant (after a two hour decay) in a representative monitor and noting its gross count rate. Reactor Coolant was chosen because it represents the most likely contaminant of Station Waters.

A two hour decay was chosen by judgement of the staff of Nine Mile Point. Reactor Coolant with no decay contains a considerable amount of very energetic nuclides which would bias the detector response term high. However assuming a longer than 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> decay is not realistic as the most likely release mechanism is a leak through the Residual Heat Removal Heat Exchangers which would contain Reactor Coolant during shutdowns.

Unit 2 Revision 23 II 6 December 2002

Service Water and Cooling Tower Blowdown Alarm Setpoint Equation:

Alarm Setpoint < 0-8 1/CF £ Ci/[E (ci/MEci)] + Background.

Where:

Alarm Setpoint The Radiation Detector Alarm Setpoint, cpm 0.8 Safety Factor, unitless C' Concentration of isotope i in potential contaminated stream, 9Ci/ml CF1 Detector response for isotope i, net 9Ci/ml/cpmn See Table 2-1 for a list of nominal values MECL Maximum Effluent Concentration, ten times the effluent concentration limit for isotope i from 10 CFR 20 Appendix B, Table 2, Column 2, ^Ci/ml Background Detector response when sample chamber is filled with nonradioactive water, cpm

£ (Ci/CF1 ) The total detector response when exposed to the concentration of nuclides in the potential contaminant, cpm Yi (CI/MEC i ) The total fraction of ten times the 10CFR20, Appendix B, Table 2, Column 2 limit that is in the potential contaminated stream, unitless.

(1/CF) YiCj An approximation to yi ccj/cF ), determined at each calibration of the effluent monitor CF Monitor Conversion Factor, ptCi/ml/cpm 1.2 Liquid Effluent Concentration Calculation This calculation documents compliance with Section D 3.1.1 of Part I:

As required by Technical Specification 5.5.4, "Radioactive Effluent Controls Program," the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure D 1.0-1) shall be limited to ten times the concentrations specified in 10 CFR 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 2E-04 microcurie/ml total activity.

The concentration of radioactivity from-Liquid Radwaste, Service Water A and B and the Cooling Tower Blowdown are included in the calculation. The calculation is performed for a specific period of time. No credit is taken for averaging. The limiting concentration is calculated as follows:

FMEC E.[Fs/ls(Fs)Xi(Cis MECi) ]

Where: FMEC = The Fraction of Maximum Effluent Concentration, the ratio at the point of discharge Unit 2 Revision 23 II 7 December 2002

of the actual concentration to ten times the limiting concentration of 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases, unitless Cis The concentration of nuclide i in a particular effluent stream s, gLCi/ml F, The flow rate of a particular effluent stream s, gpm MEC, Maximum Effluent Concentration, ten times the limiting Effluent Concentration of a specific nuclide i from 10CFR20, Appendix B, Table 2, Column 2 (for noble gases, the concentration shall be limited to 2E-4 microcurie/ml), gCi/ml

, (Cis/MECi) The Maximum Effluent Concentration fraction of stream s prior to dilution by other streams E. ( F.) The total flow rate of all effluent streams s, gpm A value of less than one for the MEC fraction is required for compliance.

1.3 Liquid Effluent Dose Calculation Methodology The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure D 1.0-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the whole 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 whole body and to less than or equal to 10 mrem to any organ.

Doses due to Liquid Effluents are calculated monthly for the fish and drinking water ingestion pathways and the external sediment exposure pathways from all detected nuclides in liquid effluents released to the unrestricted areas using the following expression from NUREG 0133, Section 4.3.

De = YS (Alt YL (ATLCiLFL) I Where:

Dt = The cumulative-dose commitment to the total body or any organ, t from the liquid effluents for the total time period EL (ATL),Imrem ATL = The length of the L th time period over which CL and FL are averaged for all liquid releases, hours CiL = The average concentration of radionuclide, i, in undiluted liquid effluents during time period AT, from any liquid release, ptCi/ml-Unit 2 Revision 23 II 8 December 2002

At The site related ingestion dose commitment factor for the maximum individual to the total body or any or gan t for each identified principal gamma or beta emitter, mrem/hr per [,Ci/ml. Table D 2-2.

FL = The near field average dilution factor for Cd during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5.9. (5.9 is the site specific applicable factor for the mixing effect of the discharge structure.)

See the Nine Mile Point Unit 2 Environmental Report - Operating License Stage, Table 5.4-2 footnote 1.

These factors can be related to batch release parameters as follows:

FL = PEF / (TDF x 5.9) (Terms defined in Section 1.1.2.1 and above)

ATLFL = [PEF (gpm) x ATL (min) x 1.67E-2 (hr/min)] / [TDF (gpm) x 5.9]

= [TV x 2.83E-3 (hours)] / TDF For each batch, PEF (gpm) x ATL (min) = Tank Volume. For each batch, a dose calculation common constant (ATLFL) is calculated to be used with the concentration of each nuclide and dose factor, Ap, to calculate the dose to a receptor. Normally, the highest dose factor for any age group (adult, teen, child, infant) will be used for calculation, but specific age-group calculations to demonstrate compliance may be performed if required.

1.4 Liquid Effluent Sampling Representativeness There are four tanks in the radwaste system designed to be discharged to the discharge canal. These tanks are labeled 4A, 4B, 5A, and SB.

Liquid Radwaste Tank 5A and 5B at Nine Mile Point Unit 2 contain a sparger spray ring which assists the mixing of the tank contents while it is being recirculated prior to sampling. This sparger effectively mixes the tank four times faster than simple recirculation.

Liquid Radwaste Tank 4A and 4B contain a mixing ring but no sparger. No credit is taken for the mixing effects of the ring. Normal recirculation flow is 150 gpm for -

tank 5A and 5B, 110 gpm for tank 4A and 4B while each tank contains up to 25,000 gallons although the entire contents are not discharged. To assure that the tanks are adequately mixed prior to sampling, it is a plant requirement that the tank be recirculated for the time required to pass 2.5 times the volume of the tank:

Recirculation Time = 2.5T/RM Unit 2 Revision 23 II 9 December 2002

Where:

Recirculation Time = Is the minimum time to recirculate the Tank, min 2.5 = Is the plant requirement, unitless T = Is the tank volume, gal R = Is the recirculation flow rate, gpm.

M = Is the factor that takes into account the mixing of the sparger, unitless, four for tank 5A and B, one for tank 4A and B.

Additionally, the Alert Alarm setpoint of the Liquid Radwaste Effluent monitor is set at approximately 60% of the High alarm setpoint. This alarm will give indication of incomplete mixing with adequate margin before exceeding ten times the effluent concentration.

Service Water A and B and the Cooling Tower Blowdown are sampled from the radiation monitor on each respective stream. These monitors continuously withdraw a sample and pump it back to the effluent stream. The length of tubing between the continuously flowing sample and the sample spigot contains less than 200 ml which is adequately purged by requiring a purge of at least 1 liter when grabbing a sample.

1.5 Liquid Radwaste System Operability The Liquid Radwaste Treatment System shall be OPERABLE and used when projected doses due to liquid radwaste effluents would exceed 0.06 mrem to the whole body or

-0.2 mrem to any organ in a 31-day period. Cumulative doses will be determined at least once per 31 days (as indicated in Section 1.3) and doses will also be projected if the radwaste treatment systems are not being fully utilized.

The system collection tanks are processed as follows:

1) Low Conductivity (Waste Collector): Radwaste Filter and Radwaste Demineralizer or the Thermex System.

2) High Conductivity (Floor Drains): Regeneranf Evaporator or the Thermex System.

3) Regenerant Waste: If resin regeneration is used at NMP-2; the waste will be processed through the regenerant evaporator or Thermex System.

The dose projection indicated above will be performed in accordance with the methodology of Section 1.3.

Unit 2 Revision 23 11 10 December 2002

2.0 GASEOUS EFFLUENTS The gaseous effluent release points are the stack and the combined Radwaste/Reactor Building vent. The stack effluent point includes Turbine Building ventilation, main condenser offgas (after charcoal bed holdup), and Standby Gas Treatment System exhaust. NUREG 0133 and Regulatory Guide 1.109, Rev. 1 were followed in the development of this section.

2.1 Gaseous Effluent Monitor Alarm Setpoints 2.1.1 Basis The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure D 1.0-1) shall be limited to the following in accordance with Technical Specification 5.5.4.g:

a. For noble gases: Less than or equal to 500 mrem/yr to the whole 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 with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.

The radioactivity rate of noble gases measured downstream of the recombiner shall be limited to less than or equal to 350,000 microcuries/second during offgas system operation in accordance with Technical Specification 3.7.4.

2.1.2 Setpoint Determination Methodology Discussion Nine Mile Point Unit 1 and the James A FitzPatrick nuclear plants occupy the same site as Nine Mile Point Unit 2. Because of the independence of these plants' safety systems, control rooms and operating staffs it is assumed that simultaneous accidents are not likely to occur at the different units. However, there are two release points at Unit 2. It is assumed that if an accident were to occur at Unit 2 that both release points could be involved.

The alarm setpoint for Gaseous Effluent Noble Gas Monitors are based on a dose rate limit of 500 mRem/yr to the Whole Body. Since there are two release points at Unit 2, the dose rate limit of 500 mRem/yr is divided equally for each release point, but may be apportioned otherwise, if required. These monitors are sensitive to only noble gases. Because of this it is considered impractical to base their alarm setpoints on organ dose rates due to iodines or particulates. Additionally skin dose rate is never significantly greater than the whole body dose rate. Thus the factor R which is the basis for the alarm setpoint calculation is nominally taken as equal' to 250 mRem/yr.

If there are significant releases from any gaseous release point on the site ( > 25 mRem/yr) for an extended period of time then the setpoint will be recalculated with an appropriately smaller value for R.

The high alarm setpoint for the Offgas Noble Gas monitor is based on a limit of 350,000 uCi/sec. This is the release rate for which a FSAR accident analysis was Unit 2 Revision 23 II 11 December 2002

completed. At this rate the Offgas System charcoal beds will not contain enough activity so that their failure and subsequent release of activity will present a significant offsite dose assuming accident meteorology.

Initially, in accordance with Part I, Section D 3.3.2, the Germanium multichannel analysis systems of the stack and vent will be calibrated with gas standards (traceable to NIST) in accordance with DSR 3.3.2.9. Subsequent calibrations may be performed with gas standards, or with related solid sources. The quarterly Channel Functional Test will include operability of the 30cc chamber and the dilution stages to confirm monitor high range capability. (Appendix D, Gaseous Effluent Monitoring System).

2.1.2.1 Stack Noble Gas Detector Alarm Setpoint Equation:

The stack at Nine Mile Point Unit 2 receives the Offgas after charcoal bed delay, Turbine Building Ventilation and the Standby Gas Treatment system exhaust. The Standby Gas Treatment System Exhausts the primary containment during normal shutdowns and maintains a negative pressure on the Reactor Building to maintain secondary containment integrity. The Standby Gas Treatment will isolate on high radiation detected (by the SGTS monitor) during primary containment purges.

The stack noble gas detector is made of germanium. It is sensitive to only gamma radiation. However, because it is a computer based multichannel analysis system it is able to accurately quantify the activity released in terms of uCi of specific nuclides.

Only pure alpha and beta emitters are not detectable, of which there are no common noble gases. A distribution of Noble Gases corresponding to offgas is chosen for the nominal alarm setpoint calculation. Offgas is chosen because it represents the most significant contaminant of gaseous activity in the plant. The release rate Q, corresponds to offgas concentration expected with the plant design limit for fuel failure. The alarm setpoint may be recalculated if a significant release is encountered.

In that case the actual distribution of noble gases will be used in the calculation.

The following calculation will be used for the initial Alarm Setpoint.

O. 8R Yj tQ,)

Alarm Setpoint, dCi/sec < I i (QiVj) 0.8 = Safety Factor, unitless R = Allocation Factor. Normally, 250 mrem/yr; the value must be 500 mrem/yr or less depending upon the dose rate from other release points within the site such that the total dose rate corresponds to

< 500 mrem/yr Q = The release rate of nuclide i, PCi/sec V, = The constant for each identified noble gas nuclide accounting for the whole body dose from the elevated finite plume listed on Table D 3-2, mrem/yr per MtCi/sec Unit 2 Revision 23 II 12 December 2002

Ei (Qi) = The total release rate of noble gas nuclides in the stack effluent, Ci/sec Yi (Qiv 1 ) The total of the product of each isotope release rate times its respective whole body plume constant, mrem/yr, 4Ci/sec The alert alarm is normally set at less than 10% of the high alarm.

2.1.2.2 Vent Noble Gas Detector Alarm Setpoint Equation:

The vent contains the Reactor Building ventilation above and below the refuel floor and the Radwaste Building ventilation effluents. The Reactor Building Ventilation will isolate when radiation monitors detect high levels of radiation (these are separate monitors, not otherwise discussed in the ODCM).. Nominal flow rate for the vent is 2.37E5 CFM.

This detector is made of germanium. It is sensitive to only gamma radiation.

However, because it is a computer based multichannel analysis system it is able to accurately quantify the activity released in terms of PCi of specific nuclides. Only pure alpha and beta emitters are not detectable, of which there are no common noble gases. A distribution of Noble Gases corresponding to that expected with the design limit for fuel failure offgas is chosen for the nominal alarm setpoint calculation.

Offgas is chosen because it represents the most significant contaminant of gaseous activity in the plant. The alarm setpoint may be recalculated if a significant release is encountered. In that case the actual distribution of noble gases will be used in the calculation.

O. 8R Fi (QJ)

Alarm Setpoint, uCi/sec < (X/Q) v (Q Ki)

Where:

0.8 = Safety Factor, unitless R = Allocation Factor. Normally, 250 mrem/yr; the value must be 500 mrem/yr or less depending upon the dose rate from other release points within the site such that the total rate corresponds to < 500 mrem/yr Q The release rate of nuclide i, PCi/sec-(X/Q)V = The highest annual average atmospheric dispersion coefficient at the site boundary as listed in the Final Environmental Statement, NUREG 1085, Table D-2, 2.OE-6 sec/rn3 K; The constant for each identified noble gas nuclide accounting for the whole body dose from the semi-infinite cloud, listed on Table D 3-3, mrem/yr per ,Ci/m 3 Unit 2 Revision 23 II 13 December 2002

(Qi) = The total release rate of noble gas nuclides in the vent effluent, uCi/sec Yi (QiKj) = The total of the product of the each isotope release rate times its respective whole body immersion constant, mrem/yr per sec/rn2 The alert alarm is normally set at less than 10% of the high alarm.

2.1.2.3 Offgas Pretreatment Noble Gas Detector Alarm Setpoint Equation:

The Offgas system has a radiation detector downstream of the recombiners and before the charcoal decay beds. The offgas, after decay, is exhausted to the main stack. The system will automatically isolate if its pretreatment radiation monitor detects levels of radiation above the high alarm setpoint.

The Radiation Detector contains a plastic scintillator disc. It is a beta scintillation detector. Detector response Yi (C/CF.) has been evaluated from isotopic analysis of offgas analyzed on a multichannel analyzer, traceable to NIST. A distribution of offgas corresponding to that expected with the design limit for fuel failure was used to establish the initial setpoint. However, the alarm setpoint may be recalculated using an updated nuclide distribution based on actual plant process conditions. The monitor nominal response values will be confirmed during periodic calibration using a Transfer Standard source traceable to the primary calibration performed by the vendor.

Particulates and Iodines are not included in this calculation because this is a noble gas monitor.

To provide an alarm in the event of failure of the offgas system flow instrumentation, the low flow alarm setpoint will be set at or above 10 scfm, (well below normal system flow) and the high flow alarm setpoint will be set at or below 110 scfm, which is well above expected steady-state flow rates with a tight condenser.

To provide an alarm for changing conditions, the alert alarm will normally be set at 1.5 times nominal full power background to ensure that the Specific Activity Action required by ITS SR 3.7.4.1, are implemented in a timely fashion.

(3.50E+05) (2.12 E-03) YS,(C/CF,)

Alarm Setpoint, cpm < 0.8 F i (Ci) + Background Where:

Alarm Setpoint = The alarm setpoint for the offgas pretreatment Noble Gas Detector, cpm 0.8 = Safety Factor, unitless Unit 2 Revision 23 II 14 December 2002

350,000 = The Technical Specification Limit for Offgas Pretreatment, Ci/sec 2.12E-03 = Unit conversion Factor, 60 sec/min / 28317 cc/CF C, = The concentration of nuclide, i, in the Offgas, tCi/cc CF1 - The Detector response to nuclide i, Ci/cc/cpm; See Table D 3-1 for a list of nominal values F - The Offgas System Flow rate, CFM Background = The detector response to non-fission gases and general area dose rates, cpm Ei (c/CFi) = The summation of the nuclide concentration divided by the corresponding detector response, net cpm Hi (c1) = The summation of the concentration of nuclides in offgas, pCi/cc 2.2 Gaseous Effluents Dose Rate Calculation Dose rates will be calculated monthly at a minimum to demonstrate that the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the dose rate limits specified in 10CFR20. These limits are as follows:

The dose rate from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure D 1.0-1) shall be limited per Technical Specification 5.5.4.g to the following:

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

b. For iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ:

2.2.1 X/Q and WV - Dispersion Parameters for Dose Rate, Table D 3-23 The dispersion parameters for the whole body and skin dose rate calculation correspond to the highest annual average dispersion parameters at or beyond the unrestricted area boundary. This is at the east site boundary. These values were obtained from the Nine Mile Point Unit 2 Final Environmental Statement, NUREG 1085 Table D-2 for the vent and stack. These were calculated using the methodology of Regulatory Guide 1.111, Rev. 1. The stack was modeled as an elevated release point because its height is more than 2.5 times any adjacent building height. The vent was modeled as a ground level release because even though it is higher than any adjacent building it is not more than 2.5 times the height.

