ML031250549

Radioactive Effluent Release Report for January 1 - December 31, 2002, Part II Through Appendix G

ML031250549
Person / Time
Site:	Comanche Peak
Issue date:	04/24/2003
From:	Bradley S, Curtis J, Floyd E TXU Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2009-0260
Download: ML031250549 (106)

Text

I PART II CALCULATIONAL METHODOLOGIES COMANCHE PEAK - UNITS 1 AND 2 01/93

SECTION 1.0 LIQUID EFFLUENTS The Comanche Peak Steam Electric Station (CPSES) is a 2-unit nuclear generating 8 facility. Each unit is a 1150 MWe, 4-loop, Westinghouse PWR. The units share a common primary liquid radwaste processing system. CPSES is located on Squaw 74 Creek Reservoir (SCR). which serves as the point of supply and discharge for the plant circulating water. Radioactive liquid effluent releases from the primary radwaste processing system are batch type releases, from the Plant Effluent Tanks (PET). Laundry Holdup & Monitor Tanks (LHMT) and Waste Monitor Tanks (WMT),

discharged to SCR via the Circulating Water Discharge Tunnel. Potentially 7 radioactive liquid effluent releases from secondary systems include a continuous release from the Turbine Building Sumps (TB Sump), the Unit 1 and Unit 2 9 Component Cooling Water Drain Tanks (CCWDT). Auxiliary Building Sumps 3 and 11, the Unit 1 and Unit 2 Diesel Generator Sumps 1 and 2, and batch releases from the 14 Condensate Polisher Backwash Recovery Tanks (CPBWRT) and temporary hold up tanks.

These secondary pathways from each unit are normally discharged to the common Low 8 Volume Waste (LVW) Pond for chemical treatment. The LVW Pond normally discharges to SCR via the circulating Water Discharge Tunnel. Alternatively, secondary 14 waste streams may be routed to the common Waste Water Holdup Tanks (WWHT) or other parts of the Waste Water Management System. The WWHTs may be released on a batch basis to the LVW Pond or to SCR via the Circulating Water Discharge Tunnel, 7 depending on the levels of radioactivity present. Table 4.11-1 of Part I of this 12 document requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B. Table 2. Column 2. Also, releases 8 from the Station Service Water (SSW) System are monitored for radioactivity, although no significant releases of radioactivity are expected from this pathway.

Sampling and analysis requirements for all release sources are given in Part I.

Table 4.11-1. All batch release sources are isolated and thoroughly mixed by mechanical mixing or recirculating the tank contents, prior to sampling, to assure representative sampling. The recirculation or mixing times necessary to assure representative sampling shall be specified in station procedures.

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-1 Rev. 14 10/96

A summary of all liquid effluent release sources, volumes, flow rates, and 7 associated radiation monitors is shown in Table 1.1. A flow diagram of all liquid effluent discharge pathways is shown in Figure 1.1.

The liquid effluent radiation monitors shown in Figure 1.1 are part of the plant Digital Radiation Monitoring System (DRMS) supplied by Sorrento Electronics (formerly General Atomics). Since the DRMS monitors provide a digital output.

they may be calibrated to read out in the appropriate engineering units (i.e.,

uCi/ml). The conversion factor for detector output from counts per minute to uCi/ml is determined in the calibration process and input into the database for the monitor microprocessor.

1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL 3/4.11.1.1 COMPLIANCE 8 To demonstrate compliance with 10 CFR 20.1301. ODCM Radiological Effluent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B. 12 Table 2. Column 2. for radionuclides other than dissolved or entrained 7 noble gases, and to 2E-4 uCi/ml for dissolved or entrained noble gases.

10 CFR 20 compliance is checked for all discharges to SCR via the Circulating Water Discharge Tunnel listed in Table 1.1. Because the LVW 8 Pond is located in a CONTROLLED AREA, discharges to the LVW Pond are also checked for 10 CFR 20 compliance. If radioactive materials are present in the LVW Pond discharge in concentrations that exceed 10% of the limits of 10 CFR 20, Appendix B. Table 2. Column 2. then all inputs to the LVW 8 Pond are sampled and checked for compliance with 10 CFR 20. The following 7 methodology is used to determine compliance with these limits.

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-2 Rev. 12 12/95

1.1.1 Isotopic Concentration of the Waste Tank Determine the isotopic concentration in waste stream to be released:

Z Ci = Z Cg + (Ca + Cs + Ct + CFe)

I g [Eq 1-1]

Where: ZCi = Sum of the concentrations of each radionuclide, in the i release (uCi/ml)

ZCg = Sum of the concentrations of each measured g gammanaemitter, g, (uCi/ml) as required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

Ca = Concentration of alpha emitters as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-

1. (Sample analyzed for gross alpha only) 7 Cs = Concentration of 89 Sr and 90 Sr as measured in the 7 most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

Ct = Concentration of 3H as measured in the most recent 7 composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

CFe= Concentration of 55Fe as measured in the most recent 7 composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

1.1.2 Effluent Flow Rate (f)

The maximum effluent discharge flow rates for each release 7 source are shown in Table 1.1. For pre-release calculations, 8 the maximum effluent flow rate is normally used. For post-release calculations, the average effluent flow rate during the release may be used. When the maximum effluent flow rate 18 is used for pre-release calculations, no setpoint is required for the flow measuring device for the effluent release line.

If a lower effluent flow rate is used in pre-release calculations, a flow measuring device setpoint shall be established to ensure that the ratio of the Required Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-3 01/93

Dilution Factor (RDF) to the Actual Dilution Factor (ADF) is maintained 8 less than or equal to 1.0. as discussed in Section 1.1.6. ADF and RDF are defined in Section 1.1.4 and 1.1.5. respectively.