The NRC Final Environmental Statement values for the site boundary X/Q and D/Q terms were selected for use in calculating Effluent Monitor Alarm Points and compliance with Site Boundary Dose Rate specifications because they are conservative Unit 2 Revision 23 II 15 December 2002

when compared with the corresponding Nine Mile Point Environmental Report values.

In addition, the stack "intermittent release" X/Q was selected in lieu of the "continuous" value, since it is slightly larger, and also would allow not making a distinction between long term and short term releases.

The dispersion parameters for the organ dose calculations were obtained from the Environmental Report, Figures 7B-4 (stack) and 7B-8 (vent) by locating values corresponding to currently existing (1985) pathways. It should be noted that the most conservative pathways do not all exist at the same location. It is conservative to assume that a single individual would actually be at each of the receptor locations.

2.2.2 Whole Body Dose Rate Due to Noble Gases The ground level gamma radiation dose from a noble gas stack release (elevated),

referred to as plume shine, is calculated using the dose factors from Appendix B of this document. The ground level gamma radiation dose from a noble gas vent release accounts for the exposure from immersion in the semi-infinite cloud. The dispersion of the cloud from the point of release to the receptor at the east site boundary is factored into the plume shine dose factors for stack releases and through the use of X/Q in the equation for the immersion ground level dose rates for vent releases. The release rate is averaged over the period of concern. The factors are discussed in Appendix B.

Whole body dose rate (DR)y due to noble gases:

(DR)y 3.17E-08 aj (ViQl 5 + K; (X/Q)vQiv]

Where:

DRY Whole body dose rate (mrem/sec)

V, = The constant accounting for the gamma whole body dose rate from the finite plume from the elevated stack releases for each identified noble gas nuclide, i. Listed on Table D 3-2, mrem/yr per PCi/sec K, = The constant accounting for the gamma whole body dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table D 3-3, mrem/yr per uCi/m3 (From Reg.

Guide 1.109)

X/QV = The relative plume concentration at or beyond the X/Q5 land sector site boundary. Average meteorological data is used.

Elevated X/Q values are used for the stack releases (s =stack);

ground X/Q values are used for the vent releases (v=vent). Listed on Table D 3-23 Qs)Q1V = The release rate of each noble gas nuclide i, from the stack (s) or vent (v). Averaged over the time period of concern. (StCi/sec)

Unit 2 Revision 23 11 16 December 2002

3.17E-08 = Conversion Factor; the inverse of the number of seconds in one year. (yr/sec) 2.2.3 Skin Dose Rate Due to Noble Gases There are two types of radiation from noble gas releases that contribute to the skin dose rate: beta and gamma.

For stack releases this calculation takes into account the dose from beta radiation in a semi infinite cloud by using an immersion dose factor. Additionally, the dispersion of the released activity from the stack to the receptor is taken into account by use of the factor (X/Q). The gamma radiation dose from the elevated stack release is taken into account by the dose factors in Appendix B.

For vent releases the calculations also take into account the dose from the beta (p) and gamma (y) radiation of the semi infinite cloud by using an immersion dose factor.

Dispersion is taken into account by use of the factor (X/Q).

The release rate is averaged over the period of concern.

Skin dose rate (DR)D+fldue to noble gases:

(DR) y+ = 3.17E-8 hE [ (L; (X/Q) 5 +1. 11BJ Q,,+ (L1 +1. 11M) (X/Q) Q,,]

Where:

(DR) y+p Skin dose rate (mremlsec)

L= The constant to account for the gamma and beta skin dose rates for each noble gas nuclide, i, from immersion in the semi-infinite cloud, mrem/yr per tCi/m3 , listed on Table D 3-3 (from R. G. 1.109)

M, = The constant to account for the air gamma dose rate for each noble gas nuclide, i, from immersion in the semi-infinite cloud, mrad/yr per gCi/m3 , listed on Table D 3-3 (from R.G. 1.109) 1.11 = Unit conversion constant, mrem/mrad

.7 = Structural shielding factor, unitless B1 = The constant accounting for the air gamma dose rate from exposure to the overhead plume of elevated releases of each identified noble gas nuclide, i. Listed on Table D 3-2, mrad/yr per gCi/sec.

Unit 2

- Revision 23 II 17 December 2002

(X/Q), = The relative plume concentration at or beyond the land (X/Q), sector site boundary. Average meteorological data is used. Elevated X/Q values are used for the stack releases (s=stack); ground X/Q values are used for the vent releases (v=vent).

3.17E-8 = Conversion Factor; the inverse of the number of seconds in a year; (yr/sec)

QIVQI = The release rate of each noble gas nuclide i, from the stack(s) or vent (v) averaged over the time period of concern, gCi/sec.

2.2.4 Organ Dose Rate Due to I-131, 1-133, Tritium, and Particulates with Half-lives greater than 8 days.

-The organ dose rate is calculated using the dose factors (R.) from Appendix C. The factor R. takes into account the dose rate received from the ground plane, inhalation and ingestion pathways. W, and W, take into account the atmospheric dispersion from the release point to the location of the most conservative receptor for each of the respective pathways. The release rate is averaged over the period of concern.

Organ dose rates (DR)ac due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days:

(DR) at = 3. 17E-8 j [YiRliat (WsQi. + WvQi,] I Where:

(DR)at = Organ dose rate (mrem/sec)

Rijac The factor that takes into account the dose from nuclide i through pathway j to an age group a, and individual organ t. Units for inhalation pathway, mrem/yr per pCi/m3 . Units for ground and ingestion pathways, m2-mrem/yr per uCi/sec. See Tables D 3-4 through D 3-22).

WS, W, = Dispersion parameter either X/Q (sec/in) or D/Q (1/m2 )

depending on pathway and receptor location. Average meteorological data is used (Table D 3-23). Elevated W, values are used for stack releases (s=stack); ground W, values are used for vent releases (v=vent).

Q., Qv = The release rates for nuclide i, from the stack (s) and vent (v) respectively, gCi/sec.

When the release rate exceeds 0.75 uCi/sec from the stack or vent, the dose rate assessment shall, also, include JAF and NMP1 dose contributions. The use of the 0.75 4Ci/sec release rate threshold is conservative because it is based on the dose conversion Unit 2 Revision 23 II 18 December 2002

factor (R.) for the Sr-90 child bone which is significantly higher than the dose factors for the other isotopes present in the stack or vent release.

2.3 Gaseous Effluent Dose Calculation Methodology Doses will be calculated monthly at a minimum to demonstrate that doses resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50. These limits are as follows:

The air dose from noble gases released in gaseous effluents, from each unit, to areas at or beyond the SITE BOUNDARY (see Figure D 1.0-1) 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

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.

The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at or beyond the SITE BOUNDARY (see Figure D 1.0-1) 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.

The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and appropriate portions of this system shall be used to reduce releases of radioactivity when the projected doses in 31 days from iodine and particulate releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Figure D 1.0-1) would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

2.3.1 WV and W. - Dispersion Parameters for Dose, Table D 3-23 The dispersion parameters for dose calculations were obtained chiefly from the Nine Mile Point Unit 2 Environmental Report Appendix 7B. These were calculated using the methodology of Regulatory Guide 1.111 and NUREG 0324. The stack was modeled as an elevated release point because height is more than 2.5 times the height of any adjacent building. The vent was modeled as a combined elevated/ground level release because the vent's height is not more than 2.5 times the height of any adjacent building.

Average meteorology over the appropriate time period was used. Dispersion parameters not available from the ER were obtained from C.T. Main Data report dated November, 1985, or the FES.

Unit 2 Revision 23 II 19 December 2002

2.3.2 Gamma Air Dose Due to Noble Gases Gamma air dose from the stack or vent noble gas releases is calculated monthly. The gamma air dose equation is similar to the gamma dose rate equation except the receptor is air instead of the whole body or skin of whole body. Therefore, the stack noble gas releases use the finite plume air dose factors, and the vent noble gas releases use semi-infinite cloud immersion dose factors. The factor X/Q takes into account the dispersion of vent releases to the most conservative location. The release activity is totaled over the period of concern. The finite plume factor is discussed in Appendix B.

Gamma air dose due to noble gases:

Dy = 3.17E-8 E (Mi(X/Q)v Qiv + Bi Qi 5s X t DY The gamma air dose for the period of concern, mrad t = The duration of the dose period of concern, sec Where all other parameters have been previously defined.

2.3.3 Beta Air Dose Due to Noble Gases The beta air dose from the stack or vent noble gas releases is calculated using the semi-infinite cloud immersion dose factor in beta radiation. The factor X/Q takes into account the dispersion of releases to the most conservative location.

Beta air dose due to noble gases:

DP 3.17E-8 YiNif(X/Q)v Q1v + (X/Q)s Qsl1 X t D = Beta air dose (mrad) for the period of concern N. = The constant accounting for the beta air dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed on Table D 3-3, mrad/yr per uCi/m3 . (From Reg. Guide 1.109).

t = The duration of the dose period of concern, sec Where all other parameters have been previously defined.

2.3.4 Organ Dose Due to I-131, I-133, Tritium and Particulates with half-lives greater than 8 days.

The organ dose is based on the same equation as the dose rate equation except the dose is compared to the 10CFR50 dose limits. The factor R, takes into account the dose received from the ground plane, inhalation, food (cow milk, cow meat and vegetation) pathways. W, and W, take into account the atmospheric dispersion from the release point to the location of the most conservative receptor for each of the respective pathways. The release is totaled over the period of concern. The R. factors are discussed in Appendix C.

Unit 2 Revision 23 II 20 December 2002

Organ dose Dat due to iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days.

Dat = 3. 17E-8 Ot [ £1 Rijat [Ws QiS + WV Q1YvI X t Where:

Dat = Dose to the critical organ t, for age group a, mrem t = The duration of the dose period of concern, sec Where all other parameters have been previously defined in Section 2.2.4.

2.4 I-133 and I-135 Estimation Stack and vent effluent iodine cartridges are analyzed to a sensitivity of at least lE-12 uCi/cc. If detected in excess of the LLD, the I-131 and 1-133 analysis results will be reported directly from each cartridge analyzed. Periodically, (usually quarterly but on a monthly frequency if effluent iodines are routinely detected) a short-duration (12 to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) effluent sample is collected and analyzed to establish an I-135/1-131 ratio and an I-133/I-131 ratio, if each activity exceeds LLD. The short-duration ratio is used to confirm the routinely measured 1-133 values. The short-duration I-135/I-131 ratio (if determined) is used with the 1-131 release to estimate the I-135 release. The short-duration I-133/1-131 ratio may be used with the 1-131 release to estimate the I-133 release if the directly measured I-133 release appears non-conservative.

2.5 Isokinetic Sampling Sampling systems for the stack and vent effluent releases are designed to maintain isokinetic sample flow at normal ventilation flow rates. During periods of reduced ventilation flow, sample flow may be maintained at a minimum flow rate (above the calculated isokinetic rate) in order to minimize sample line losses due to particulate deposition at low velocity.

2.6 Use of Concurrent Meteorological Data vs. Historical Data It is the intent to use dispersion parameters based on historical meteorological data to set alarm points and to determine or predict dose and dose rates in the environment due to gaseous effluents. If effluent levels approach limiting values, meteorological conditions concurrent with the time of release may be used to determine gaseous pathway doses.

2.7 Gaseous Radwaste Treatment System Operation Part I, Section D 3.2.4 requires the GASEOUS RADWASTE TREATMENT SYSTEM to be in operation whenever the main condenser air ejector system is in operation. The system may be operated for short periods with the charcoal beds bypassed to facilitate Unit 2 Revision 23 II 21 December 2002

transients. The components of the system which normally should operate to treat offgas Filter, are the Preheater, Recombiner, Condenser, Dryer, Charcoal Adsorbers, HEPA and Vacuum Pump. (See Appendix D, Offgas System).

2.8 Ventilation Exhaust Treatment System Operation Part I, Section D 3.2.5 requires the VENTILATION EXHAUST TREATMENT SYSTEM to be OPERABLE when projected doses in 31 days due to iodine and particulate releases would exceed 0.3 mrem to any organ of a member of the public.

The appropriate components, which affect iodine or particulate release, to be OPERABLE are:

1) HEPA Filter - Radwaste Decon Area

2) HEPA Filter - Radwaste Equipment Area

3) HEPA Filter - Radwaste General Area projections Whenever one of these filters is not OPERABLE, iodine and particulate dose as will be made for 31-day intervals starting with filter inoperability, and continuing long as the filter remains inoperable, in accordance with DSR 3.2.5.1. Predicted release rates will be used, along with the methodology of Section 2.3.4. (See Appendix D, Gaseous Radiation Monitoring.)

Unit 2 Revision 23 II 22 December 2002

3.0 URANIUM FUEL CYCLE The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) as follows:

"Uranium fuel cycle means the operations of milling of uranium ore chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle. "

Sections D 3.1.2, D 3.2.2, and D 3.2.3 of Part I requires that when the calculated doses associated with the effluent releases exceed twice the applicable quarter or annual limits, the licensee shall evaluate the calendar year doses and, if required, submit a Special Report to the NRC and limit subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem). This report is to demonstrate that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190. If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit such releases will be requested and if possible, action will be taken to reduce subsequent releases.

The report to the NRC shall contain:

1) Identification of all uranium fuel cycle facilities or operations within 5 miles of the nuclear power reactor units at the site, that contribute to the annual dose of the maximum exposed member of the public.

2) Identification of the maximum exposed member of the public and a determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation.

The total body and organ doses resulting from radioactive material in liquid effluents from Nine Mile Point Unit 2 will be summed with the doses resulting from the releases

-of noble gases, radioiodines, and particulates. The direct dose components will also be determined by either calculation or actual measurement. Actual measurements will utilize environmental TLD dosimetry. Calculated measurements will utilize engineering calculations to determine a projected direct dose component. In the event calculations are used, the methodology will be detailed as required by Technical Specification 5.6.3.

The doses from Nine Mile Point Unit 2 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site.

Unit 2 Revision 23 II 23 December 2002

For the purpose of calculating doses, the results of the Environmental Monitoring Program may be included to provide more refined estimates of doses to a real maximum exposed individual. Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual environmental sample results.

Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered. Since the doses from other aquatic pathways are insignificant, fish consumption and shoreline sediment are the only two pathways that will be considered. The dose associated with fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data.

Because of the nature of the receptor location and the extensive fishing in the area, the critical individual may be a teenager or an adult. The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area. This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.

Equations used to evaluate fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology. Because of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of the equations are deleted. This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view. Table D 3-24 presents the parameters used for calculating doses from liquid effluents.

The dose from fish sample media is calculated as:

Rap: = Hi [Cif (U) (Daipi) f] (1E+3)

Where:

Rpj = The total annual dose to organ j, of an individual of age group a, from nuclide i, via fish pathway p, in mrem per year; ex. if calculating to the adult whole body, then Rpj = R,Vb and Daipi = D'WB Cf= The concentration of radionuclide i in fish samples in pCi/gram U The consumption rate of fish 1E+3 = Grams per kilogram (Daipj) = The ingestion dose factor for age group a, nuclide i, fish pathway p, and organj, (Reg. Guide 1.109, Table E-11) (mrem/pCi). ex. when calculating to the adult whole body Da,,P = DwB f = The fractional portion of the year over which the dose is applicable Unit 2 Revision 23 II 24 December 2002

The dose from shoreline sediment sample media is calculated as:

Rapj = Ey (C.s (U)(4E+4) (0.3) (Daipj) fi Where:

= The total annual dose to organ j, of an individual of age group a, from nuclide i, via the sediment pathway p, in mrem per year; ex. if calculating to the adult whole body, then R.P, = Rw and Daipi = DwB Cls = The concentration of radionuclide i in shoreline sediment in pCi/gram U = The usage factor, (hr/yr) (Reg. Guide 1.109) 4E- -4 = The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm) times the number of grams per kilogram 0.3 - The shore width factor for a lake Daipj = The dose factor for age group a, nuclide i, sediment pathway s, and organ j. (Reg. Guide 1.109, Table E-6) (mrem/hr per pCi/m 2 ); ex.

when calculating to the adult whole body Daipj = DwB f = The fractional portion of the year over which the dose is applicable NOTE: Because of the nature of the receptor location and the extensive fishing in the area, the critical individual may be a teenager or an adult.

Unit 2 Revision 23 II 25 December 2002

3.2 Evaluation of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 2 of the calculational methodologies section will be considered and include ground deposition, inhalation, cows milk, goats milk, meat, and food products (vegetation). However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data, location of critical receptors, etc. Data from the most recent census and sample location surveys should be utilized. Doses may also be calculated from actual environmental sample media, as available. Environmental sample media data such as TLD, air sample, milk sample and vegetable (food crop) sample data may be utilized in lieu of effluent calculational data.

Doses to members of the public from the pathways considered in section 2 as a result of gaseous effluents will be calculated using the methodology of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable. Doses calculated from environmental sample media will be based on methodologies found in Regulatory Guide 1.109.

3.3 Evaluation of Doses From Direct Radiation The dose contribution as a result of direct radiation shall be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded. Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating environmental TLD results at critical receptor locations, site boundary or other special interest locations. For the evaluation of direct radiation doses utilizing environmental TLDs, the critical receptor in question, such as the critical residence, etc., will be compared to the control locations.

The comparison involves the difference in environmental TLD results between the receptor location and the average control location result.

3.4 Doses to Members of the Public Within the Site Boundary The Radioactive Effluent Release Report shall include 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 as defined by Figure D 1.0-1. A member of the public, would be represented by an individual who visits the sites' Energy Center for the purpose of observing the educational displays or for picnicking and associated activities.