1.1.3 Dilution of LiQuid Effluents

a. Discharges to SCR via Circulating Water Discharge Tunnel 7 Since liquid effluents from the radwaste treatment system, Waste Water 7 Holdup Tanks and the LYW Pond are mixed with Circulating water prior to being discharged to S.quaw Creek Reservoir. compliance with 10 CFR 20 is a function of the Circulating water flow rate. The maximum Circulating water flow rate per plant is 1.1 million gpm. This is determined from the Ingersoll-Rand pump curves (Fig. 1.2) which indicate a flow rate per pump of 275,000 gpm. The actual Circulating water dilution flow is given by:

F(diluting flow) = (275,000 gpm/pump) x (# of pumps) x 0.9

[Eq. 1-2]

Where: 0.9 = Safety Factor to compensate for flow fluctuations from the rate predicted by the Circulating water pump curves (Fig. 1.2).

As an additional consideration, the available dilution flow for any release may be corrected to allow for simultaneous releases from the Radwaste Processing System, a Waste Water Holdup Tank, and/or the LVW Pond (i.e.. a radwaste system tank. a Waste Water Holdup Tank, and the LVW Pond may be discharged simultaneously). For simultaneous releases.

the available dilution flow for any release is reduced by the required dilution flow for any other concurrent releases. Also, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isotopes. It is therefore necessary to account for recirculation of previously discharged radionuclides. This is accomplished as follows:

F' = F (1 - zi (C'1/10ECL1)) [Eq. 1-31 12 COMANCHE PEAK - UNITS 1 AND 2 . PART II 1-4 Rev. 12 12/95

Where: F' = Adjusted Circulating Water Flow Rate 7 C', = Maximum concentration of radionuclide i in Squaw 12 Creek Reservoir (uCi/ml) as measured in the analysis of the monthly samples of the reservoir required by Radiological Effluent Control 3/4.12.1.

Table 3.12.1. Sample locations are listed and maintained current in the results of the annual Land Use Census.

ECLi = Effluent Concentration Limit of radionuclide i. from 8 10CFR20. Appendix B. Table 2. Column 2 F = (275,000 gpm/pump) x (# or pumps) x 0.9 7 NOTE: If C'; is less than LLD then F' = F and no adjusted flow rate need be considered in the calculation of ADF. The LLD values used for this determination shall be the LLD values for water given in Radiological Effluent Control 3/4.12.1. Table 4.12-1.

b. Discharges to the LVW Pond Secondary release sources are discharged directly to the LVW Pond with no dilution (i.e., F=O).

1.1.4 Actual Dilution Factor (ADF)

ADF is the ratio of the effluent flow rate plus the Circulating water flow rate divided by the effluent flow rate.

ADF = (f + F)/f [Eq. 1-4]

Where: f = Effluent flow rate (gpm)

F = Dilution flow rate (gpm)

NOTE: If radioactivity is detected in the Reservoir, an adjusted Circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See Section 1.1.3 for the calculation of F' (Eq. 1-3). Also, if 1 simultaneous releases are occurring, the available dilution flow shall be reduced by the required dilution flow for any other concurrent release.

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-5 Rev. 12 12/95

1.1.5 Required Dilution Factor (RDF)

The required dilution factor ensures that'the limits of Control 12 3/4.11.1.1 (i.e., 10 times the effluent concentrations expressed in 10CFR20. Appendix B. Table 2. Column 2. and a total concentration of dissolved or entrained noble gases of 2 x 10 -4 uCi/ml) are not exceeded during a discharge. The required dilution factor includes a safety factor of 2 to provide a margin of assurance that the instantaneous concentration limits are not exceeded.

RDF = ( i (Cj/1OECLj)) x SF 12

= (E g (Cg/1OECLg) + (Ca/10ECLa + Cs/10ECLs +

Ct/10ECLt + CFe/10ECLFe)) x SF [Eq. 1-5]

Where: ECL 1 = Effluent Concentration Limit of radionuclide i. from 8 10CFR20. Appendix B. Table 2. Column 2 SF = Safety Factor of 2. 7 All other variables and subscripts are previously defined.

NOTE: If RDF is less than 1. the release meets discharge limits 7 without dilution. For conservatism, set RDF equal to 1.0.

The maximum value for the high alarm setpoint for detector XRE-5253 would then be calculated in accordance with the equation for Ca1 in Section 1.2.1.

1.1.6 10 CFR 20 Compliance Compliance with 10 CFR 20 is demonstrated if the Actual Dilution Factor 7 (ADF) is greater than or equal to the Required Dilution Factor (RDF),

or:

BEE ' 1.0 [Eq. 1-6] 7 ADF COMANCHE PEAK - UNITS 1 AND 2 PART II 1-6 Rev. 12 12/95

1.2 RADIATION MONITOR ALARM SETPOINTS 17 1.2.1 Primary Liquid Effluent Monitor XRE-5253 17 To ensure that releases from the primary radwaste processing system do 12 not exceed 10 times the 10 CFR 20. Appendix B, Table 2. Column 2 limits at the point of release to the CONTROLLED AREA or UNRESTRICTED AREA. a radiation detector (XRE-5253) monitors discharges to the Circulating Water Discharge Tunnel. XRV-5253 is the discharge isolation valve 7 controlled by XRE-5253. The isolation valve shuts automatically if the detector alarms on high radiation or a detector operation failure occurs. It should be noted that the liquid effluent monitor setpoint 10 values determined using the methodology from this section will be regarded as upper bounds for the actual setpoint adjustments. That is, 7 setpoints may be established at values lower than the calculated values, if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.

Since the radiation monitor XRE-5253 is a gamma sensitive device, the 10 monitor setpoint value shall be set based on the gamma radionuclides present in the waste stream. Therefore, a Required Dilution Factor gamma (RDFg) must be determined before the setpoint can be calculated.

RDFg = E: (Cg/1OECL9) X SF [Eq. 1-6a] 12 Where: RDFg = The required dilution factor (gamma) corresponding to the gamma concentration in the undiluted waste stream ensuring that 10 times the effluent concentration limits in 10CFR20, Appendix B. Table 2, Column 2 are not exceeded at the point of release during a discharge. If RDFg is less than 1. set RDFg equal to 1.0.

SF = A required safety factor of 2 is used to account for 10 the presence of Tritium, composited Alpha emitters, Fe-55, Sr-89 and Sr-90 values which are undetectable by this monitor and are at or near equilibrium and/or not expected to change rapidly under most plant conditions and statistical errors of measurement.

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-7 Rev. 12 12/95

The monitor XRE-5253 setpoint is determined using the following 10 calculation:

Ci, = (ADF/RDFg) X Eg Cg [Eq. 1-7]

Where: C, = The liquid waste effluent monitor alarm setpoint. This 12 corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in a release at the limits of Control 3.11.1.1.

All other variables are as previously defined. 7 When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be those referenced in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. Table Notation 2. Figure 1.3 is a representative energy spectrum response for the RD-33 type detector used in XRE-5253. This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant. In fact between 13 7Cs and 60Co. the total change in sensitivity is approximately 7%. Because this is well within the accuracy of measurement. there is no need to change the software sensitivity for given varied effluent concentrations. However, should the concentration of previously unexpected nuclides become significant.

further evaluation would be required.

1.2.2 Turbine Buildina Sump Effluent Radiation Monitor IRE-5100 and 2RE-5100 8 The purpose of the turbine building sump monitor (1RE-5100 and 2RE-5100) is to monitor turbine building sump discharges and divert this discharge from the Low Volume Waste Pond to the Waste Water Holdup Tanks if radioactivity is detected. Because the only sources of water 7 to the turbine building sump are from the secondary steam system.

activity is expected only if a significant primary-to-secondary leak is present. Since detectable radioactivity is not normally present in the 8 Turbine Building Sumps. the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm, should an inadvertent COMANCHE PEAK - UNITS 1 AND 2 PART II 1-8 Rev. 12 12/95

radioactive release occur. To this end, the setpoint will be 8 initially established at three (3)times background until further data can 7 be collected. Then, if this setpoint is exceeded, the monitor will direct 8 control valves to divert the turbine building sumps discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir, if required by 7 Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. When radioactive 12 materials are detected in the Turbine Building Sumps, a setpoint then may be established for 1RE-5100 or 2RE-5100 using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond' 1.2.3 Station Service Water (SSW) Effluent Radiation Monitors 1RE-4269/4270 and 15 2RE-4269/4270 The concentration of byproduct radioactive materials released from plant operations to the station service water (SSW) effluent lines normally is expected to be insignificant. However, because the SSW effluent has no additional dilution prior to its release into Squaw Creek Reservoir. it is important that this stream's process radiation monitors be optimized to detect any potential radioactive release of CPSES radioactive materials which could leak via this pathway. Complicating this surveillance task, operational experience has shown that the SSW radiation monitors periodically detect natural radionuclides in the SSW effluent. These natural radionuclides originate from washout of radon daughter products on plant surfaces following rainfall events. The detection of natural radionuclides in the SSW effluent is consistent with the normal expected function and operable status of the SSW radiation monitors. However, if a SSW radiation monitor setpoint is exceeded and an alarm is initiated (especially during or immediately after rainfall), then it is necessary to verify if the detected radioactivity is from natural radionuclides or from plant contamination by established assessment techniques. Natural radionuclides may be verified when a SSW alert setpoint only is exceeded by sampling or by comparison to the Component Cooling Water (CCW) process radiation monitors since the source of CPSES byproduct radionuclides in the SSW would be from the CCW.

Plant procedures and operating practices provide verification of detector alert or alarm conditions. The SSW effluent radiation monitors should have alert setpoints established as close to background as practical to prevent COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9 Rev. 15 03/99

spurious alarms and yet alarm should an inadvertent release of plant 15 byproduct radioactive materials occur. To this end, the monitor's alert setpoint is normally established at three (3)times background. Alert setpoint alarms should be verified in accordance with plant procedures.

Those alert setpoint alarms attributable to natural radionuclides should not be considered to be a plant adverse condition (i.e.. release of plant contamination) and should not result in the monitor being declared inoperable.

The SSW effluent radiation monitor's alarm setpoint is set at a higher level threshold. based on 'operating experience, to prevent alarm by most natural radionuclide washout events. Events that result in a SSW effluent radiation monitor alarm setpoint alarm should be considered a plant adverse condition and be investigated in accordance with plant procedures and applicable Controls of Part I of the ODCM. If the SSW effluent stream becomes contaminated with plant byproduct radioactive materials.

radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows:

CW = (EgCg) + DF [Eq. 1-8] 7 Where: CW = Station Service Water effluent monitor alarm setpoint 15 Cg = Concentration of each measured gamma emitter (g), 7 observed in the effluent (uCi/ml)

OF = zj(C 1/1OECL1) = Dilution factor required to ensure limits 12 of Control 3/4.11.1.1 are not exceeded.