Fishing is a major recreational activity in the area and on the Site as a result of the salmon and trout populations in Lake Ontario. Fishermen have been observed fishing at the shoreline near the Energy Center from April through December in all weather conditions. Thus, fishing is the major activity performed by members of the public within the site boundary. Based on the nature of the fishermen and undocumented observations, it is conservatively assumed that the maximum exposed individual spends an average of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week fishing from the shoreline at a location between the Unit 2 Revision 23 II 26 - December 2002

Energy Center and the Unit 1 facility. This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.

The pathways considered for the evaluation include the inhalation pathway with the resultant lung dose, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated total body dose. The direct radiation dose pathway, in actuality, includes several pathways. These include:

the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose, possible direct radiation dose from the facility and a ground plane dose (deposition). Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.

Other pathways, such as the ingestion pathway, are not applicable. In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here. These include swimming, boating and wading which are prohibited at the facility.

The inhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period.

The radionuclide concentrations are then multiplied by the appropriate X/Q value, inhalation dose factor, air intake rate, and the fractional portion of the year in question.

Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109. Table D 3-24 presents the reference for the parameters used in the following equation.

NOTE: The following equation is adapted from equations C-3 and C-4 of Regulatory Guide 1.109. Since many of the factors are in units of pCi/tnS, m3/sec., etc., and since the radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation presented here is not identical to the Regulatory Guide equations.

Dja En [ (Ci) F (X/Q) (DFA) ija (BR)atl Where:

Dia = The maximum dose from all nuclides to the organ j and age group (a) in mrem/yr; ex. if calculating to the adult lung, then DJa = DL and DFAij = DFAL C, = The average concentration in the stack or vent release of nuclide i for the period in pCi/in.

F = Unit 2 average stack or vent flowrate in m1/sec.

Unit 2 Revision 23 II 27 December 2002

XIQ = The plume dispersion parameter for a location approximately 0.50 miles west of NMP-2 (The plume dispersion parameters are 9.6E-07 (stack) and 2.8E-06 (vent) and were obtained from the C.T. Main five year average annual X/Q tables.

- The vent X/Q (ground level) is ten times the listed 0.50 mile X/Q because the vent is approximately 0.3 miles from the receptor location. The stack (elevated) X/Q is conservative when based on 0.50 miles because of the close proximity of the stack and the receptor location.

(DFA)&Ja = the dose factor for nuclide i, organ j, and age group a in mrem per pCi (Reg. Guide 1.109, Table E-7); ex. if calculating to the adult lung the DFAija = DFAIL (BR)a = annual air intake for individuals in age group a in M3 per year (obtained from Table E-5 of Regulatory Guide 1.109).

t = fractional portion of the year for which radionuclide i was detected and for which a dose is to be calculated (in years).

The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where fishing occurs. The dose will then be calculated using the sample results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 3.1. The resultant dose may be adjusted for a background dose by subtracting the applicable off-site control soil or shoreline sediment sample radionuclide activities. In the event it is noted that fishing is not performed from the shoreline but is instead performed in the water (i.e., the use of waders), then the ground dose pathway (deposition) 'will not be evaluated.

The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, submersion in the plume, possible radiation from the facility and ground plane dose (deposition). This general pathway will be evaluated by average environmental TLD readings. At least two environmental TLDs will be used at one location in the approximate area where fishing occurs. The TLDs will be placed in the field on approximately the beginning of each calendar quarter and removed approximately at the end of each calendar quarter (quarter 2, 3, and 4).

The average TLD readings will be adjusted by the average control TLD readings. This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLD value. The applicable quarterly control TLD values will be used after adjusting for the appropriate time period (as applicable). In the event of loss or theft of the TLDs, results from a TLD or TLDs in a nearby area may be utilized.

Unit 2 Revision 23 II 28 December 2002

4.0 ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampling Stations The current sampling locations are specified in Table D 5-1 and Figures D 5.1-1 and D 5.1-2. The meteorological tower location is shown on Figure D 5.1-1 and is located where TLD location #17 is identified. The Environmental Monitoring Program is a joint effort between the owners and operators of the Nine Mile Point Units 1 and 2 and the James A. FitzPatrick Nuclear Power Plants. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units. The environmental sampling location coordinates shown on Table D 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters for the three units have been calculated for a 5 year period, 1978 through 1982. Average dispersion or deposition parameters for the site are calculated using the 1978 through 1982 data and are used to compare the results of the annual land use census. If it is determined that sample locations required by Control D 3.5.1 are unavailable or new locations are identified that yield a significantly higher (i.e., 50%) calculated D/Q value, actions will be taken as required by Controls D 3.5.1 and D 3.5.2 and the Radiological Environmental Monitoring Program updated accordingly.

4.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Crosscheck Program.

Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point Environmental Monitoring Program and for which cross check samples are available. An attempt will be made to obtain a QC sample to program sample ratio of 5 % or better. The Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.

Specific sample media for which EPA Cross Check Program samples are available include the following:

• gross beta in air particulate filters

• gamma emitters in air particulate filters

• gamma emitters in milk

• gamma emitters in water tritium in water 1-131 in water Unit 2 Revision 23 II 29 December 2002

4.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by the Technical Specifications are based on ANSI Standard N545, section 4.3. TLDs are defined as phosphors packaged for field use. In regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate the above capabilities per type of TLD.

Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs. Required detection capabilities are as follows.

4.3.1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The responses obtained shall have a relative standard deviation of less than 7.5 %. A total of at least 5 TLDs shall be evaluated.

4.3.2 Reproducibility shall be determined by giving TLDs repeated exposures equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The average of the relative standard deviations of the responses shall be less than 3.0%. A total of at least 4 TLDs shall be evaluated.

4.3.3 Dependence of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a field cycle and a period equal to half the same field cycle in an area where the exposure rate is known to be constant. This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures. For these tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85. At least 6 TLDs shall be evaluated.

4.3.4 Energy dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 MeV. The response shall not differ from that obtained with the calibration source by more than 25 % for photons with energies greater than 80. keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV. A total of at least 8 TLDs shall be evaluated.

4.3.5 The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations. To accomplish this, the TLD shall be rotated through at least two perpendicular planes. The response averaged over all directions shall not differ from the response obtained in the standard calibration position by more than 10%. A total of at least 4 TLDs shall be evaluated.

4.3.6 Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6. The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10%. A total of at least 4 TLDs shall be evaluated for each of the four conditions.

Unit 2 Revision 23 II 30 December 2002

4.3.7 Moisture dependence shall be determined by placing TLDs (that is, the phosphors packaged for field use) for a period equal to the field cycle in an area where the exposure rate is known to be constant. The TLDs shall be exposed under two conditions: (1) packaged iri a thin, sealed plastic bag, and (2) packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle.

The TLD or phosphor, as appropriate, shall be dried before readout. The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by more than 10%. A total of at least 4 TLDs shall be evaluated for each condition.

4.3.8 Self irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known. If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545, section 4.3.3).

The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. A total of at least 3 TLDs shall be evaluated.

Unit 2 Revision 23 II 31 - December 2002

TABLE D 2-1 LIQUID EFFLUENT DETECTORS RESPONSES*

NUCLIDE (CPM/,,Ci/Ml x 101)

Sr 89 0.78E-04 Sr91 1.22 Sr92 0.817 Y91 2.47 Y92 0.205 Zr 95 0.835 Nb 95 0.85 Mo 99 -0.232 Tc 99m 0.232 Te 132 1.12 Ba 140 0.499 Ce 144 0.103 Br 84 1.12 I 131 1.01 1 132 2.63 1 133 0.967 I 134 2.32 1 135 1.17 Cs 134 1.97 Cs 136 2.89 Cs 137 0.732 Cs 138 1.45 Mn 54 0.842 Mn 56 1.2 Fe 59 0.863 Co 58 1.14 Co 60 1.65

• Values from SWEC purchase specification NMP2-P28 IF. -

Unit 2 Revision 23 II 32 December 2002

TABLE D 2-2 A. VALUES - LIQUID' ADULT mrem - ml hr - uCi NUCLIDE T BODY GI-TRACT BONE LIVER KIDNEY THYROID -

LUNG H 3 3.67E-1 3.67E-1 3.67E-1 3.67E-1 3.67E-1 3.67E-1 Cr51 1.26 3.13E2 1.18E-2 1.18E-2 2.86E-1 7.56E-1 1.66 Cu 64 1.28 2.33E2 2.73 6.89 Mn 54 8.38E2 1.34E4 3.98 4.38E3 1.3 1E3 3.98 3.98 Fe 55 1.07E2 2.62E2 6.62E2 4.57E2 2.55E2 FeS9 9.28E2 8.06E3 1.03E3 2.42E3 7.53E-1 7.53E-1 6.76E2 Co 57 5.43E1 5.36E2 2.11E1 Co 58 2.01E2 1.81E3 1.07 9.04E1 1.07 1.07 1.07 Co 60 6.36E2 4.93E3 6.47E1 3.24E2 6.47E1 6.47E1 6.47E1 Zn 65 3.32E4 4.63E4 2.3 1E4 7.35E4 4.92E4 2.21 2.21 Sr89 6.38E2 3.57E3 2.22E4 6.18E-5 6.18E-5 6.18E-5 6.18E-5 Sr 90 1.36E5 1.60E4 5.55E5 Sr92 1.44E-2 6.61 3.34E-1 Zr 95 7.59E-1 2.83E2 9.77E-1 7.88E-1 8.39E-1 6.99E-1 6.99E-1 Mn56 3.07E-2 5.52 1.73E-1 2.20E-1 Mo 99 1.60E1 1.95E2 1.97E-3 8.42E1 1.91E2 1.97E-3 1.97E-3 Na 24 1.34E2 1.34E2 1.34E2 1.34E2 1.34E2 1.34E2 1.34E2 I131 1.16E2 5.36E1 1.42E2 2.03E2 3.48E2 6.65E4 2.77E-2 1132 4.34E-3 2.33E-3 4.64E-3 1.24E-2 1.98E-2 4.34E-1 I133 1.22E1 3.59E1 2.30E1 3.99E1 6.97E1 5.87E3 I135 1.32EO 3.79EO 1.28EO 3.36EO 5.39EO 2.22E2 Ni 65 1.14E-2 6.35E-1 1.93E-1 2.50E-2 Cs 134 5.79E5 1.24E4 2.98E5 7.08E5 2.29E5 2.04E1 7.61E4 Cs 136 8.42E4 1.33E4 2.96E4 1. 17E5 6.51E4 3.28E-1 8.92E3 Cs 137 3.42E5 1.01E4 3.82E5 5.22E5 1.77E5 3. 10E1 5.89E4 Ba140 1.37E1 4.30E2 2.09E2 3.04E-1 1.3lE-1 4.17E-2 1.92E-1 Ce 141 3.79E-2 8.81E1 6.93E-2 5.83E-2 4.60E-2 3.53E-2 3.53E-2 Nb 95m 1.5lEl 1.44E6 3.53E1 2.74E1 2.70E1 Nb 95 1.31E2 1.48E6 4.38E2 2.44E2 2.4 1E2 3.56E-1 3.56E-1 La 140 1.62E-2 3.72E3 1.03E-1 5.36E-2 2.83E-3 2.83E-3 2.83E-3 Ce 144 3.03E-1 6.15E2 2.02 9.66E-1 6.57E-1 2.06E-1 2.06E-1 Te 99m 2.05E-2 9.54E-O1 5.71E-4 1.61E-3 2.45E-2 7.90E-4 Np 239 1.8E-3 4.47E2 2.28E-2 2.78E-3 7.40E-3 5.95E-4 5.95E-4 Te 132 1.18E3 5.97E4 1.95E3 1.26E3 1.22E4 1.39E3 2.66E-3 Zr 97 5.08E-4 3.39E2 5.44E-3 1.1OE-3 1.66E-3 7.11E-6 7.11E-6 W 187 4.3lEl 4.04E4 1.48E2 1.23E2 4.43E-5 4.43E-5 4.43E-5 Ag lOrm 1.09E1 3.94E2 1.14E1 1.13E1 1.22E1 1.04E1 1.04E1 Sb 124 4.72E1 3.36E2 1.07E3 4.33E1 4.3lEl 4.31E1 5.12E1 Zn 69m 5.40E1 3.60E4 2.46E2 5.90E2 3.57E2 6.90E-2 6.90E-2 Au 199 3.95 7.33E2 1.26E-1 4.67 1.79E1 1.26E-1 1.26E-1 As 76 5.94 1.24E4 1.60E-1 6.19 1.16E1 1.60E-1 1.60E-1 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 2 Revision 23 II 33 December 2002

TABLE D 2-3 A,.VALUES - LIQUmD' TEEN mrem - ml hr - uCi LUNG NUCLIDE T BODY GI-TRACT BONE LIVER KIDNEY THYROID .

2.73E-1 H 3 2.73E-1 2.73E-1 2.73E-1 2.73E-1 2.73E-1 1.35 2.16E2 6.56E-2 6.56E-2 3.47E-1 7.79E-1 1.90 Cr51 Cu 64 1.35 2.23E2 2.87 7.27 8.75E2 8.84E3 2.22E1 4.32E3 1.31E3 2.22E1 2.22E1 Mn 54 1.15E2 2.13E2 6.93E2 4.91E2 3.1 1E2 Fe55 9.59E2 5.85E3 1.06E3 2.48E3 4.20 4.20 7.84E2 Fe59 Co 57 1.44E2 4.08E2 2.19E1 2.10E2 1.23E3 5.98 9.47E1 5.98 5.98 5.98 Co 58 9.44E2 3.73E3 3.61E2 6.20E2 3.61E2 3.61E2 3.61E2 Co 60 3.40E4 3.08E4 2. 10E4 7.28E4 4.66E4 1.24E1 1.24E1 Zn 65 6.92E2 2.88E3 2.42E4 3.45E-4 3.45E-4 3.45E-4 3.45E-4 Sr 89 Sr 90 1. 14E5 1.30E4 4.62E5 Sr 92 1.54E-2 9.19E1 3.61E-1 3.96 2. 10E2 4.19 3.99 4.03 3.90 3.90 Zr 95 Mn56 3.22E-2 1. 19E1 1.81E-1 2.29E-1 1.71E1 1.60E2 1.lOE-2 8.95E1 2.05E2 1.lOE-2 1. 1OE-2 Mo99 1.38E2 1.38E2 1.38E2 1.38E2 1.38E2 1.38E2 1.38E2 Na 24

1. 14E2 4.21E1 1.52E2 2.12E2 3.66E2 6.19E4 1.55E-1 1131 1132 4.56E-3 5.54E-3 4.86E-3 1.27E-2 2.00E-2 4.29E-1 1.28E1 3.17E1 2.47E1 '4.19E1 7.35E1 5.85E3 1.02E-4 I133 I135 1.76EO 3.84EO 1.34EO 3.46EO 5.47EO 2.23E2 Ni 65 1.21E-2 1.44 2.08E-1 2.66E-2 9.05E3 3.05E5 7.18E5 2.28E5 1.14E2 8.72E4 Cs 134 3.33E5 9.44E3 2.98E4 1. 17E5 6.38E4 1.83 1.01E4 Cs 136 7.87E4 1.9OE5 7.91E3 4.09E5 5.44E5 1.85E5 1.73E2 7.21E4 Cs 137 1.44E1 3.40E2 2.21E2 5.03E-1 3.25E-1 2.33E-1 4.15E-1 Ba 140 2.OOE-1 6.85E1 2.33E-1 2.21E-1 2.08E-1 1.97E-1 1.97E-1 Ce 141 Nb 95m 1.69E1 1. 14E6 3.87E1 2.99E1 2.96E1 1.17E2 1.05E6 4.43E2 2.47E2 2.39E2 1.99 1.99 Nb 95 2.97E-2 3.01E3 1.22E-1 6.82E-2 1.58E-2 1.58E-2 1.58E-2 La 140 1.25 4.83E2 3.07 1.94 1.62 1.15 1.15 Ce 144 2.11E-2 1.07 5.84E-4 1.63E-3 2.43E-2 9.04E-4 Tc 99m 4.63E-3 3.78E2 2.82E-2 5.67E-3 1.07E-2 3.32E-3 3.32E-3 Np 239 4.13E4 2.06E3 1.30E3 1.25E4 1.37E3 1.48E-2 Te 132 1.23E3 3.11E2 5.84E-3 1. 19E-3 1.78E-3 3.97E-5 3.97E-5 Zr 97 5.68E-4 3.52E4 1.59E2 1.30E2 2.47E-4 2.47E-4 2.47E-4 W 187 4.55E1 5.85E1 3.17E2 5.89E1 5.88E1 5.97E1 5.79E1 5.79E1 Ag lOnm 4.53E2 2.51E2 2.41E2 2.41E2 2.41E2 2.50E2 Sb 124 2.45E2 5.76E1 3.43E4 2.65E2 6.24E2 3.79E2 3.85E-1 3.85E-1 Zn 69m 5.78E2 7.04E-1 5.60 2.01E1 7.04E-1 7.04E-1 Au 199 4.85 1.06E4 8.92E-1 7.40 1.33E1 8.92E-1 8.92E-1 As 76 7.18 Regulatory position C, Section 1.

'Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory G~uide 1.109,

- Unit 2 Revision 23

- II 34 December 2002

TABLE D 2-4 A,,, VALUES - LIQUID' CHILD mrem - ml hr - uCi NUCLIDE T BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H 3 3.34E-1 3.34E-1 3.34E-1 3.34E-1 3.34E-1 3.34E-1 Cr51 1.39 7.29E1 1.37E-2 1.37E-2 2.22E-l 7.76E-1 1.41 Cu 64 1.60 1.25E2 2.65 6.41 Mn 54 9.02E2 2.83E3 4.65 3.37E3 9.49E2 4.65 4.65 Fe55 1.50E2 8.99E1 9.15E2 4.85E2 2.74E2 1.04E3 2.18E3 1.29E3 2.09E3 8.78E-1 -8.78E-1 6.08E2 Fe59 Co 57 6.24E1 1.62E2 2.00E1 Co58 2.21E2 4.20E2 1.25 7.30E1 1.25 1.25 1.25 Co 60 7.03E2 1.25E3 7.55E1 2.88E2 7.55E1 7.55E1 7.55E1 Zn 65 3.56E4 1.01E4 2.15E4 5.73E4 3.61E4 2.58 2.58 Sr 89 9.13E2 1.24E3 3.20E4 Sr90 1.06E5 5.62E3 4.17E5 Sr 92 1.85E-2 8.73 4.61E-1 Zr 95 8.95E-1 9.36E1 1.22 9.04E-1 9.43E-1 8.15E-1 8.15E-1 Mn56 3.73E-2 2.39E1 1.65E-1 2.OOE-1 Mo 99 2.22E1 7.42E1 2.30E-3 8.98E1 1.92E2 2.30E-3 2.30E-3 Na 24 1.51E2 1.51E2 1.51E2 1,51E2 1.51E2 1.51E2 1.51E2 1131 1. 14E2 1.80E1 2.00E2 2.01E2 3.3 1E2 6.66E4 3.23E-2 I132 5.08E-3 1.30E-2 6.01E-3 1. 10E-2 1.69E-2 5.13E-1 I133 1.51E1 1.60E1 3.22E1 3.98E1 6.64E1 7.40E3 I135 1.53E0 2.30E0 1.68E0 3.02Eo 4.63E0 2.67E2 Ni 65 1.46E-2 3.07 2.66E-1 2.5 1E-2 Cs 134 1.27E5 3.28E3 3.68E5 6.04E5 1.87E5 2.38E1 6.72E4 Cs 136 6.26E4 3.40E3 3.52E4 9.67E4 5.15E4 3.82E-1 7.68E3 Cs 137 7.28E4 3.12E3 5.15E5 4.93E5 1.6lE5 3.62E1 5.78E4 Ba 140 1.87E1 1.62E2 3.19E2 3.28E-1 1.40E-1 4.87E-2 2.15E-1 Ce 141 4.61E-2 4.14E1 1.08E-1 7.43E-2 5.57E-2 4.12E-2 4.12E-2 Nb 95m 2.14E1 5.28E5 4.99E1 2.92E1 2.68E1 Nb 95 1.45E2 3.75E5 5.21E2 2.03E2 1.91E2 4.16E-1 4.16E-1 La 140 1.93E-2 1.33E3 1.39E-1 5.09E-2 3.30E-3 3.30E-3 3.30E-3 Ce 144 4.31E-1 2.92E2 3.81 1.36 8.61E-1 2.40E-1 2.40E-1 Tc99m 2.29E-2 7.87E-1 7.05E-4 1.38E-3 2.01E-2 7.02E-4 Np 239 2.40E-3 1.79E2 3.44E-2 3.12E-3 7.70E-3 6.94E-4 6.94E-4 Te 132 1.38E3 1.15E4 2.57E3 1. 14E3 1.06E4 1.66E3 3.1OE-3 Zr 97 6.99E-4 1.77E2 8.1 1E-3 1.18E-3 1.69E-3 8.29E-6 8.29E-6 W 187 5.37E1 1.68E4 2.02E2 1.20E2 5.16E-5 5.16E-5 5.16E-5 Aglr0m 1.29E1 1.24E2 1.35E1 1.30E1 1.39E1 1.21E1 1.21E1 Sb 124 5.69E1 1.68E2 6.92E1 5.06E1 5.03E1 5.04E1 6.08E1 Zn 69m 6.80E1 1.87E4 3.37E2 5.75E2 3.34E2 8.05E-2 8.05E-2 Au 199 5.58 2.75E2 1.47E-1 5.02 1.80E1 1.47E-1 1.47E-1 As 76 8.31 5.47E3 1.86E-1 6.58 1.15E1 1.86E-1 1.86E-1

'Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 2 Revision 23 II 35 - December 2002

TABLE D 2-5 A, VALUES - LIQUID' INFANT mrem - ml hr-uCi NUCLIDE T BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG H3 1.87E-1 1.87E-1 -- 1.87E-1 1.87E-1 1.87E-1 1.87E-1 Cr51 8.21E-3 2.39E-1 -- - 1.17E-3 5.36E-3 1.04E-2 Cu 64 1.96E-2 8.70E-1 -- 4.24E-2 7.17E-2 -- --

Mn 54 2.73 4.42 - 1.20E1 2.67 -- --

Fe55 1.45 6.91E-1 8.42 5.44 -- - 2.66 Fe59 1.25E1 1.52E1 1.82E1 -3.18E1 - - 9.41 Co57 1.13E0 2.37E0 -- 6.95E1 - - --

Co 58 5.36 5.36 -- 2.15 -- -

Co 60 1.55E1 1.56E1 -- 6.55 -- -- --

Zn65 1.76E1 3.22E1 1.1lE1 3.81E1 1.85E1 -- --

Sr 89 4.27El 3.06E1 1.49E3 -

Sr 90 2.86E3 1.40E2 1.12E4 -- -- - -

Sr 92 1.56E-5 4.54E-3 4.21E-4 --

Zr95 2.12E-2 1.49E1 1.23E-1 2.99E-2 3.23E-2 - --

Mn56 1.81E-6 9.56E-4 -- 1.05E-5 9.05E-6 - --

Mo 99 2.65 4.48 -- 1.36E1 2.03E1 -- --

Na24 9.61E-1 9.61E-1 9.61E-1 9.61E-1 9.61E-1 9.61E-1 9.61E-1 I131 9.78 7.94E-1 1.89E1 2.22E1 2.60E1 7.31E3 -

I132 3.43E-6 7.80E-6 4.75E-6 9.63E-6 1.07E-5 4.52E-4 -

I133 8.26E-1 4.77E-1 1.94 2.82 3.31 5.13E2 - -

I135 2.38E2 2.36E2 3.29E2 6.54E2 7.28E2 5.86E0 -

Ni 65 2.96E-6 4.96E-4 5.75E-5 6.51E-6 -- -- --

Cs 134 4.30E1 1.16 2.28E2 4.26E2 1.10E2 -- 4.50E1 Cs 136 2.81E1 1.14 2.56E1 7.53E1 3.00E1 - 6.13 Cs 137 2.63E1 1.16 3.17E2 3.71E2 9.95E1 - 4.03E1 Ba 140 4.88 2.33E1 9.48E1 9.48E-2 2.25E-2 - 5.82E-2 Ce 141 3.31E-3 1.45E1 4.61E-2 2.81E-2 8.67E-3 - --

Nb 95m 1.02E3 1.20E1 2.39E3 1.73E3 1.10E3 --

Nb 95 5.87E-3 8.57 - 2.47E-2 1.02E-2 7.28E-3 - --

La 140 6.52E-4 2.98E1 6.43E-3 2.53E-3 -- -- --

Ce 144 1.01E-1 1.03E2 1.80 7.37E-1 2.98E-1 -- --

Tc 99m 3.17E-4 7.14E-3 1.19E-5 2.46E-5 2.64E-4 -- 1.28E-5 Np 239 2.08E-4 1.06E1 4.12E-3 3.68E-4 7.34E-4 --

Te 132 4.08 1.62E1 8.83 4.37 2.74E1 - 6.46 --

Zr 97 1.38E-4 1.92E1 - 1.76E-3 3.02E-4 3.04E-4 -- --

W 187 4.13E-2 7.02 1.72E-1 1.19E-1 -- -- --

Ag 110m 2.91E-1 2.28E1 6.02E-1 4.39E-1 6.28E - --

Sb 124 3.95 3.93E1 1.27E1- 1.87E-1 -- 3.38E-2 7.98 Zn69m 2.30E-2 3.50 1.24E-1 2.52E-1 1.02E-1 -- --

Au 199 2.23E-1 5.38 -- 2.48E-1 6.26E-1 - --

As76 8.67E-2 2.85E1 -- 8.46E-2 1.03E-1 --

'Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 2

'Revision 23 II 36 December 2002

TABLE D 3-1

-OFFGAS PRETREATMENT*

DETECTOR RESPONSE NUCLIDE NET CPM/1,Ci/cc Kr 83m Kr 85 4.28E + 03 Kr 85m 3.85E+03 Kr 87 6.68E+03 Kr88 3.97E +03 Kr 89 6.48E+03 Xe 131m Xe 133 1.69E+03 Xe 133m Xe 135 4.91E+03 Xe 135m Xe 137 6.89E+03 Xe 138 5.51E+03

• Values from calculation H21C-070 Unit 2 Revision 23 II 37 December 2002

TABLE D 3-2 PLUME SHINE PARAMETERS' NUCLIDE B. mrad/yr V, mremlyr uCi/sec uCi/sec Kr 83m 9.01E-7 Kr 85 6.92E-7 Kr 85m 5.09E-4 4.91E-4 Kr 87 2.72E-3 2.57E-3 Kr 88 7.23E-3 7.04E-3 Kr 89 1.15E-2 1. 13E-2 Kr 90 6.57E-3 4.49E-3 Xe 131m 7.76E-6 Xe 133 7.46E-5 6.42E-5 Xe 133m 4.79E-5 3.95E-5 Xe 135 7.82E-4 7.44E-4 Xe 135m 1.45E-3 1.37E-3 Xe 137 6.25E-4 5.98E-4 Xe 138 4.46E-3 4.26E-3 Xe-127 1.96E-3 1.3 1E-3 Ar41 5.OOE-3 4.79E-3 B. and V; are calculated for critical site boundary location; 1.6km in the easterly direction. See Appendix B. Those values that show a dotted line were negligible because of high energy absorption coefficients.

Unit 2 Revision 23 II 38 December 2002

TABLE D 3-3 IMMERSION DOSE FACTORS1 3 -

Nuclide K (ty-Bodv)2 Li (13-Skin)2 &'(y-Air) 3 N, (0-Air)3 Kr 83m 7.56E-02 1.93E1 2.88E2 Kr 85m 1.17E3 1.46E3 1.23E3 1.97E3 Kr 85 1.61E1 1.34E3 1.72E1 1.95E3 Kr 87 5.92E3 9.73E3 6.17E3 1.03E4 Kr 88 1.47E4 2.37E3 1.52E4 2.93E3 Kr 89 1.66E4 1.01E4 1.73E4 1.06E4 Kr 90 1.56E4 7.29E3 1.63E4 7.83E3 Xe 131m 9.15E1 4.76E2 1.56E2 1.11E3 Xe 133m 2.51E2 9.94E2 3.27E2 1.48E3 Xe 133 2.94E2 3.06E2 3.53E2 1.05E3 Xe 135m 3.12E3 7.1 1E2 3.36E3 7.39E2 Xe 135 1.81E3 1.86E3 1.92E3 2.46E3 Xe 137 1.42E3 1.22E4 1.51E3 1.27E4 Xe 138 8.83E3 4.13E3 9.21E3 4.75E3 Ar 41 8.84E3 2.69E3 9.30E3 3.28E3

'From, Table B-i .Regulatory Guide 1.109 Rev. 1 2 mrem/yr per uCi/m 3 .

3mrad/yr per uCi/m3 .

- Unit 2 Revision 23 II 39 December 2002

TABLE D 3-4 DOSE AND DOSE RATE RI VALUES - INHALATION - INFANT' mrem/yr uci/m3 NUCLIDE BONE LIVER - T. BODY THYROID KIDNEY LUNG GI-LLI H 3* 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 C 14* 2.65E4 5.31E3 5.3 1E3 5.3 1E3 5.3 1E3 5.3 1E3 5.3 1E3 Cr51 8.95E1 5.75E1 1.32E1 1.28E4 3.57E2 Mn 54 2.53E4 4.98E3 4.98E3 1.OOE6 7.06E3 Fe 55 1.97E4 1. 17E4 3.33E3 8.69E4 1.09E3 Fe59 1.36E4 2.35E4 9.48E3 1.02E6 2.48E4 Co 58 1.22E3 1.82E3 7.77E5 1.11E4 Co 60 8.02E3 1.1 8E4 4.5 1E6 3.19E4 Zn 65 1.93E4 6.26E4 3.1 1E4 3.25E4 6.47E5 5.14E4 Sr 89 3.98E5 1. 14E4 2.03E6 - 6.40E4 Sr 90 4.09E7 2.59E6 1.12E7 1.3 1E5 Zr 95 1. 15E5 2.79E4 2.03E4 3.1 1E4 1.75E6 2.17E4 Nb 95 1.57E4 6.43E3 3.78E3 4.72E3 4.79E5 1.27E4 Mo 99 1.65E2 3.23E1 2.65E2 1.35E5 4.87E4 1-131 3.79E4 4.44E4 1.96E4 1.48E7 5.18E4 1.06E3 I133 1.32E4 1.92E4 5.60E3 -3.56E6 2.24E4 2.16E3 Cs 134 3.96E5 7.03E5 7.45E4 1.9OE5 7.97E4 1.33E3 Cs 137 5.49E5 6.12E5 4.55E4 1.72E5 7.13E4 1.33E3 Ba 140 5.60E4 5.60E1 2.90E3 1.34E1 1.60E6 3.84E4 La 140 5.05E2 2.00E2 5.15E1 1.68E5 8.48E4 Ce 141 2.77E4 1.67E4 1.99E3 5.25E3 5.17E5 2.16E4 3.19E6 1.21E6 1.76E5 5.38E5 9.84E6 1.48E5 Ce 144 Nd 147 7.94E3 8.13E3 5.00E2 3.15E3 3.22E5 3.12E4 Ag lOnm 9.99E3 7.22E3 5.00E3 1.09E4 3.67E6 3.30E4 3

• mremn/yr per pCi/rn

'This and following R, Tables Calculated in accordance with NUREG 0133, Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109 Equation C-8.

Unit 2 Revision 23 II 40 December 2002

TABLE D 3-5 DOSE AND DOSE RATE R, VALUES - INHALATION - CHILD mrem/yr 3

uCi/m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 1.12E3 1.12E3 1.12E3 1.12E3 1.12E3 1.12E3 C 14* 3.59E4 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 Cr51 1.54E2 8.55E1 -2.43E1 1.70E4 1.08E3 Mn 54 4.29E4 9.5 1E3 1.00E4 1.58E6 2.29E4 Fe 55 4.74E4 2.52E4 7.77E3 1.11E5 2.87E3 Fe59 2.07E4 3.34E4 1.67E4 1.27E6 7.07E4 Co58 1.77E3 3.16E3 1.1lE6 3.44E4 Co 60 1.31E4 2.26E4 7.07E6 9.62E4 Zn 65 4.26E4 1. 13E5 7.03E4 7.14E4 9.95E5 1.63E4 Sr 89 5.99E5 1.72E4 2.16E6 1.67E5 Sr 90 1.01E8 6.44E6 1.48E7 3.43E5 Zr 95 1.9OE5 4.18E4 3.70E4 5.96E4 2.23E6 6.11E4 Nb 95 2.35E4 9.18E3 6.55E3 8.62E3 6.14E5 3.70E4 Mo 99 1.72E2 4.26E1 3.92E2 1.35E5 1.27E5 1131 4.81E4 4.81E4 2.73E4 1.62E7 7.88E4 2.84E3 I133 1.66E4 2.03E4 7.70E3 3.85E6 3.38E4 5.48E3 Cs 134 6.5 1E5 1.01E6 2.25E5 3.30E5 1.21E5 3.85E3 Cs 137 9.07E5 8.25E5 1.28E5 2.82E5 1.04E5 3.62E3 Ba 140 7.40E4 6.48E1 4.33E3 2.11E1 1.74E6 1.02E5 La 140 6.44E2 2.25E2 7.55E1 1.83E5 2.26E5 Ce 141 - 3.92E4 1.95E4 2.90E3 8.55E3 5.44E5 5.66E4 Ce 144 6.77E6 2.12E6 3.61E5 1.17E6 1.20E7 3.89E5 Nd 147 1.08E4 8.73E3 6.8 1E2 4.81E3 3.28E5 8.21E4 Ag lOnm 1.69E4 1. 14E4 9.14E3 2.12E4 5.48E6 1.OOE5

• mrem/yr per pLCihf3 Unit 2 Revision 23 II41 December 2002

TABLE D 3-6 DOSE AND DOSE RATE RI VALUES - INHALATION - TEEN mrem/yr uCilm 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 C 14* 2.60E4 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 Cr51 1.35E2 7.50E1 3.07E1 2. 10E4 3.00E3 Mn 54 5.11E4 8.40E3 1.27E4 1.98E6 6.68E4 Fe55 3.34E4 2.38E4 5.54E3 1.24E5 6.39E3 Fe59 1.59E4 3.70E4 1.43E4 1.53E6 1.78E5 Co 58 2.07E3 2.78E3 1.34E6 9.52E4 Co 60 1.51E4 1.98E4 8.72E6 2.59E5 Zn 65 3.86E4 1.34E5 6.24E4 8.64E4 1.24E6 4.66E4 Sr 89 4.34E5 1.25E4 2.42E6 3.71E5 Sr 90 1.08E8 6.68E6 1.65E7 7.65E5 Zr 95 1.46E5 4.58E4 3.15E4 6.74E4 2.69E6 1.49E5 Nb 95 1.86E4 1.03E4 5.66E3 1.00E4 7.5 1E5 9.68E4 Mo 99 1.69E2 3.22E1 4.11E2 1.54E5 2.69E5 I 131 3.54E4 4.91E4 2.64E4 1.46E7 8.40E4 6.49E3 I 133 1.22E4 2.05E4 6.22E3 2.92E6 3.59E4 1.03E4 Cs 134 5.02E5 1.13E6 5.49E5 3.75E5 1.46E5 9.76E3 Cs 137 6.70E5 8.48E5 3.11E5 3.04E5 1.21E5 8.48E3 Ba 140 5.47E4 6.70E1 3.52E3 2.28E1 2.03E6 2.29E5 La 140 4.79E2 2.36E2 6.26E1 2.14E5 4.87E5 Ce 141 2.84E4 1.9OE4 2.17E3 8.88E3 6.14E5 1.26E5 Ce 144 4.89E6 2.02E6 2.62E5 1.21E6 1.34E7 8.64E5 Nd 147 7.86E3 8.56E3 5.13E2 5.02E3 3.72E5 1.82E5 Ag 110m 1.38E4 1.31E4 7.99E3 2.50E4 6.75E6 2.73E5 3

• mremlyr per pLCilm Unit 2 Revision 23 II 42 December 2002

TABLE D 3-7 DOSE AND DOSE RATE Ri VALUES - INHALATION - ADULT mrem/yr uci/m3 -

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG .

GI-LLI -

1.26E3 1.26E3 1.26E3 1.26E3 1.26E3 1.26E3 H3*

1.82E4 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 C 14*

Cr51 1.OOE2 5.95E1 2.28E1 1.44E4 3.32E3 3.96E4 6.30E3 9.84E3 1.40E6 7.74E4 Mn 54 2.46E4 1.70E4 3.94E3 7.21E4 6.03E3 Fe 55 1.18E4 2.78E4 1.06E4 1.02E6 1.88E5 Fe59 1.58E3 2.07E3 9.28E5 1.06E5 Co58-

1. 15E4 1.48E4 5.97E6 2.85E5 Co 60 3.24E4 1.03E5 4.66E4 6.90E4 8.64E5 5.34E4 Zn 65 3.04E5 8.72E3 1.40E6 3.50E5 Sr 89 9.92E7 6.10E6 9.60E6 7.22E5 Sr90 1.07E5 3.44E4 2.33E4 5.42E4 1.77E6 1.50E5 Zr 95 1.41E4 7.82E3 4.21E3 7.74E3 5.05E5 1.04E5 Nb 95 1.21E2 2.30E1 2.9 1E2 9.12E4 2.48E5 Mo 99 1.19E7 6.13E4 - 6.28E3 1131 2.52E4 3.58E4 2.05E4 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 8.88E3 I133 3.73E5 8.48E5 7.28E5 2.87E5 9.76E4 1.04E4 Cs 134 4.78E5 6.21E5 4.28E5 2.22E5 7.52E4 8.40E3 Cs 137 3.90E4 4.90E1 2.57E3 1.67E1 1.27E6 2.18E5 Ba 140 3.44E2 1.74E2 4.58E1 1.36E5 4.58E5 La 140 1.99E4 1.35E4 1.53E3 6.26E3 3.62E5 1.20E5 Ce 141 3.43E6 1.43E6 1.84E5 8.48E5 7.78E6 8.16E5 Ce 144 5.27E3 6.10E3 3.65E2 3.56E3 2.21E5 1.73E5 Nd 147 1.08E4 1.OOE4 5.94E3 1.97E4 4.63E6 3.02E5 Agl Onm

• mrem/yr per ,Ciim' Unit 2 Revision 23 II 43 December 2002

TABLE D 3-8 DOSE AND DOSE RATE R,VALUES - GROUND PLANE ALL AGE GROUPS m2-mrem/yr uCi/sec NUCLIDE TOTAL BODY SKIN H 3 C 14 Cr51 4.65E6 5.50E6 Mn54 1.40E9 1.64E9 Fe55 Fe 59 2.73E8 3.20E8 Co58 3.80E8 4.45E8 Co 60 2.15E10 2.53E10 Zn 65 7.46E8 8.57E8 Sr89 2.16E4 2.51E4 Sr 90 Zr 95 2.45E8 2.85E8 Nb 95 1.36E8 -1.61E8 Mo 99 3.99E6 4.63E6 I131 1.72E7 2.09E7 I133 2.39E6 2.91E6 Cs 134 6.83E9 7.97E9 Cs 137 1.03E10 1.20E10 Ba 140 2.05E7 2.35E7 La 140 1.92E7 2.18E7 Ce 141 1.37E7 1.54E7 Ce 144 6.96E7 8.07E7 Nd 147 8.46E6 1.01E7 Ag lOnm 3.44E9 4.01E9 Unit 2 Revision 23 11 44 December 2002

TABLE D 3-9 DOSE AND DOSE RATE RI VALUES - COW MILK - INFANT m2 -mrem/yr uCilsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 H3 -

3.23E6 6.89E5 6.89E5 6.89E5 6.89E5 6.89E5 6.89E5 C 14

-- 8.35E4 5.45E4 1.19E4 1.06E5 2.43E6 Cr51 --

2.51E7 5.68E6 -- 5.56E6 -- 9.21E6 Mn54 --

8.43E7 5.44E7 1.45E7 -- - 2.66E7 6.91E6 Fe 55 1.22E8 2.13E8 8.38E7 - -- 6.29E7 1.02E8 Fe59 1.39E7 3.46E7 - -- -- 3.46E7 Co58 --

5.90E7 1.39E8 -- -- -- 1.40E8 Co60 --

3.53E9 1.21E10 5.58E9 - 5.87E9 - 1.02E10 Zn 65 6.93E9 1.99E8 - -- - 1.42E8 Sr89 --

8.19E10 2.09E10 -- -- 1.02E9 Sr90 --

3.85E3 9.39E2 6.66E2 -- 1.01E3 - 4.68E5 Zr95 4.21E5 1.64E5 1.17E5 - 1.54E5 - 3.03E8 Nb 95 1.04E8 2.03E7 - 1.55E8 -- 3.43E7 Mo 99 --

6.81E8 8.02E8 3.53E8 2.64E11 9.37E8 -- 2.86E7 I131 1.24E7 3.63E6 2.26E9 1.46E7 - 2.10E6 I 133 -8.52E6 2.41E10 4.49E10 4.54E9 - 1.16E10 4.74E9 1.22E8 Cs 134 3.47E10 4.06E10 2.88E9 - 1.09E10 4.41E9 1.27E8 Cs 137 1.21E8 1.21E5 6.22E6 -- 2.87E4 7.42E4 2.97E7 Ba 140 2.03E1 7.99 2.06 -- - - 9.39E4 La 140 2.28E4 1.39E4 1.64E3 - 4.28E3 -- 7.18E6 Ce 141 1.49E6 6.10E5 8.34E4 -- 2.46E5 -- 8.54E7 Ce 144 4.43E2 4.55E2 2.79E1 -- 1.76E2 -- 2.89E5 Nd 147 2.46E8 1.79E8 1.19E8 -- 2.56E8 -- 9.29E9 Ag lOrm 3

rnreniyr per +/-ci/rm .

Unit 2 Revision 23 II 45 December 2002

TABLE D 3-10 DOSE AND DOSE RATE R, VALUES - COW MILK - CHILD ni-mrem/yr uCilsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY .

LUNG GI-LLI H 3- 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 C 14 1.65E6 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 Cr 51 5.27E4 2.93E4 7.99E3 5.34E4 2.80E6 Mn54 1.35E7 3.59E6 3.78E6 1. 13E7 Fe55 6.97E7 3.07E7 1. 15E7 2.09E7 6.85E6 Fe59 6.52E7 1.06E8 5.26E7 3.06E7 1.10E8 Co 58 6.94E6 2.13E7 4.05E7 Co 60 2.89E7 8.52E7 1.60E8 Zn 65 2.63E9 7.00E9 4.35E9 4.41E9 1.23E9 Sr89 3.64E9 1.04E8 1.41E8 Sr90 7.53E10 1.91E10 1.01E9 Zr 95 2.17E3 4.77E2 4.25E2 6.83E2 4.98E5 Nb 95 1.86E5 1.03E4 5.69E4 1.OOE5 4.42E8 Mo 99 4.07E7 1.01E7 8.69E7 3.37E7 1131 3.26E8 3.28E8 1.86E8 1.08E1 1 5.39E8 2.92E7 I133 4.04E6 4.99E6 1.89E6 9.27E8 8.32E6 2.01E6 Cs 134 1.50E10 2.45E10 5.18E9 7.61E9 2.73E9 1.32E8 Cs 137 2.17E10 2.08E10 3.07E9 6.78E9 2.44E9 1.30E8 Ba 140 5.87E7 5.14E4. 3.43E6 1.67E4 3.07E4 2.97E7 La 140 9.70 3.39 1.14 9.45E4 Ce 141 1. 15E4 5.73E3 8.5 1E2 2.5 1E3 7.15E6 Ce 144 1.04E6 3.26E5 5.55E4 1.80E5 8.49E7 Nd 147 2.24E2 1.81E2 1.40E1 9.94E1 2.87E5 Ag 11m 1.33E8 8.97E7 7.17E7 1.67E8 1.07E10 3

mrrenmyr per ,Ci/m 1 .

Unit 2 Revision 23 II 46 December 2002

TABLE D 3-11 DOSE AND DOSE RATE Ri VALUES -COW MILK - TEEN m -mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 - 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 C 14 6.70E5 1.34E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr51 - -- 2.58E4 1.44E4 5.66E3 3.69E4 4.34E6 Mn54 -- 9.01E6 1.79E6 -- 2.69E6 - 1.85E7 Fe 55 2.78E7 1.97E7 4.59E6 -- - 1.25E7 8.52E6 Fe59 2.81E7 6.57E7 2.54E7 - - -- 2.07E7 1.55E8 Co58 -- 4.55E6 - 1.05E7 - -- - 6.27E7 Co60 -- 1.86E7 4.19E7 - - - 2.42E8 Zn 65 1.34E9 4.65E9 2.17E9 -- 2.97E9 - 1.97E9 Sr 89 1.47E9 - 4.21E7 -- -- -- 1.75E8 Sr 90 4.45E10 - 1.10E10 - -- -- 1.25E9 Zr 95 9.34E2 2.95E2 2.03E2 - 4.33E2 - 6.80E5 Nb 95 1.86E5 1.03E5 5.69E4 -- 1.00E5 - 4.42E8 Mo 99 - 2.24E7 4.27E6 -- 5.12E7 -- 4.01E7 I131 1.34E8 1.88E8 1.01E8 5.49E10 3.24E8 -- 3.72E7 1133 1.66E6 2.82E6 8.59E5 3.93E8 4.94E6 - 2.13E6 Cs 134 6.49E9 1.53E10 7.08E9 -- 4.85E9 1.85E9 1.90E8 Cs 137 9.02E9 1.20E10 4.18E9 -- 4.08E9 1.59E9 1.71E8 Ba 140 2.43E7 2.98E4 1.57E6 -- 1.01E4 2.00E4 3.75E7 La 140 4.05 1.99 5.30E-1 - - - 1.14E5 Ce 141 4.67E3 3.12E3 3.58E2 - 1.47E3 - 8.91E6 Ce 144 4.22E5 1.74E5 2.27E4 -- 1.04E5 -- 1.06E8 Nd 147 9.12E1 9.91E1 5.94E0 - 5.82E1 -- 3.58E5 Ag lOnm' 6.13E7 5.80E7 3.53E7 -- 1.11E8 - 1.63E10 mremlyr per pLCihn3 .

Unit 2 Revision 23 II 47 December 2002

TABLE D 3-12 DOSE AND DOSE RATE R, VALUES - COW MILK - ADULT M -mrem/yr uCilsec LIVER T. BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE BONE -

7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 H 3 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 C 14 3.63E5 1.48E4 8.85E3 3.26E3 1.96E4 3.72E6 Cr51 5.41E6 1.03E6 1.61E6 1.66E7 Mn54 1.08E7 2.52E6 6.04E6 6.21E6 Fe55 1.57E7 3.79E7 1.45E7 - 1.06E7 1.26E8 Fe 59 1.61E7 2.70E6 6.05E6 5.47E7 Co 58

1. 10E7 2.42E7 2.06E8 Co 60 8.71E8 2.77E9 1.25E9 1.85E9 1.75E9 Zn 65 2.29E7 1.28E8 Sr89 7.99E8 7.74E9 9. 1E8 Sr90 3.15E10 1.71E2 1.16E2 2.69E2 5.43E5 Zr 95 5.34E2 6.07E4 3.27E4 6.00E4 3.69E8 Nb 95 1.09E5 1.24E7 2.36E6 2.8 1E7 2.87E7 Mo 99 7.41E7 1.06E8 6.08E7 3.47E10 1.82E8 - 2.80E7 I131 9.09E5 1.58E6 4.82E5 2.32E8 2.76E6 1.42E6 I133 8.89E9 7.27E9 2.88E9 9.55E8 1.56E8 Cs 134 3.74E9 6.80E9 4.46E9 2.3 1E9 7.68E8 1.32E8 Cs 137 4.97E9 1.69E4 8.83E5 5.75E3 9.69E3 2.77E7 Ba 140 1.35E7 1.14 3.01E-1 8.35E4 La 140 2.26 1.72E3 1.95E2 7.99E2 6.58E6 Ce 141 2.54E3 9.58E4 1.23E4 5.68E4 7.74E7 Ce 144 2.29E5 5.48E1 3.28E0 3.20E1 2.63E5 Nd 147 4.74E1 3.43E7 2.04E7 6.74E7 1.40E10 Ag lOnm 3.71E7 rnrern/yr per pCi&m-.

Unit 2 Revision 23 II 48 December 2002

TABLE D 3-13 DOSE AND DOSE RATE R1 VALUES - GOAT MILK - INFANT m2-mrem/yr uCitsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3- 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 C 14- 3.23E6 6.89E5 6.89E5 6.89E5 6.89E5 6.89E5 6.89E5 Cr51 1.00E4 6.56E3 1.43E3 1.28E4 2.93E5 Mn 54 3.01E6 6.82E5 6.67E5 1.11E6 FeS5 1.10E6 7.08E5 1.89E5 3.46E5 8.98E4 Fe 59 1.59E6 2.78E6 1.09E6 8.2lE5 1.33E6 Co 58 1.67E6 4.16E6 4.16E6 Co 60 7.08E6 1.67E7 1.68E7 Zn 65 4.24E8 1.45E9 6.70E8 7.04E8 1.23E9 Sr 89 1.48E10 4.24E8 3.04E8 Sr90 1.72Ell 4.38E10 2.15E9 Zr 95 4.66E2 1.13E2 8.04E1 1.22E2 5.65E4 Nb 95 9.42E4 3.88E4 2.24E4 2.78E4 3.27E7 Mo 99 1.27E7 2.47E6 1.89E7 4.17E6 I131 8.17E8 9.63E8 4.23E8 3.16El1 1.12E9 3 .44E7 I133 1.02E7 1.49E7 4.36E6 2.71E9 1.75E7 2.52E6 Cs 134 7.23E10 1.35Ell 1.36E10 3.47E10 1.42E10 3.66E8 Cs 137 1.04E1l 1.22Ell 8.63E9 3.27E10 1.32E10 3.81E8 Ba 140- 1.45E7 1.45E4 7.48E5 3.44E3 8.91E3 3.56E6 La 140 2.430 9.59E-1 2.47E-1 1. 13E4 Ce 141 2.74E3 1.67E3 1.96E2 - 5.14E2 8.62E5 Ce 144 1.79E5 7.32E4 1.00E4 2.96E4 1.03E7 Nd 147 5.32E1 5.47E1 3.35EO 2.1 lEl 3.46E4 Ag lOrm 2.95E7 2.15E7 1.43E7 3.07E7 1.11E9 mrem/yr per j 1Ci&m3.

Unit 2 Revision 23 II 49 December 2002

TABLE D 3-14 DOSE AND DOSE RATE R1 VALUES - GOAT MULK - CHILD m2-mrem/yr uCitsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 -- 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 C 14' 1.65E6 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 Cr 51 -- -- 6.34E3 3.52E3 9.62E2 6.43E3 3.36E5 Mn54 - 1.62E6 4.31E5 -- 4.54E5 -- 1.36E6 Fe 55 9.06E5 4.811E5 1.49E5 -- -- 2.72E5 8.91E4 Fe 59 8.52E5 1.38E6 6.86E5 -- -- 3.99E5 1.43E6 Co58 -- 8.35E5 2.56E6 -- -- - 4.87E6 Co60 -- 3.47E6 1.02E7 -- - - 1.92E7 Zn65 3.15E8 8.40E8 5.23E8 -- 5.29E8 -- 1.48E8 Sr 89 7.77E9 -- 2.22E8 - -- - 3.01E8 Sr 90 1.58El1 -- 4.01E10 - -- - - 2.13E9 Zr 95 2.62E2 5.76E1 5.13E1 -- 8.25E1 -- 6.01E4 Nb 95 5.05E4 1.96E4 1.40E4 -- 1.85E4 -- 3.63E7 Mo 99 -- 4.95E6 1.22E6 -- 1.06E7 -- 4.09E6 I131 3.91E8 3.94E8 2.24E8 1.30E11 6.46E8 -- 3.50E7 I133 4.84E6 5.99E6 2.27E6 1.11E9 9.98E6 - 2.41E6 Cs 134 4.49E10 7.37E10 1.55E10 - 2.28E10 8.19E9 3.97E8 Cs 137 6.52E10 6.24E10 9.21E9 - 2.03E10 7,32E9 3.91E8 Ba 140 7.05E6 6.18E3 - 4.12E5 - 2.01E3 3.68E3 3.57E6 La 140 1.16 - 4.07E-1 1.37E-1 - -- -- 1.13E4 Ce 141 1.38E3 6.88E2 1.02E2 - 3.02E2 -- 8.59E5 Ce 144 1.25E5 3.911E4 6.66E3 -- 2.16E4 -- 1.02E7 Nd 147 2.68E1 2.17E1 1.68E0 -- 1.19El -- 3.44E4 Ag 110m 1.60E7 1.08E7 8.60E6 -- 2.00F,7 -- 1.28E9 mremlyr per ,Ci/mh.