As stated above. for the SSW effluent release pathway there is no 15 additional dilution available. Therefore, if the calculated OF is greater 12 than 1.0. any releases occurring via this pathway will result in a violation of Radiological Effluent Control 3/4.11.1.1. If plant byproduct 15 radioactivity is detected in the SSW effluent, doses due to releases shall be calculated in accordance with the methodology given in Section 1.3. with the near field average dilution factor, Fk. equal to 1.0.

1.2.4 Auxiliary Building to LVW Pond Radiation Monitor XRE-5251A j 9 The purpose of the Auxiliary Building to LVW Pond monitor (XRE-5251A) is to 9 monitor the Auxiliary Building Sumps 3 and 11. Unit 1 and Unit 2 Diesel Generator Sumps 1 and 2 and the Unit 1 and Unit 2 Component Cooling Water Drain Tanks 14 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9a Rev. 15 03/99

continuous discharges and divert these discharges from the Pond to the Waste 9 Water Holdup Tanks if radioactivity is detected. Since detectable radioactivity is not normally present in these discharges, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent radioactive release occur. To this end, the setpoint will be initially established at three (3)times background until further data can be collected. Then, if this setpoint is exceeded. XRE-5251A will direct valves X-HV-WM182 and 183 to divert the discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir. if required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. When radioactive materials are 12 detected in the discharges. a setpoint then may be established for XRE-5251A using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond.

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9b Rev. 15 03/99

1.3 DOSE CALCULATION FOR LIOUID EFFLUENTS For implementation of Radiological Effluent Control 7 3/4.11.1.2, the dose commitment from the release of liquid effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose commitments will be maintained for each calendar quarter and each calendar year. Dose calculations will be performed for releases from the Plant Effluent Tanks, Waste Monitor Tanks, 7A Laundry Holdup & Monitor Tanks, Waste Water Holdup Tanks, and 7 the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir. Although the LVW Pond is 8 located in a CONTROLLED AREA, dose calculations for discharges to the LVW Pond will not be performed because there are no real pathways for exposure to members of the public. Doses for these pathways will be calculated when the LVW Pond is 7 discharged to Squaw Creek Reservoir. The cumulative dose over the desired time period (e.g., the sum of all doses due to releases during a 31 day period, calendar quarter, or a calendar year) will be calculated using the following equation:

DT = I Dk + ZD(lake)m [Eq 1-9]

k m Where DT = the dose commitment to the total body or any organ due 8 to all releases during the desired time interval from all release sources (mrem).

Dk = the dose commitment received by the total body or any 7 organ during the duration of release k(mrem). The equation for calculating Dk is given in Section 1.3.1 (Eq. 1-10)

D(la1:e)m = the dose commitment received by the total body or any 7 organ during the desired time period, m, (normally m =

31 days) due to the buildup in the lake of previously discharged radionuclides. The equation for calculating D(lake)m is given in Section 1.3.2 (Eq.

1-12).

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-10 01/93

To demonstrate compliance with the dose limits of Control 8 3/4.11.1.2, the calculated cumulative dose (i.e., the total dose for both units) will be compared to two times the dose limits for a unit. In other words, the dose assigned to each unit will be one-half of the total doses from all releases from the site.

1.3.1 Calculation of Dose Due to Liauid Releases 7 The dose commitment to the total body or any organ due to a 7 release will be calculated using the following equation.

Dk= 'ZAj tk Cik Fk [Eq. 1-10] 7 Where: tk = the time duration of the release k (hrs) 7 Cik = The isotopic concentration (uCi/ml) of 7 radionuclide I found in the release sample for release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For Sr-89, SR-90, H-3, Fe-55 and alpha emitters, the last measured value will be used in the dose calculation.

Fk = The near field average dilution factor during 7 a liquid effluent release. This is defined as the ratio of the average undiluted liquid effluent flow rate to the average Circulating water flow rate during the release. The average liquid effluent flow rate is based on the actual average flow into the Circulating water during the release.

Fk = average undiluted liquid effluent flow rate 7 circulating water flow rate Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-11 01/93

AiT = the site related ingestion dose commitment 7 factor for the toal body or any organ, r , for each identified gamma or beta emitter (mrem/hr per uCi/ml) . Ai. is calculated as follows:

Ai, = 1.14x10 5 (Uw/Dw + UfBFi) DFi

[Eq. 1-11] 7 Where: 1.14x105 = unit conversion factor, I7 Uw = adult water consumption from Squaw Creek 8 Reservior, 0 liters/yr for CPSES.

Uf = adult fish consumption, 21 kg/yr 77 BFi = bioaccumulation factor for radionuclide i, in 7 fish from Table A-1, Ref. 2 (pCi/kg per pCi/l) 7 DFj = adult dose conversion factor for radionuclide 7 i, from Table E-11, Ref. 2 (mrem/pCi ingested)

Dw = Dilution factor from the near field area 7 within one-quarter mile of the release point to the potable water intake for the adult water consumption; 1.0 for CPSES.

(unitless)

Calculated values for AlT are given in Table 1.2.