Unit 2 Revision 23 II 50 December 2002

TABLE D 3-15 DOSE AND DOSE RATE RiVALUES- GOAT MILK-TEEN MZmrem/yr uCilsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 2.64E3 2.64E3 2.64E3 2.64E3 2.64E3 2.64E3 C 14' 6.70E5 1.34E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr51 3.11E3 1.73E3 6.82E2 4.44E3 5.23E5 Mn54 1.08E6 2.15E5 3.23E5 2.22E6 Fe 55 3.61E5 2.56E5 5.97E4 1.62E5 1.1lE5 Fe59 3.67E5 8.57E5 3.3 IE5 2.70E5- 2.03E6 Co58 5.46E5 1.26E6 7.53E6 Co 60 2.23E6 5.03E6 2.91E7 Zn 65 1.61E8 5.58E8 2.60E8 3.57E8 2.36E8 Sr89 3.14E9 8.99E7 3.74E8 Sr 90 9.36E10 2.31E10 2.63E9 Zr 95 1.13E2 3.56E1 2.45E1 5.23E1 8.22E4 Nb 95 2.23E4 1.24E4 6.82E3 1.20E4 5.30E7 Mo 99 2.72E6 5.19E5 6.23E6 4.87E6 I131 1.61E8 2.26E8 1.21E8 6.59E10 3.89E8 4.47E7 I133 1.99E6 3.38E6 1.03E6 4.72E8 5.93E6 2.56E6 Cs 134 1.95E10 4.58E10 2.13E10 1.46E10 5.56E9 5.70E8 Cs 137 2.71E10 3:60E10 1.25E10 1.23E10 4.76E9 5.12E8 Ba 140 2.92E6 3.58E3 1.88E5 1.21E3 2.41E3 4.50E6 La 140 4.86E-1 2.39E-1 6.36E-2 1.37E4 Ce 141 5.60E2 3.74E2 4.30E1 1.76E2 1.07E6 Ce 144 5.06E4 2.09E4 2.72E3 1.25E4 1.27E7 Nd 147 1.09E1 1. 19E I 7.13E-1 6.99E0 4.29E4 Ag 10m 7.36E6 6.96E6 4.24E6 1.33E7 1.96E9

• mremlyr per LCi&m3 .

Unit 2 Revision 23 11 51 December 2002

TABLE D 3-16 DOSE AND DOSE RATE Ri VALUES - GOAT MILK - ADULT m2 -mrem/vr uCilsec -

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY .

LUNG GI-LLI H 3 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 C 14' 3.63E5 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr51 1.78E3 1.06E3 3.92E2 2.36E3 4.48E5 Mn 54 6.50E5 1.24E5 1.93E5 1.99E6 Fe55 2.04E5 1.41E5 3.28E4 7.85E4 8.07E4 Fe59 2. 10E5 4.95E5 1.90E5 1.38E5 1.65E6 Co 58 3.25E5 7.27E5 6.58E6 Co 60 1.32E6 2.91E6 2.48E7 Zn 65 1.05E8 3.33E8 1.51E8 2.23E8 2.10E8 Sr89 1.70E9 4.89E7 2.73E8 Sr 90 6.62E10 1.63E10 1.91E9 Zr 95 6.45E1 2.07E1 1.40E1 3.25E1 6.56E4 Nb 95 1.31E4 7.29E3 3.92E3 7.21E3 4.42E7 Mo 99 1.51E6 2.87E5 3.41E6 3.49E6 I131 8.89E7 1.27E8 7.29E7 4.17E10 2.18E8 3.36E7 1133 1.09E6 1.90E6 5.79E5 2.79E8 3.3 1E6 1.71E6 Cs 134 1.12E10 2.67E10 2.18E10 8.63E9 2.86E9 4.67E8 Cs 137 1.49E10 2.04E10 1.34E10 6.93E9 2.30E9 3.95E8 Ba 140 1.62E6 2.03E3 1.06E5 6.91E2 1.1 6E3 3.33E6 La 140 2.71E-1 1.36E-1 3.61E-2 1.00E4 Ce 141 3.06E2 2.07E2 2.34E1 9.60E1 7.90E5 Ce 144 2.75E4 1.15E4 1.48E3 6.82E3 9.30E6 Nd 147 5.69E0 6.57E0 3.93E-1 3.84E0 3.15E4 Ag 110m 4.45E6 4.12E6 2.45E6 8.09E6 1.68E9 -

• mremlyr per [,Cifm 3.

Unit 2 Revision 23 II 52 December 2002

TABLE D 3-17 DOSE AND DOSE RATE R, VALUES - COW MEAT - CHILD m2 -mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 C 14- 5.29E5 1.06E5 1.06E5 1.06E5 1.06E5 1.06E5 - 1.06E5 Cr51 4.55E3 2.52E3 6.90E2 4.61E3 2.41E5 Mn 54 5.15E6 1.37E6 1.44E6 4.32E6 Fe55 2.89E8 1.53E8 4.74E7 8.66E7 2.84E7 Fe 59 2.04E8 3.30E8 1.65E8 9.58E7 3.44E8 Co58 9.41E6 2.88E7 5.49E7 Co 60 4.64E7 1.37E8 2.57E8 Zn 65 2.38E8 6.35E8 3.95E8 4.00E8 1. 12E8 Sr89 2.65E8 7.57E6 1.03E7 Sr90 7.01E9 1.78E9 9.44E7 Zr 95 1.51E6 3.32E5 2.95E5 4.75E5 3.46E8 Nb 95 4.10E6 1.59E6 1.14E6 1.5OE6 2.95E9 Mo 99 5.42E4 1.34E4 1.16E5 4.48E4 I131 4.15E6 4.18E6 2.37E6 1.38E9 6.86E6 3.72E5 I133 9.38E-2 1.16E-1 4.39E-2 2.15E1 1.93E-1 4.67E-2 Cs 134 6.09E8 1.OOE9 2.11E8 3. lOE8 1.1lE8 5.39E6 Cs 137 8.99E8 8.60E8 1.27E8 2.80E8 1.01E8 5.39E6 Ba 140 2.20E7 1.93E4 1.28E6 6.27E3 1. 15E4 1.11E7 La 140 2.80E-2 9.78E-3 3.30E-3 2.73E2 Ce 141 1. 17E4 5.82E3 8.64E2 2.55E3 7.26E6 Ce 144 1.48E6 4.65E5 7.91E4 2.57E5 1.21E8 Nd 147 5.93E3 4.80E3 3.72E2 2.64E3 7.61E6 Ag lOnm 5.62E6 3.79E6 3.03E6 7.05E6 4.52E8 rmrern/yr per 1,Ci/m 3.

Unit 2 Revision 23 II 53 December 2002

TABLE D 3-18 DOSE AND DOSE RATE RI VALUES - COW MEAT - TEEN 2 -mrem/yr a

uCi/sec .

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 C 14 2.8 1E5 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 Cr51 2.93E3 1.62E3 6.39E2 4.16E3 4.90E5 Mn 54 4.50E6 8.93E5 1.34E6 9.24E6 Fe 55 1.50E8 1.07E8 2.49E7 6.77E7 4.62E7 Fe59 1. 15E8 2.69E8 1.04E8 8.47E7 6.36E8 Co58 8.05E6 1.86E7 1.11E8 Co 60 3.90E7 8.80E7 5.09E8 Zn 65 1.59E8 5.52E8 2.57E8 3.53E8 2.34E8 Sr89 1.40E8 4.01E6 1.67E7 Sr 90 5.42E9 1.34E9 1.52E8 Zr 95 8.50E5 2.68E5 1.84E5 3.94E5 6.19E8 Nb 95 2.37E6 1.32E6 7.24E5 1.28E6 5.63E9 Mo 99 3.90E4 7.43E3 8.92E4 6.98E4 I131 2.24E6 3.13E6 1.68E6 9.15E8 5.40E6 6.20E5 I133 5.05E-2 8.57E-2 2.6 1E-2 1.20E1 1.50E-1 6.48E-2 Cs 134 3.46E8 8.13E8 3.77E8 2.58E8 9.87E7 1.01E7 Cs 137 4.88E8 6.49E8 2.26E8, 2.21E8 8.58E7 9.24E6 Ba 140 1. 19E7 1.46E4 7.68E5 4.95E3 9.8 1E3 1.84E7 La 140 1.53E-2 7.51E-3 2.OOE-3 4.31E2 Ce 141 6.19E3 4.14E3 4.75E2 1.95E3 1.18E7 Ce 144 7.87E5 3.26E5 4.23E4 1.94E5 1.98E8 Nd 147 3.16E3 3.44E3 2.06E2 2.02E3 1.24E7 Ag lOrm 3.39E6 3.20E6 1.95E7 6.13E6 9.01ES

• mremn/yrper pICi/d 3 .

Unit 2 Revision 23 If 54 December 2002

TABLE D 3-19 DOSE AND DOSE RATE RI VALUES - COW MEAT - ADULT n9-mrem/yr uCilsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 3.25E2 3.25E2 3.25E2 3.25E2 3.25E2 3.25E2 C 14- 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 Cr51 3.65E3 2;18E3 8.03E2 4.84E3 9.17E5 Mn54 5.90E6 1. 13E6 1.76E6 1.81E7 Fe55 1.85E8 1.28E8 2.98E7 7.14E7 7.34E7 Fe 59 1.44E8 3.39E8 1.30E8 9.46E7 1.13E9 Co 58 1.04E7 2.34E7 2.12E8 Co 60 5.03E7 1.1 1E8 9.45E8 Zn 65 2.26E8 7.19E8 3.25E8 4.81E8 4.53E8 Sr89 1.66E8 4.76E6 2.66E7 Sr 90 8.38E9 2.06E9 2.42E8 Zr 95 1.06E6 3.40E5 2.30E5 5.34E5 1.08E9 Nb 95 3.04E6 1.69E6 9.08E5 1.67E6 1.03E10 Mo 99 4.71E4 8.97E3 1.07E5 1.09E5 I131 2.69E6 3.85E6 2.21E6 1.26E9 6.61E6 1.02E6 I133 6.04E-2 1.05E-1 3.20E-2 1.54E1 1.83E-1 9.44E-2 Cs 134 4.35E8 1.03E9 8.45E8 3.35E8 1.11E8 1.81E7 Cs 137 5.88E8 8.04E8 5.26E8 2.73E8 9.07E7 1.56E7 Ba 140 1.44E7 1.81E4 9.44E5 6.15E3 1.04E4 2.97E7 La 140 1.86E-2 9.37E-3 2.48E-3 6.88E2 Ce 141 7.38E3 4.99E3 5.66E2 2.32E3 1.91E7 Ce 144 9.33E5 3.90E5 5.01E4 2.3 1E5 3.16E8 Nd 147 3.59E3 4.15E3 2.48E2 2.42E3 1.99E7 Ag 110m 4.48E6 4.14E6 2.46E6 8.13E6 1.69E9 3.

• rreninyr perp+/-Cinm Unit 2 Revision 23 II55 December 2002

TABLE D 3-20 DOSE AND DOSE RATE R, VALUES - VEGETATION - CHILD m 2 -mrem/yr uCilsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3' ~4.01E3 4.01E3 4.01E3 4.01E3 4.01E3 4.01E3 C 14- 3.50E6 7.01E5 7.0lE5 7.01E5 7.01E5 7.01E5 7.01E5 Cr 51 1. 17E5 6.49E4 1.77E4 1.18E5 6.20E6 Mn 54 6.65E8 1.77E8 1.86E8 5.58E8 Fe 55 7.63E8 4.05E8 1.25E8 2.29E8 7.50E7 Fe 59 3.97E8 6.42E8 3.20E8 1.86E8 6.69E8 Co 58 6.45E7 1.97E8 3.76E8 Co 60 3.78E8 1. 12E9 2. 10E9 Zn 65 8.12E8 2.16E9 1.35E9 1.36E9 3.80E8 Sr 89 3.59E10 1.03E9 1.39E9 Sr 90 1.24E12 3.15Ell 1.67E10 Zr 95 3.86E6 8.50E5 7.56E5 1.22E6 8.86E8 Nb 95 1.02E6 3.99E5 2.85E5 3.75E5 7.37E8 Mo 99 7.70E6 1.91E6 1.65E7 6.37E6 1131 7.16E7 7.20E7 4.09E7 2.38E10 1.18E8 6.41E6 1133 1.69E6 2.09E6 7.92E5 3.89E8 3.49E6 8.44E5 Cs 134 1.60E10 2.63E10 5.55E9 8.15E9 2.93E9 1.42E8 Cs 137 2.39E10 2.29E10 3.38E9 7.46E9 2.68E9 1.43E8 Ba 140 2.77E8 2.43E5 1.62E7 7.90E4 1.45E5 1.40E8 La 140 3.25E3 1.13E3 3.83E2 3.16E7 Ce 141 6.56E5 3.27E5 4.85E4 1.43E5 4.08E8 Ce 144 1.27E8 3.98E7 6.78E6 2.21E7 1.04E10 Nd 147 7.23E4 5.86E4 4.54E3 3.22E4 9.28E7 AglOnm 3.21E7 2.17E7 1.73E7 - 4.04E7 2.58E9 3.

• nrem/yr per Ci/dm Unit 2 Revision 23 II 56 December 2002

TABLE D 3-21 DOSE AND DOSE RATE RI VALUES - VEGETATION - TEEN M2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3- 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3 C 14' 1.45E6 2.91E5 2.9lE5 2.91ES 2.91E5 2.91E5 2.91E5 Cr51 6.16E4 3.42E4 1.35E4 8.79E4 1.03E7 Mn 54 4.54E8 9.01E7 1.36E8 9.32E8 Fe 55 3.10E8 2.20E8 5.13E7- 1.40E8 9.53E7 Fe 59 1.79E8 4.18E8 1.61E8 1.32E8 9.89E8 Co 58 4.37E7 1.01E8 6.02E8 Co 60 2.49E8 5.60E8 3.24E9 Zn 65 4.24E8 1.47E9 6.86E8 9.41E8 6.23E8 Sr89 1.5lE10 4.33E8 1.80E9 Sr90 7.5lEll 1.85Ell 2.1lE10 Zr 95 1.72E6 5.44E5 3.74E5 7.99E5 1.26E9 Nb 95 4.80E5 2.66E5 1.46E5 2.58E5 1.14E9 Mo 99 5.64E6 1.08E6 1.29E7 1.01E7 1131 3.85E7 5.39E7 2.89E7 1.57E10 9.28E7 1.07E7 1133 9.29E5 1.58E6 4.80E5 2.20E8 2.76E6 1.19E6 Cs 134 7. 10E9 1.67E10 7.75E9 5.31E9 2.03E9 2.08E8 Cs 137 1.OlE10 1.35E10 4.69E9 4.59E9 1.78E9 1.92E8 Ba 140 1.38E8 1.69E5 8.91E6 5.74E4 1. 14E5 2.13E8 La 140 1.81E3 8.88E2 2.36E2 5.10E7 Ce 141 2.83E5 1.89E5 2.17E4 8.89E4 5.40E8 Ce 144 5.27E7 2.18E7 2.83E6 1.30E7 1.33E10 Nd 147 3.66E4 3.98E4 2.3863 2.34E4 1.44E8 Ag lOnm 1.5 1E7 1.43E7 8.72E6 2.74E7 4.03E9 3

• mremlyr per 11Ci/m Unit 2 Revision 23 II 57 December 2002

TABLE D 3-22 DOSE AND DOSE RATE RI VALUES - VEGETATION - ADULT

_ 2-mremlyr uCilsec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LI LI H 3- 2.26E3 2.26E3 2.26E3 2.26E3 2.26E3 2.26E:

C 14 8.97E5 1.79E5 1.79E5 1.79E5 1.79E5 1.79E5 1.79E. 5 Cr 51 - - 4.64E4 2.77E4 1.02E4 6.15E4 1.17E' 7 Mn54 - 3.13E8 5.97E7 - - 9.31E7 -- 9.58E 8 Fe 55 2.00E8 1.38E8 3.22E7 - -- 7.69E7 7.91E-7 Fe 59 1.26E8 2.96E8 1.13E8 -- -- 8.27E7 1.02E 9 Co58 -- 3.08E7 6.90E7 -- -- -- 6.24E Co 60 -- 1.67E8 3.69E8 -- -- -- 3.14E 9 Zn65 3.17E8 1.01E9 4.56E8 -- 6.75E8 -- 6.36E 8 Sr 89 9.96E9 -- 2.86E8 -- -- -- 1.60E 9 Sr 90 6.05E11 - 1.48Ell - -- -- 1.75E 10 Zr 95 1.18E6 3.77E5 2.55E5 - 5.92E5 -- 1.20E 9 Nb 95 3.55E5 1.98E5 1.06E5 - 1.95E5 -- 1.20E 9 Mo99 -- 6.14E6 1.17E6 -- 1.39E7 -- 1.42E 7 1131 4.04E7 5.78E7 3.3 1E7 1.90E10 9.91E7 - 1.53E 7 1133 1.00E6 1.74E6 5.30E5 2.56E8 3.03E6 - 1.56E 6 Cs 134 4.67E9 1.11E10 9.08E9 -- 3.59E9 1.19E9 1.94E 8 Cs 137 6.36E9 8.70E9 5.70E9 -- 2.95E9 9.81E8 1.68E 8 Ba 140 1.29E8 1.61ES 8.42E6 - 5.49E4 9.25E4 2.65E 8 La 140 1.98E3 9.97E2 2.63E2 - - -- 7.32E'7 Ce 141 1.97E5 1.33E5 1.51E4 - 6.19E4 -- 5.09EE8 Ce 144 3.29E7 1.38E7 1.77E6 - 8.16E6 -- 1.11E E10 Nd 147 3.36E4 3.88E4 2.32E3 -- 2.27E4 -- 1.86E E8 Ag ll0m 1.05E7 9.75E6 5.79E6 -- 1.92E7 - 3.98E E9

• mrem/yr per 1 Ci/m3 Unit 2 Revision 23 II 58 December 2002

TABLE D 3-23 DISPERSION PARAMETERS AT CONTROLLING LOCATIONS' X/Q,Wv and W. VALUES VENT DIRECTION DISTANCE (__) X/Q (sec/m3 )

Site Boundary 2 E 1,600 2.00 E-6 2.0OE-9 Inhalation and Ground E (104') 1,800 1.42E-7 2.90E-9 Plane Cow Milk ESE (130') 4,300 4.11E-8 4.73E-10 Goat Milk3 SE (140') 4,800 3.56E-08 5.32E-10 Meat Animal E (114°) 2,600 1.17E-7 1.86E-9 Vegetation E (96') 2,900 1.04E-7 1.50E-9 STACK Site Boundary 2 E 1,600 4.50E-8 6.OOE-9 Inhalation and Ground E (109') 1,700 8.48E-9 1.34E-9 Plane Cow Milk ESE (135') 4,200 1.05E-8 3.64E-10 Goat Milk' SE (140') 4,800 2.90E-08 5.71E-10 Meat Animal E (1 14°) 2,500 1. 13E-8 l.l15E-9 Vegetation E (96') 2,800 1.38E-8 9.42E-10 NOTE: Inhalation and Ground Plane are annual average values. Others are grazing season only.