1.3.2 Calculation of Dose Due to Radionuclide Buildup in the Lake 7 The dose contribution from significant pathways, due to 8 buildup of previously discharged radionuclides in the lake, must be considered in the committed dose calculation only if Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-12 01/93

radioactivity is detected in the water of Squaw Creek 8 Reservoir or in fish from Squaw Creek Reservoir. Based on the design calculations presented in the CPSES FSAR, Appendix 11A and documented in CPSES Engineering Calculation No. ME-CA-0000-3161, the significant pathways included in this calculation are fish consumption from Squaw Creek Reservoir and consumption of meat from cows drinking water from Squaw Creek. Additionally, consumption of milk from cows drinking water from Squaw Creek is included, but a CPSES site-specific consumption factor of 0 is normally used since there are no identified animals milked for human consumption along Squaw Creek. If animals milked for consumption are identified along Squaw Creek during the annual land use census, this pathway should be included in the dose calculation. Also, water from Squaw Creek Reservoir or Squaw Creek is not used as a source of drinking water, so the drinking water pathway is not included in dose calculations.

To further simplify the calculation, the dose due to 8 consumption of meat and milk from cows drinking water from Squaw Creek is only calculated for tritium. CPSES Engineering Calculation No. ME-CA-0000-3161 shows that tritium is the only isotope routinely released from CPSES that significantly contributes to the dose from these pathways (i.e., >95% of the total dose). The calculation does show a significant dose contribution from Ru-106 for the cow-meat pathway, but this isotope has not historically been observed in actual CPSES liquid effluent samples. The dose from the fish consumption pathway will be calculated for all measured isotopes.

The contribution to the total dose due to the buildup of 8 radionuclides in the reservoir is determined as follows:

D(lake)m = 1.14x104 [(E4 DF c C.D Uf) + 8 DFt Co tw Qaw (Umilk Fmt+ Umeat Fft)l

[Eq. 1-12]

COMANCHE PEAK UNITS 1 AND 2 PART II 1-13 Rev. 8 ERRATA (6/93)

Where: 1.14 x 104 = Units conversion factor (yr/hir).

C if = Concentration of radionuclide i in fish sampled from Squaw Creek Reservoir 20 from location Fl as described in the most current CPSES Land Use Census (pCi/kg).

DF, = Adult ingestion dose conversion factor for tritium for the organ of interest 8 from Table E-l I, Ref. 2 (mrem/pCi).

C ', = Concentration of tritium in the reservoir. This value shall correspond to the 8 highest concentration measured at any Squaw Creek Reservoir sample location (pCi/1).

Consumption rate of contaminated water by a cow, 60 I/day from Table E-3, 8 Ref. 2.

Umul = Adult milk consumption rate. A CPSES site-specific usage factor of 0 is 8 normally used unless milk cows are identified along Squaw Creek during the annual Land Use Census. If milk cows are identified, a value of 310 I/yr from Table E-5, Ref. 82, should be used.

F.T! = Stable element transfer coefficient for tritium that relates the daily intake rate 8 of tritium by a cow to the concentration in milk, l.OE-2 pCi/ per pCi/day from Table E-1, Rev. 2.

Unnt = Adult meat consumption rate, 110 kg/yr from Table E-5, Ref. 2. 18

= Stable element transfer coefficient for tritium that relates the daily intake rate 8 of tritium by a cow to the concentration in meat, I.2E-2 pCi/kg per pCi/day.

COMANCHE PEAK - UNITS I AND 2 PART 11 1-14 R 20 Rev.

07/02

All other variables are previously defined.

NOTE: This calculation is only required if activity is detected in 7 water and/or fish in excess of the appropriate LLD values given in Radiological Effluent Control 3/4.12.1, Table 4.12-1.

If the measured activity in water or fish is less than the required LLD values, the concentration for that particular pathway is assumed to be zero.

1.4 DOSE PROJECTIONS FOR LIQUID EFFLUENTS 7 Radiological Effluent Control 3/4.11.1.3 requires that 8 appropriate portions of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit to CONTROLLED AREAS and UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided for performing this 7 dose projection.

At least once every 31 days, the total dose from liquid 8 releases for each unit for the previous three months will be divided by the number of days in the three month period and multiplied by 31. Also, this dose projection may include the estimated dose for a unit due to any anticipated unusual releases during the period for which the projection is made.

If the projected dose for a unit exceeds 0.06 mrem total body or 0.2 mrem for any organ, appropriate portions of the Liquid Radwaste Treatment System shall be used to reduce radioactivity levels prior to release.

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-15 01/93

1.5 DEFINITIONS OF COMMON LIOUID EFFLUENT PARAMETERS 17 TERM DEFINITION ADF Actual Dilution Factor (unitless). This is defined as the ratio of the effluent flow 7 rate plus the circulating water flow rate divided by the effluent flow rate.

The site related ingestion dose commitment factor to the total body or any organ, r

, for each identified gamma or beta emitter, i. (mRem/hr per uCi/ml)

BF1 Biaccumulation factor for radionuclide, i, in fish from Reg. Guide 1.109. (pCi/kg per pCi/I)

The concentration of alpha emitters in liquid waste as measured in the analysis of 7 the most recent monthly composite sample required by Radiological Effluent Control 3/4.1 1.1. 1, Table 4.1 1-1. (uCi/ml)

CF, The concentration of 55Fe in liquid waste as measured in the analysis of the most 7 recent quarterly composite sample required by Radiological Effluent Control 3/41 1.1. 1, Table 4.1 1-1. (uCi/ml)

C9 The concentration of each measured gamma emitter, g, in the waste tank as measured in the analysis of the sample of each batch as required by Radiological Effluent Control 3i4.1 1.1. 1, Table 4.1 1 i1. (uCi/ml)

C; The concentrations of radionuclide, i, in the waste tank. (uCi/ml) 7 C'; The concentration of radionuclide i in the Reservoir as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Control 3/4.12.1, Table 3.12- 1. This sample is taken at the Circulatory Water Intake Structure as indicated by location SW6 as described in the most current CPSES 20 Land Use Census. (uCi/ml)

C'if The concentration of radionuclide i in fish sampled from the reservoir from location Fl as described in the most current CPSES Land Use Census. (pCi/kg)

Cik The isotopic concentration of radionuclide i found in the pre-release sample for 7 batch release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For "9Sr, Sr, 3 H, 5Fe and alpha emitters, the last measured value will be used. (uCi/ml)

COMANCHE PEAK - UNITS I AND 2 PART 11 1-16 Rev. 20 07102

TERM DEFINITION C' The maximum concentration of radionuclide i in SCR as measured in 12 analysis of monthly samples of SCR.