I X/Q and D/Q values from NMP-2 ER-OLS.

2 X/Q and D/Q from NMP-2 FES, NUREG-1085, May 1985, Table D-2.

3 X/Q and DIQ from C.T. Main Data Report dated November 1985.

Unit 2 Revision 23 II 59 December 2002

I TABLE D 3-24 PARAMETERS FOR THE EVALUATION OF DOSES TO REAL MEMBERS OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS Pathway Parameter Value Reference Fish U (kg/yr) - adult 21 Reg. Guide 1.109 Table E-5 Fish Da,,, (mremlpCi) Each Radionuclide Reg. Guide 1.109 Table E-1 1 Shoreline U (hr/yr)

- adult 67 Reg. Guide 1.109

- teen 67 Assumed to be Same as Adult Shoreline Dapj Each Radionuclide Reg. Guide 1.109 (mremlhr per pCi/ma) Table E-6 Inhalation DFAija Each Radionuclide Reg. Guide 1.109 Table E-7 Unit 2 Revision 23 JI 60 December 2002

TABLE D 5.1 NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS M ap Collection Site Type of Sample Location (Env. Program No.) Location Radioiodine and I Nine Mile Point Road North 1.8 mi @ 88-E Particulates (air) (R-l)

Radioiodine and 2 County Route 29 & Lake Road 1.1 mu @ 104 ESE Paruculates (air) (R-2)

Radioiodune and 3 County Route 29 1.5 ml © 132 SE Particulates (air) (R-3)

Radioiodmne and 4 Village of Lycoming, NY 1.8 mi @ 143 SE Particulates (air) (R-4)

Radloiodme and 5 Montano Point Road 16.4 mi @ 42 NE Particulates (air) (R-5)

Direct Radiation (TLD) 6 North Shoreline Area 0.1 ml @ 5- N (75)

Direct Radiation (TLD) 7 North Shoreline Area 0 1 mi @ 25 NNE (76)

Direct Radiation (TLD) 8 North Shoreline Area - 0.2 ml @ 45- NE (77)

Direct Radiation (TLD) 9 North Shoreline Area 0.8 mi @ 70 ENE (23)

Direct Radiation (TLD) 10 JAF East Boundary 1.0 mi @ 90' E (78)

Direct Radiation (TLD) 11 Route 29 1.1 mi @ 115' SE (79)

Direct Radiation (TLD) 12 Route 29 1.4 mi @ 133- SE (80)

Direct Radiation (TLD) 13 Miner Road - 1.6 ml @ 159' SSE (81)

Direct Radiation (TLD) 14 Miner Road 1.6 mi @ 181' S (82)

Direct Radiation (TLD) 15 Lakeview Road 1.2 mi @ 200' SSW (83)

Direct Radiation (TLD) 16 Lakeview Road 1.1 mi @ 225- SW (84)

Direct Radiation (TLD) 17 Site Meteorological Tower 0.7 ml @ 250' WSW

'(7)

Direct Radiation (TLD) 18 Energy Information Center 0.4 mi @ 265' W

- (18)

Direct Radiation (TLD) 19 North Shoreline 0 2 mi @ 294- WNW (85)

• Map = See Figures D 5.1-1 and D 5 1-2.

Unit 2 Revision 23 II 61 December 2002

TABLE D 5.1 (Cont'd)

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

SAMPLING LOCATIONS

• Map Collection Site Type of Sample Location (Env. Program No.) Location Direct Radiation (TLD) 20 North Shoreline 0.1 mi @ 315' NW (86)

Direct Radiation (TLD) 21 North Shoreline 0.1 mi @ 341'NNW (87)

Direct Radiation (TLD) 22 Hickory Grove 4.5 mi @ 97 E (88)

Direct Radiation (TLD) 23 Leavitt Road 4 lmi@ 111'ESE (89)

Direct Radiation (TLD) 24 Route 104 4.2 mi © 135' SE (90)

Direct Radiation (TLD) 25 Route 51A 4 8 mi @ 156' SSE (91)

Direct Radiation (TLD) 26 Maiden Lane Road 4 4 mi @ 183'S (92)

Direct Radiation (TLD) 27 County Route 53 4.4 mi @ 205' SSW (93)

Direct Radiation (TLD) 28 County Route I 4.7 mi © 223' SW (94)

Direct Radiation (TLD) 29 Lake Shoreline 4.1 mi @ 237-WSW (95)

Direct Radiation (TLD) 30 Phoenix, NY Control 19.8 mi @ 163' S (49)

Direct Radiation (TLD) 31 S. W. Oswego, Control 12 6 mi @ 226- SW (14)

Direct Radiation (TLD) 32 - Scriba, NY 3.6 mi @ 199' SSW (96)

Direct Radiation (TLD) 33 Alcan Aluminum, Route IA 3.1 nru 220' SW (58)

Direct Radiation (TLD) 34 Lycoming, NY 1.8 mi 143'SE (97)

Direct Radiation (TLD) 35 New Haven, NY 5.3 mi @ 123' ESE (56)

Direct Radiation (TLD) 36 W. Boundary, Bible Camp 0.9 ml @ 237' WSW (15)

Direct Radiation (TLD) 37 Lake Road 1.2 mi 101'E (98)

• Map = See Figures D 5.1-1 and D 5.1-2.

Unit 2 Revision 23 II 62- December 2002

TABLE D 5.1 (Cont'd)

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS

• Map Collection Site Type or Sample Location (Env. Program No.) Location Surface Water 38 OSS Inlet Canal 7.6 ml 235'SW (NA)

Surface Water 39 JAFNPP Inlet Canal 0.5 mi @ 70 ENE (NA)

Shoreline Sediment 40 Sunset Bay Shoreline 1.5 mi @ 80' E (NA)

Fish 41 NMP Site Discharge Area 0.3 mii315'NW (NA)

(and/or)

Fish 42 NMP Site Discharge Area 0.6 ml @ 55' NE (NA)

Fish 43 Oswego Harbor Area 6.2 mi @ 235 SW (NA)

Milk 44 Milk Location #50 8.2 mi @ 93 E Milk 64 Milk Location #55 9.0 mi@ 95-E Milk 65 Milk Location #60 9 5 mli 90' E Milk 66 Milk Location #4 7.8 ms t13-ESE Milk (CR) 77 Milk Location 13.9 mi @ 191' SSW (Summerville)

Food Product 48 Produce Location #6** 1.9 ml 141'SE (Bergenstock) (NA)

Food Product 49 Produce Location #1** 1.7 ml @ 96-E (Culeton) (NA)

Food Product 50 Produce Location #2** 1.9 mln 101'E (Vitullo) (NA)

Food Product 51 Produce Location #5** 1.5 mi @ 114 ESE (C.S. Parkhurst) (NA)

Food Product 52 Produce Location #3** 1.6 mi@ 84- E (C. Narewskh) (NA)

• Map = See Figures D 5.1-1 and D 5.1-2

= Food Product Samples need not necessanly be collected from all listed locations Collected samples will be of the highest calculated site average D/Q.

(NA) = Not applicable.

CR = Control Result (location).

Unit 2 -

Revision 23 II 63 December 2002

TABLE D 5.1 (Cont'd)

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS

• Map Collection Site Type of Sample Location (Env. Program No.) Location Food Product 53 Produce Location #4** 2.1 mi @ 1100 ESE (P. Parkhurst) (NA)

Food Product (CR) 54 Produce Location #7** 15.0 mi @ 223° SW (Mc Millen) (NA)

Food Product (CR) 55 Produce Location #8** 12.6 mi @ 2250 SW (Denman) (NA)

Food Product 56 Produce Location ,#9** -1.6 mi O 171' S (O'Connor) (NA)

Food Product 57 Produce Location #10** 2.2 mi@ 123' ESE (C. Lawton) (NA)

Food Product 58 Produce Location #11** 2.0 mi @112' ESE (C. R. Parkhurst) (NA)

Food Product 59 Produce Location #12** 1.9 mni@ 1150 ESE (Barton) (NA)

Food Product (CR) 60 Produce Location#13** 15.6 nii C 225°W (Flack) (NA)

Food Product 61 Produce Location #14** 1.9 mi@95 0E (Koeneke) (NA)

Food Product 62 Produce Location #15** 1.7 mi@ 136' SE (Whaley) (NA)

Food Product 63 Produce Location #16** 1.2 mni @ 2070 SSW (Murray) (NA)

Food Product 67 Produce Location #17** 1.76 mi @ 970 E (Battles) (NA)

• Map = See Figures D 5.1-1 and D 5.1-2.

• • = Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.

(NA) Not applicable.

CR = Control Result (location).

Unit 2 Revision 23 II 64 December 2002

APPENDIX A LIQUID DOSE FACTOR DERIVATION Unit 2 Revision 23 II 65 December 2002

Appendix A Liquid Effluent Dose Factor Derivation, A,,,

A.a, (mrem/hr per uCi/ml) which embodies the dose conversion factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water and the sediment. The total body and organ dose conversion factors for each radionuclide will be used from Table E-1 1 of Regulatory Guide 1.109. To expedite time, the dose is calculated for a maximum individual instead of each age group. The maximum individual dose factor is a composite of the highest dose factor Aiat of each nuclide i age group a, and organ t, hence Aiat. It should be noted that the fish ingestion pathway is the most significant pathway for dose from liquid effluents. The water consumption pathway is included for consistency with NUREG 0133.

The equation for calculating dose contributions given in section 1.3 requires the use of the composite dose factor A,t for each nuclide, i. The dose factor equation for a fresh water site is:

U,, e-~ tPW69.3U UW e--P' ja1t AKO[(Uw KLO D, + B.

BPDF feU eUB 2 ,,D a+

D(l D, AL e )DFSl Where:

at = Is the dose factor for nuclide i, age group a, total body or organ t, for all appropriate pathways, (mrem/hr per uCi/ml)

K= Is the unit conversion factor, 1.14E5 = lE6pCi/uCi x 1E3 mi/liter 8760 hr/yr UW = Water consumption (liters/yr); from Table E-5 of Reg. Guide 1.109 Uf= Fish consumption (kg/yr); from Table E-5 of Reg. Guide 1.109 Us = Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg. Guide 1.109 BF 1 = Bioaccumulation factor for nuclide, i, in fish, (pCi/kg per pCi/liter),

from Table A-1 of Reg. Guide 1.109 DFLat = Dose conversion factor for age, nuclide, i, group a, total body or organ t, (mrem/pCi); from Table E-11 of Reg. Guide 1.109 DFS, = Dose conversion factor for nuclide i and total body, from standing on contaminated ground (mrem/hr per pCi/rn2); from Table E-6 of Reg.

Guide 1.109 Unit 2 Revision 23 II 66 December 2002

Appendix A (Cont'd)

Dw= Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption. This is the Metropolitan Water Board, Onondaga County intake structure located west of the City of Oswego.

(Unitless)

D= Dilution factor from the near field area within one quarter mile of the release point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles; unitless) 69.3 = conversion factor .693 x 100, 100 = KC (liters/kg-hr)*40 kg/m 2 *24 hr/day/.693 in liters/m 2 -d, and Kr = transfer coefficient from water to sediment in liters/kg per hour.

tpW tpy = Average transit time required for each nuclide to reach the point of exposure for internal dose, it is the total time elapsed from release of the nuclides to either ingestion for water (w) and fish (f) or shoreline deposit (s), (hr) tb = Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life),

(hrs).

=- decay constant for nuclide i (Iff')

W = Shore width factor (unitless) from Table A-2 of Reg. Guide 1.109 Example Calculation For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents release:

(DFS), = 2.80E-9 mrem/hr per pCi/mn (DFL)tat = 1.95E-3 mrem/pCi tp 40 hrs. (w = water)

BF, = 15 pCi/kg per pCi/liter t.f = 24 hrs. (f = fish)

Uf = 21 kg/yr tb = 1.314E5 hr (5.48E3 days)

Dw = 62 unitless UW = 730 liters/yr D, = 17.8 unitless K1( = 1.14E5 (pCi/uCi)(ml/kg)

Us = 12 hr/yr (hr/yr)

W = 0.3 X, = 3.61E-3hr '

= 7.3 hrs (s=Shoreline Sediment)

These values will yield an A., Factor of 6.65E4 mrem-ml per uCi-hr as listed in Table D 2-2. It should be noted that only a limited number of nuclides are listed on Tables D 2-2 to D 2-5. These are the most common nuclides encountered in effluents. If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.

In addition, not all dose factors are used for the dose calculations. A maximum individual is used, which is a composite of the maximum dose factor of each age group for each organ as reflected in the applicable chemistry procedures.

Unit 2 Revision 23 II 67 December 2002

APPENDIX B PLUME SHINE DOSE FACTOR DERIVATION Unit 2 Revision 23 II 68 December 2002

Appendix B For elevated releases the plume shine dose factors for gamma air (B,) and whole body (V,), are calculated using the finite plume model with an elevation above ground equal to the stack-height. To calculate the plume shine factor for gamma whole body doses, the gamma air dose factor is adjusted for the attenuation of tissue, and the ratio of mass absorption coefficients between tissue and air. The equations are as follows:

Gamma Air Bi = aE Is Where: K' - conversion factor (see S RE V5 below for actual value).

pa = mass absorption coefficient (cm 2/g; air for B, tissue for Vi)

E = Energy of gamma ray per disintegration (Mev)

Vs average wind speed for each stability class (s), r/s R = downwind distance (site boundary, m)

E = sector width (radians)

- s = subscript for stability class Is = I function = I, + k02 for each stability class. (unitless, see Regulatory Guide 1.109) le Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)

Whole Body

[Ilatd Vi = 1.llSFBie Where: td = tissue depth (g/cm2 )

SF = shielding factor from structures (unitless) 1.11 = Ratio of mass absorption coefficients between tissue and air.

Where all other parameters are defined above.

Unit 2 Revision 23 II 69 December 2002

Appendix B (Cont'd)

'K = conversion factor = 3.7 E10 dis 1.6 E-6 erg Ci-sec Mev = .46 1293 g 100 erg m3 g-rad pa Where: L = mass attenuation coefficient (cm2 /g; air for B^, tissue for V1) a = defined above There are seven stability classes, A thru F. The percentage of the year that each stability class is taken from the U-2 FSAR. From this data, a plume shine dose factor is calculated for each stability class and each nuclide, multiplied by its respective fraction and then summed.

The wind speeds corresponding to each stability class are, also, taken from the Unit 2 FSAR.

To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values. The average wind speed of the actual data is equal to 6.78 m/s, which compared favorably to the FSAR average wind speed equal to 6.77 m/s.

The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide. These energies were taken from the handbook "Radioactive Decay Data Tables", David C. Kocher.

The mass absorption (pa) and attenuation (I,) coefficients were calculated by multiplying the mass absorption (ps/p) and mass attenuation (p/p) coefficients given in the Radiation Health Handbook by the air density equal to 1.293 E-3 g/cc or the tissue density of 1 g/cc where applicable. The tissue depth is 5g/cm 2 for the whole body.

The downwind distance is the site boundary.

SAMPLE CALCULATION Ex. Kr-89 F STABILITY CLASS ONLY - Gamma Air

-DATA E = 2.22MeV k = .871 K = .46

= 2.943 E-3Mrn [la VF = 5.55 m/sec p 5.5064E-3m' P. = 1600m e = .39 1=9m vertical plume spread taken from "Introduction to Nuclear Engineering", John R. LaMarsh Unit 2 Revision 23 II 70 December 2002

Appendix B (Cont'd)

-I Function Uoz .11 I, .3 I2 .4 1 I + 0 2 = .3 + (.871) (.4) = .65 dis.

Bi = 0.46 Ci-sec) (Mev/ergs3 (2.943E-3m') (2.22Mev) (.65)

(zn2 I(g/m3) (ergs) (5.55 m/s) (.39) (1600m)

(g-rad)

= 3.18(-7) rad/s (3600 s/hr) (24 h/d) (365 d/y) (lE3mrad/rad)

Ci/s (lE6uCi)

Ci

= 1.00(-2) mrad/yr u c 3.7se-c 2

- (.0253 cm 2 /g) (5g/cm )

Vi 1.11 (.7) (1E-2) mrad/yr [e I I pCi/sec]

= 6.85(-3) mradlyr pCi/sec Note: The above calculation is for the F stability class only. For Table D 3-2 and procedure values, a weighted fraction of each stability class was used to determine.

the B. and V, values.