C1w The liquid waste effluent monitor alarm setpoint. This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in a release at the limits of Control 3.11.1.1. (uCi/ml)

Cs The concentration of 89Sr and 90Sr in liquid waste as measured in the 7 analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1. (uCi/ml)

CSW The Station Service Water effluent monitor alarm setpoint. 15 (uCi/ml). A Ct The concentration of 3H in liquid waste as measured in the analysis 7 of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)

DF1 Adult dose conversion factor for radionuclide. i, from Reg. Guide 1.109. (mrem/pCi ingested)

Dk The dose commitment received by the total body or any organ during the duration of batch release k of liquid effluents. (mRem)

D(lake). The dose commitment received by the total body or any organ during a desired time period. m. due to the buildup in the lake of previously discharged radionuclides. (mRem)

DT The total dose commitment to the total body or any organ due to all releases of liquid effluents during a desired time interval.

(mRem)

D. Dilution factor, from the near field area within 1/4 mile of the release point to the potable water intake for adult water consumption. 1.0 for CPSES. (unitless) f Effluent flow rate. (gpm)

F Circulating water flow rate (or dilution flow rate). (gpm)

F' Adjusted Circulating water flow rate to account for buildup of radionuclides in the Circulating water due to previous releases.

(gpm)

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-17 Rev. 15 03/99

iEm DEFINITION Fk The near field average dilution factor during a liquid effluent release 7 (unitless). This is defined as the ratio of the average undiluted liquid waste flow to the average Circulating water flow during the release.

ECLa Effluent Concentration Limit* of a mixture of unidentified alpha 8 emitters. (uCi/ml)

ECLFe Effluent Concentration Limit* of -Fe. (uCi/ml)

ECLg Effluent Concentration Limit* of each identified gamma emitter. g.

(uCi/ml)

ECL1 Effluent Concentration Limit* of radionuclide, i. (uCi/ml).

89Sr and 9OSr. (uCi/ml)

ECLS Effluent Concentration Limit* of a mixture of ECLt Effluent Concentration Limit* of tritium (3H). (uCi/ml).

SF Safety Factor of 2. Used in the calculation of the Required Dilution 7 Factor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are not exceeded.

RDF Required Dilution Factor (unitless). This is defined as the dilution factor that ensures that 10 times the effluent concentrations expressed in 10CFR20. Appendix B. Table 2. Column 2. are not exceeded at the point of release to CONTROLLED AREAS and UNRESTRICTED AREAS during a discharge.

tk The time duration of batch release k. (hours) 7 U. Adult fish consumption. (kg/yr)

Uw Adult water consumption. (liters/yr)

• Effluent Concentration limits (ECL) for liquids are given4 in 10CFR20, Appendix B. Table 2, Column 2. A value of 2x10- uCi/ml for dissolved or entrained noble gas sha 11 be used.

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-18 Rev. 12 12/95

TABLE 1.1 I

SUMMARY

OF LIQUID RELEASE PATHWAYS I 7

1. RELEASES TO SCR VIA THE CIRC WATER DISCHARGE 7 Release Source Release Type Max Flow Max Vol Monitor Rate (onm) (aal)

PET-1 Batch 100 30000 XRE-5253 7A PET-2 Batch 100 30000 XRE-5253 WMT-1 Batch 100 5340 XRE-5253 7 WMT-2 Batch 100 5340 XRE-5253 LHMT- 1 Batch 100 5875 XRE-5253 LHMT-2 Batch 100 5875 XRE-5253 WWHT-1 Batch > 300 30500 None 12 WWHT-2 Batch 300 30500 None LVW Pond Continuous 1600 None 7

2. RELEASES TO THE WASTE WATER MANAGEMENT SYSTEM 14 Release Source Release Type Max Flow Max Vol Monitor Rate (aDm) (aal)

CPBWRT-A Batch 1550 8500 None 11 CPBWRT-B Batch 1550 17000 None WWHT-1 Batch 200 33100 None 9 WWHT-2 Batch 200 33100 None TBSump2 (Unitl) Continuous 300 1RE-5100 7 TBSump4 (Unit2) Continuous 300 2RE-5100 8 AB Secondary* Continuous 380 XRE-5251A 9 Temporary 14

• • ** None holdup tanks Batch

• • Maximum flow and volume will be determined by temporary systems design.

3. DIRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT) 7 Release Source Release Type Max Flow Max Vol Monitor Rate (aDm) (cal)

Unit 1 SSW Train A Continuous 17,000 1RE-4269 8 Unit 1 SSW Train B Continuous 17.000 1RE-4270 Unit 2 SSW Train A Continuous 17.000 2RE-4269 Unit 2 SSW Train B Continuous 17.000 2RE-4270 9

• AB Secondary Effluents contain the following sources:

Max. Flow (qpm)

Auxiliary Building Sump 3 50 Auxiliary Building Sump 1LUi 50 Diesel Generator Sump 1 ((Unit 1) 50 Diesel Generator Sump 2 (tJnit 1) 50 Diesel Generator Sump 1 CLUnit 2) 50 14 Diesel Generator Sump 2 (lJnit 2) 50 CCWDT (Unit 1) 40 9 CCWDT (Unit 2) 40 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-19 REV. 14 10/96

TABLE 1.2 PAGE (1 of 4)

SITE RELATED INGESTION DOSE COMMITMENT FACTOR Air (mRem/hr per uCi/ml)

LIVER T-BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.26E-O1 2.26E-O1 2.26E-O1 2.26E-O1 2.26E-O1 2.26E-O1 8 C-14 3.13E+04 6.25E+03 6.25E+03 6.25E+03 6.25E+03 6.25E+03 6.25E+03 8 NA-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 8 P-32 4.62E+07 2.87E+06 1.79E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E+06 8 CR-51 O.OOE+OO O.OOE+OO 1.27E+OO 7.62E-O1 2.80E-O1 1.69E+OO 3.20E+02 8 MN-54 O.OOE+OO 4.38E+03 8.35E+02 O.OOE+OO 1.31E+03 O.OOE+OO 1.34E+04 8 MN-56 O.OOE+OO 1.lOE+02 1.95E+O1 O.OOE+OO 1.40E+02 O.OOE+OO 3.51E+03 8 FE-55 6.58E+02 4.55E+02 1.06E+02 O.OOE+OO O.OOE+OO 2.54E+02 2.61E+02 8 FE-59 1.04E+03 2.44E+03 9.35E+02 O.OOE+OO O.OOE+OO 6.82E+02 8.16E+03 8 CO-58 O.OOE+OO 8.91E+O1 2.OOE+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.81E+03 8 CO-60 O.OOE+OO 2.56E+02 5.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+03 8 NI-63 3.11E+04 2.16E+03 1.05E+03 O.OOE+OO O.OOE+OO O.OOE+OO 4.50E+02 8 NI-65 1.26E+02 1.64E+O1 7.49E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.16E+02 8 CU-64 O.OOE+00 9.97E+OO 4.68E+OO O.OOE+OO 2.51E+O1 O.OOE+OO 8.49E+02 8 ZN-65 2.32E+04 7.37E+04 3.33E+04 O.OOE+OO 4.93E+04 O.OOE+OO 4.65E+04 8 ZN-69 4.93E+O1 9.44E+01 6.56E+OO O.OOE+OO 6.13E+O1 O.OOE+OO 1.42E+O1 8 BR-83 O.OOE+OO O.OOE+OO 4.05E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 5.82E+O1 8 BR-84 O.OOE+OO O.OOE+OO 5.24E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 4.11E-04 8 BR-85 O.OOE+OO O.OOE+OO 2.15E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.O1E-15 8 RB-86 O.OOE+OO 1.O1E+05 4.71E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.00E+04 8 RB-88 O.OOE+OO 2.94E+02 1.56E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.93E-09 8 RB-89 O.OOE4OO 1.95E+02 1.37E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E-11 8 SR-89 2.21E404 O.OOE+OO 6.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 8 SR-90 5.47E405 O.OOE+OO 1.33E+05 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+04 8 SR-91 4.07E+02 O.OOE+OO 1.64E+Ol O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+03 8 SR-92 1.54E+02 O.OOE+OO 6.67E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.06E+03 8 Y-90 5.77E-O1 O.OOE+OO 1.54E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.11E+03 8 Y-91M 5.44E-03 O.OOE+OO 2.11E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-02 8 Y-91 8.45E+OO O.OOE+OO 2.25E-O1 O.OOE+OO O.OOE+OO O.OOE+OO 4.64E+03 8 Y-92 5.06E-02 O.OOE+OO 1.48E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.87E+02 8 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-20 01/93

TABLE 1.2 1 7 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A;T (mRem/hr per uCi/ml)