Unit 2 Revision 23 II 71 December 2002

APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM Unit 2 Revision 23 II 72 December 2002

Appendix C DOSE PARAMETERS FOR IODINE - 131 AND - 133, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the organ dose factors for I-131, I-133, particulates, and tritium. The dose factor, R,, was calculated using the methodology outlined in NUREG-0133. The radioiodine and particulate DLCO 3.2.1 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor. Washout was calculated and determined to be negligible. Ri values have been calculated for the adult, teen, child and infant age groups for all pathways. However, for dose compliance calculations, a maximum individual is assumed that is a composite of highest dose factor of each age group for each organ and pathway. The methodology used to calculate these values follows:

C. 1 Inhalation Pathway R1(I)

M K'(BR)a(DFA)jja where:

R,(I) - dose factor for each identified radionuclide i of the organ of interest (units = mrem/yr per uCi/m3 );

K' = a constant of unit conversion, 1E6 pCi/pCi (BR)a = Breathing rate of the receptor of age group a, (units = m3/yr);

(DFA),a = The inhalation dose factor for nuclide i, organ j and age group a, and organ t (units = mrem/pCi).

The breathing rates (BR)a for the various age groups, as given in Table E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.

Age Group (a) Breathing Rate (m3/yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA),,a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.

Unit 2 Revision 23 II 73 December 2002

Appendix C (Cont'd)

C.2 Ground Plane Pathway

-Ait R,(G) = K'K(SF) (DFG)j (l-e )

Where:

R,(G) = Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units = m2 -mrem/yr per uCi/sec)

K' = A constant of unit conversion, 1E6 pCi/uCi K"= A constant of unit conversion, 8760 hr/year

= The radiological decay constant for radionuclide i, (units = sec-')

t = The exposure time, sec, 4.73E8 sec (15 years)

(DFG), = The ground plane dose conversion factor for radionuclide i; (units mremlhr per pCi/m 2 )

SF = The shielding factor (dimensionless)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision

1. A tabulation of DFG, values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1.

Unit 2 Revision 23 II 74 December 2002

Appendix C (Cont'd)

C.3 Grass-(Cow or Goat)-Milk Pathway

-Xith -Xitf R,(C) = K'Q(Ua.) Fm(r) (DFL)iat lf~f5 + (1-fPf 5 A (e e (1i + AQ) YP Y, Where:

R,(C) = Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, (units = m2-mremlyr per uCi/sec)

K' = A constant of unit conversion, 1E6 pCi/PCi QF= The cow's or goat's feed consumption rate, (units = kg/day-wet weight)

Uap = The receptor's milk consumption rate for age group a, (units = liters/yr)

Yp The agricultural productivity by unit area of pasture feed grass, (units = kg/m2)

Ys= The agricultural productivity by unit area of stored feed, (units = kg/m2)

F= The stable element transfer coefficients, (units = pCi/liter per pCi/day) r = Fraction of deposited activity retained on cow's feed grass (DFL)It = The ingestion dose factor for nuclide i, age group a, and total body or organ t (units = mrem/pCi) i = The radiological decay constant for radionuclide i, (units=sec -1)

,W- The decay constant for removal of activity on leaf and plant surfaces by weathering equal to 5.73E-7 sec -1 (corresponding to a 14 day half-life) tf The transport time from pasture to cow or goat, to milk, to receptor, (units = sec) th The transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units = sec) p = Fraction of the year that the cow or goat is on pasture (dimensionless)

= Fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless)

Unit 2 Revision 23 II 75 December 2002

Appendix C (Cont'd)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of f, is considered unity in lieu of site specific information. The value of fp is 0.5 based on 6 month grazing period. This value for fp was obtained from the environmental group.

Table C-1 contains the appropriate values and their source in Regulatory Guide -1.109 Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RT(C) is based on X/Q:

RT(C) = K'K"' FmQfUap(DFL).at 0.75(0.5/H)

Where:

RT(C) = Dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units = mrem/yr per gCi/m3 )

K"' = A constant of unit conversion, 1E3 g/kg H = Absolute humidity of the atmosphere, (units = g/m3 )

0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water Other values are given previously. A site specific value of H equal to 6.14 g/m 3 is used.

This value was obtained from the environmental group using actual site data.

Unit 2 Revision 23 II 76 December 2002

Appendix C (Cont'd)

C.4 Grass-Cow-Meat Pathway 1 (C) = KQfUaPFf (r)DFL,at f +f(1 - fpg)e-&' ] A, R,(M) = Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units = m2 -mrem/yr per gCi/sec)

Ff = The stable element transfer coefficients, (units = pCi/kg per pCi/day)

Uap = The receptor's meat consumption rate for age group a, (units = kg/year) th = The transport time from harvest, to cow, to receptor, (units = sec) tf = The transport time from pasture, to cow, to receptor, (units = see)

All other terms remain the same as defined for the milk pathway. Table C-2 contains the values which were used in calculating R,(M).

The concentration of tritium in meat is based on airborne concentration rather than deposition.

Therefore, the RT(M) is based on X/Q.

RT(M) = K'K" 'FfQfUap(DFL),at [0.75(0.5/H)]

Where:

RT(M) = Dose factor for the meat ingestion pathway for tritium for any organ of interest, (units = mrem/yr per tCi/m3 )

All other terms are defined above.

C.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed for milk. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

-XltL -Xith R1 (V) = K' r (DFL) iat ULaFLe + USaFge Y"(.1 + X..) I Unit 2 Revision 23 II 77 December 2002

Appendix C (Cont'd)

Where:

R,(V) = Dose factor for vegetable pathway for radionuclide i for the organ of interest, (units = m2 -mrem/yr per tCi/sec)

K' = A constant of unit conversion, 1E6 pCi/LCi ULa = The consumption rate of fresh leafy vegetation by the receptor in age group a, (units = kg/yr)

Usa = The consumption rate of stored vegetation by the receptor in age group a (units = kg/yr)

FL = The fraction of the annual intake of fresh leafy vegetation grown locally Fg = The fraction of the annual intake of stored vegetation grown locally tL = The average time between harvest of leafy vegetation and its consumption, (units = sec) ti = The average time between harvest of stored vegetation and its consumption, (units = sec)

Y= The vegetation areal P density, (units = kg/m2 )

All other factors have been defined previously.

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.

In lieu of site-specific data, values for FL and Fg of, 1.0 and 0.76, respectively, were used in the calculation. These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the RT(V) is based on X/Q:

RT(V) = K'K' t [ULa fL + U'a fg](DFL)at 0.75(0.5/H)

Where:

RT(V) dose factor for the vegetable pathway for tritium for any organ of interest, (units = mrem/yr per ,Ci/m 3 ).

All other terms are defined in preceeding sections.

Unit 2 Revision 23 II 78 December 2002

TABLE C-1 Parameters for Grass - (Cow or Goat) - Milk Pathways Reference Parameter Value (Reg. Guide 1.109 Rev. 1)

Qf (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL)j,,a (mrem/pCi) Each radionuclide Tables E-1 1 to E-14 Fm (pCi/liter per pCi/day) Each stable element Table E-1 (cow)

Table E-2 (goat)

Y, (kg/rtn) 2.0 Table E-15 Yp (kg/mr) 0.7 Table E-15 th (seconds) 7.78 x 106 (90 days) Table E-15 t, (seconds) 1.73 x 105 (2 days) Table E-15 Uap (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 Unit 2 Revision 23 II 79 December 2002

TABLE C-2 Parameters for the Grass-Cow-Meat Pathway Reference Parameter Value (Reg. Guide 1.109 Rev. 1) r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/kg per pCi/day) Each stable element Table E-1 Uap (kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL)ia (mrem/pCi) Each radionuclide Tables E-Il to E-14 Yp (kg/rn) 0.7 Table E-15 Y, (kg/rnm) 2.0 Table E-15 th (seconds) 7.78E6 (90 days) Table E-15 tf (seconds) 1.73E6 (20 days) Table E-15 Qf (kg/day) 50 Table E-3 Unit 2 Revision 23 II 80 December 2002

TABLE C-3 Parameters for the Vegetable Pathway Reference Parameter Value (Reg. Guide 1.109 Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL),ja (mrem/pCi) Each radionuclide Tables E-1I to E-14 UL)a (kglyr) - infant 0 Table E-5

- child 26 Table E-5

- teen 42 Table E-5

- adult 64 Table E-5 U%)a (kg/yr) - infant 0 Table E-5

- child 520 Table E-5

- teen 630 Table E-5

- adult 520 Table E-5 tL (seconds) 8.6E4 (1 day) Table E-15 tb (seconds) 5.18E6 (60 days) Table E-15 Yv (kg/m2 ) 2.0 Table E-15 Unit 2 Revision 23 II 81 December 2002

APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMS AND MONITORING SYSTEMS Unit 2 Revision 23 II 82 December 2002

Liquid Radwaste Treatment System Diagrams Unit 2 Revision 23 II 83 December 2002

I TYPICAL OF 3

.1,_ _ _ _ _ _ _, _ _ _ _ _ _ __ _ _ _ _ _ _

SPENT FUEL POOL COOLING THERME_ AOV I AOV 84 .

SYSTEM I RADWASTE _ lb DEHINERALIZER REACTOR WATER AOV 47 CLEANUP SYSTEM AV1.

RECENERANT _

EVAPORATOR t CONDENSATE DEMINERALIZERS REACTOR BUILDING EQUIPMENT DRAINS P AO PHASE SEPARATOR I WASTE COL ECTOR PUMP RECOVERY _ k lit SAMPLE TANKS ---------------------- r------

TURBINE BLDG EQUIPMENT DRAINS ASTE COLLECTOR .

RESIDUAL HEAT AOV AOV277 REMOVAL SYSTEM 278 RECOVERY A iSAHPLE SYSTEM VAST[ COLCTOR U PUWS RADWASTE _

FILTERS FLOOR DRAIN A0V307 FILTERS WASTE COLLECTION If 84

AIRISPN IPCV 266 AOVL ~ AOV 26 REI AIR6 TYPICAL OF 2 TO/FRMt AOT18W0V90 FLOOR bRAIN ODN ACV 166 COLLECTOR TK~S TO OTtfR WAST DIC7tDEHIIN AOV26 A~11 AOV 164 A SAM~E TKS I AOV 167 WASTE COLL SURGE TAW~

WASTE COtLLCO COLL PUMSVA264 H4 DDE WASTE WASELLECTOR 0 SAOiP6E TEMf PiDEAO TYPICSTEOFISCH CONDENSTE pO OTI(RC D(III T1 WASTE COLLECTOR TEtIN AOVOTHER TREATMENT SYSTEM II 85

TYPICAL OF 2 THERMEX10_ TYPICAL OF 2 SYSTEM I-II RADWASTE l_

NHP- I DEHINERALIZER RADWASTE _

FILTERS

_. r OTWR PS I- .T TA I C1C LLN FXRC I

I I

I r Il I

I. l I S 710H LINEI..

I OTHER SUXTON LINEl II CSTs I )() .

I I

I I I

. ,b I I[

RECOWR 1, ~~CULL

[

A0V314 TANK AO I _ A L---

NHP-I WTASTE R 26 A 27 L

REGEN EVAP SERVICE DISCHARGEAOV279 WATER DISCHARGE BAY A RANGE FLOOR DRAIN COLLECTOR TANKS RANGE RECOVERY SAMPLE SYSTEM and WASTE DISCHARGE SAMPLE SYSTEM I 86*

I

I I

I A-:

FLOOR DRAIN COLLECTION SYSTEM I. I 11 87 .

I I

WASTE COLLECTOR SURGE TANK , INSTRUMENT FLOOR DRAIN AIR COLLECTOR 4 COND. MAKEUP SURGE TANK AND DRAW OFF FLOOR DRAIN COLLECTOR TANKS REGEN. WASTE TANKS I

I' SLUDGE TANK WASTE COLLECTOR TANKS I AOV214 L REGEN.. WASTE TANK AOV127 I 3 WASTE DISCH.

SAMPLE TANK AOV123 3 FLOOR DRAIN COLLECTOR-TANK AOV126 WASTE COLLECTOFIR.

TANK I

FLOOR DRAIN FILTER SYSTEM II 88

I RW FLOOR AND EQUIPMENT DRAINS RW FILTER BACK WASH PUMPS REGENERANT TANK Ho REGCN EVAP I iA 9 AOV68 RECE RATE WASTEE I TANK PUIHP P3A/AOV92

-b-THERMEX SYSTEM A93 'I I- - --- - - - - - - - - - - - - - - - - - - - - - - - - -

t REGENERANT WASTE SYSTEM II 89

CO DENSA TE lA STE TRANSFER WASTE

_0 EVAP SM79 AND STORACE 18 COLL. TANKS 0PTTOUS FLOOR DRAIN 2 UCOLL.

TANKS WASTE DISCH A0V 47 SAMPLE TANKS REGENERANT EVAPORATOR SYSTEM 1 90

Gaseous Treatment System Diagrams Unit 2 Revision 23 II 91 December 2002

soV i 1 1 SYSTEM

Title:

CONDENSER 'AIR REMOVAL SYSTEM 192

ro OnmFnS Titla:

OFFGAS RECOMBINERS 11 93

lo CHAACOAL

• asso"Ins

-- I -- '-

USCLCW' II

-- J

ALL LINES AND EQUIPMENT jLOCATED INSIDE THIS BOUNDARY;

TO BE ABANDONED IN PLACE  ;

I 1194

fR -U OfFOAS DFIYCNS 03 OOV$2V T I To Main Stock Titte:

Title:

OFFGAS SYSTEM I II 95 CHARCOAL ABSORBERS I i

9I

OUtSECAn Title STANDBY GAS ,

TREATMENT SYSTEM i 11 96 _

Liquid Radiation Monitoring Diagrams Unit 2 Revision 23 11 97 December 2002

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CA CATI Sfe Silica CAC StIg -lI~t',EU I A iT I e I~ I.

L10130D RADIATION MONITORING SHEET 2 OF 2 NIAGARA MOHAWK POWER CORPORATION MILE POINT-UNIT NINESAFETY 2 FINAL ANALYSLS REPORT I198

02 GLOSE VALVE. ALL OTHER MANUALLY OPERATED VALVES ARE BALL VALVES CALIBRATIDN/DRAIN CONNECTION 2CCP-CA8115 2CCS-CA8152 LEGEND 2CWS-CAB157 PRESSURE INDICATOR O FLOW INDICATING SW.

E SOLENOID OPERATED SW.

NORMALLY CLOSED VALVE X NORMALLY OPEN VALVE OFF-LINE LIQUID MONITOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPODTED SAFETY AN1ALYSIS REPORT Efz~ R7VTRTn 3 OCTOBER 1991_

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OFF-LINE LIQUID MONITOR NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY A11ALYSIS REPORT

________________________________________________________________________ a USAR REVISION 0 APRIL I 989

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r -Mi NOTES ODCLOBE VALVE.ALL OTHER HANUALLY OPERATED VALVES CALIBRATION TEST/ ARE BALL VALVES VENT CONNECTION CALIBRATION/DRAIN CONNECTION OFFLINE LIOUJOD MONITOR 2SWPwCAa23o 2SWP*CAS238 LEGEND 2SWP.CAER46A 2SWPOCABI468 O PRESSURE INOICATOR O FLOW SW.

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Gaseous Effluent Monitoring System Diagrams Unit 2 Revision 23 II 102 December 2002

a I I I I I c I

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I LINER FILLINO NEPA FILTER A

TEMEACTOR EX"AUSI VENT RADVASTE BUILDINC 1916S CFU tCON EPA FILTERVICE BLOC MAIN, STACK AREA ARE EIOfLN CENlERAL AREA RADW4STE A910 CFU EXH. ENERA EXH.ISOTROPIC T

T 3 CfU 00 EFFLUENRT OAIon DEo RADWASTEBUILDING 25635 CFU CEN. ARESAVENIILATION lA 2-96R _23000 CPU AuXUa01LE R RU.

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• SAFETY-RELATED UONITOR HONITORINC NOTES. NIAGARA MOHAWK pOWER CORPORATIOIt I. MODIFICATION 9S-01 I HAS BEEN INSTALLED TO ALLOWCONJCURRENT

• OPERAtION OF ALL 3 EXHAUST FANS. WHEN ALL 3 FANS ARE RUNNING NINE UILE POINT-UNIT 2 THERE WILL BE AN ADDITIONAL EXHAUST OF i7.SOO CFU. lUPOATIO SAFETY ANALTSIS PIPORl I III I I I USAR RETISIONIB0 N YE.BER19i '4

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/ CHECHE ICHECK FLOWSENSORS NOT /AMPLIFIER SOURCE VALVES, ETC.

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. .. -*11VIDEO TERMINAL PROGRAMMADLE MULTICHANNEL FCONTROLLER ANALYZER _COMPUTER PRINTER HOSTCOMPUTER DUAL DISK DRIVE BLOCK DIAGRAM

.TYPICALGASEOUS EFFLUENT MONITORING SYSTEM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 11104 UPDATED SAFETY ANALYSIS REPORT

APPENDIX E NINE MILE POINT ON-SITE AND OFF-SITE MAPS Unit 2 Revision 23 II 105 December 2002

TT 1n6s SCALE or MILES I

FIGURE D 5.1-2

• I

" MM I s 2 LEGEND Intet. . ...............

U.S. A state Highway ..

NINE MILE POINT County Roads.........................

Town Road..

CountyLn Town LUnp..........

OFF-SITE MAP CIty A Village Unt ...........

Raloods............. ,.,..

ENVIRONMENTAL SAMPLE ... /\

LOCATION (10/2001)

Latitude 432rN.

Lingttude SOW.

at Ocorou Cunly 11IditOswaol INY.

Lend Arm 968Square nat Rtsiboe I It L A KE ON T A R IO

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