PAGE 2 of 4 ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Y-93 1.60E-01 O.OOE+00 4.43E-03 0.OOE+00 0.OOE+00 0.OOE+00 5.10E+03 8 ZR-95 2.40E-01 7.70E-02 5.21E--02 0.OOE+00 1.21E-01 0.OOE+00 2.44E+02 ZR-97 1.33E-02 2.68E-03 1.22E-03 0.OOE+00 4.05E-03 0.00E+00 8.30E+02 NB-95 4.46E+02 2.49E+02 1.34E+02 0.OOE+00 2.46E+02 0.OOE+00 1.51E+06 MO-99 0.00E+00 1.03E+02 1.96E+01 0.OOE+00 2.35E+02 0.OOE+00 2.39E+02 TC-99M 8.86E-03 2.51E-02 3.20E-01 0.OOE+00 3.80E-01 1.23E-02 1.48E+01 TC-101 9.13E-03 1.31E-02 1.29E-01 0.OOE+00 2.37E-01 6.72E-03 3.95E-14 RU-103 4.42E+00 0.OOE+00 1.91E+00 0.OOE+00 1.69E+01 0.OOE+00 5.16E+02 RU-105 3.69E-01 0.OOE+00 1.45E-01 0.OOE+00 4.76E+00 0.OOE+00 2.26E+02 RU-106 6.59E+01 0.OOE+00 8.33E+00 0.OOE+00 1.27E+02 0.OOE+00 4.27E+03 AG-11OM 8.81E-01 8.13E-01 4.84E-01 0.OOE+00 1.60E+00 0.OOE+00 3.33E+02 TE- 125M 2.57E+03 9.29E+02 3.44E+02 7.72E+02 1.04E+04 0.OOE+00 1.02E+04 TE-127M 6.49E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 0.0OE+00 2.17E+04 TE-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.OOE+00 8.31E+03 TE-129M 1.10E+04 4.11E+03 1.74E+03 3.78E+03 4.60E+04 0.OOE+00 5.54E+04 16 TE-129 3.01E+01 1.13E+01 7.32E+00 2.31E+01 1.26E+02 0.OOE+00 2.27E+01 8 TE-131M 1.66E+03 8.11E+02 6.75E+02 1.28E+03 8.21E+03 0.OOE+00 8.04E+04 16 TE-131 1.89E+01 7.88E+00 5.95E+00 1.55E+01 8.26E+01 0.OOE+00 2.67E+00 8 TE-132 2.41E+03 1.56E+03 1.46E+03 1.72E+03 1.50E+04 0.OOE+00 7.38E+04 I-130 2.72E+01 8.02E+01 3.17E+01 6.78E+03 1.25E+02 0.OOE+00 6.90E+01 I-131 1.50E+02 2.14E+02 1.22E+02 6.99E+04 3.68E+02 0.OOE+00 5.64E+01 I-132 7.29E+00 1.95E+01 6.81E+00 6.81E+02 3.10E+01 0.OOE+00 3.68E+00 I-133 5.09E+01 8.86E+01 2.70E+01 1.30E+04 1.55E+02 0.OOE+00 7.96E+01 I-134 3.80E+00 1.03E+01 3.71E+00 1.79E+02 1.65E+01 0.OOE+00 9.01E-03 I-135 1.59E+01 4.16E+01 1.54E+01 2.75E+03 6.69E+01 0.OOE+00 4.70E+01 CS- 134 2.98E+05 7.09E+05 5.79E+05 0.OOE+00 2.29E+05 7.62E+04 1.24E+04 CS -136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 9.39E+03 1.40E+04 CS-137 3.81E+05 5.22E+05 3.42E+05 0.OOE+00 1.77E+05 5.89E+04 1.01E+04 CS-138 2.64E+02 5.22E+02 2.59E+02 0.OOE+00 3.83E+02 3.78E+01 2.23E-03 BA-139 9.29E-01 6.61E-04 2.72E-02 0.0OE+00 6.18E-04 3.76E-04 1.65E+00 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-21 Rev. 16 7/99

TABLE 1.2 1 7 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A.T (mRem/hr per uCi/ml)

PAGE 3 of 4 ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI BA-140 1.94E+02 2.45E-01 1.27E+01 0.OOE+00 8.30E-02 1.39E-01 4.00E+02 16 BA- 141 4.51E-01 3.41E-04 1.53E-02 0.OOE+00 3.17E-04 1.93E-04 2.06E-10 8 BA- 142 2.04E-01 2.09E-04 1.28E-02 0.OOE+00 1.77E-04 1.19E-04 2.87E-19 LA-140 1.50E-01 7.53E-02 1.99E-02 0.OOE+00 0.OOE+00 0.OOE+00 5.52E+03 LA-142 7.66E-03 3.16E-03 8.66E-04 0.00E+00 0.OOE+00 0.OOE+00 2.54E+01 CE-141 2.24E-02 1.51E-02 1.72E-03 0.OOE+00 7.05E-03 0.OOE+00 5.79E+01 CE-143 3.94E-03 2.91E+00 3.24E-04 0.OOE+00 1.29E-03 0.OOE+00 1.09E+02 CE-144 1.17E+00 4.89E-01 6.26E-02 0.OOE+00 2.91E-01 0.OOE+00 3.94E+02 PR-143 5.52E-01 2.21E-01 2.73E-02 0.OOE+00 1.28E-01 0.00E+00 2.41E+03 PR-144 1.80E-03 7.49E-04 9.16E-05 0.OOEE+00 4.23E-04 0.00E+00 2.59E-10 ND-147 3.76E-01 4.35E-01 2.60E-02 0.OOE+00 2.54E-01 0.00E+00 2.09E+03 W-187 2.95E+02 2.48E+02 8.65E+01 0.OOE+00 0.OOE+00 0.00E+00 8.11E+04 NP-239 2.86E-02 2.79E-03 1.54E-03 0.00E+00 8.74E-03 0.OOE+00 5.74E+02

• SB-122 4.42E+00 8.71E-02 1.29E+00 6.01E-02 0.OOE+00 2.30E+00 1.27E+03

• • SB-124 5.38E+01 1.01E+00 2.12E+01 1.30E-01 0.OOE+00 4.18E+01 1.52E+03

• • BR-82 0.00 E+00 0.OOE+00 1.78E+02 0.OOE+00 0.OOE+00 0.OOE+00 2.05E+02

• • SB-125 4.27E+01 4.58E-01 8.58E+00 3.80E-02 0.OOE+00 4.45E+03 3.78E+02

• • SB-126 2.20E+01 4.47E-01 7.93E+00 1.35E-01 0.OOE+00 1.35E+01 1.80E+03

• • SB- 127 4.94E+00 1.80E-01 1.90E+00 5.94E-02 0.OOE+00 2.93E+00 1.13E+03

• • LA-141 1.14E-02 3.55E-03 5.81E-04 0.00E+00 0.00E+00 0.OOE+00 4.23E+02 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-22 Rev. 16 7/99

• The adult dose conversion factors, DFj, for Sb-122 are not published 5 in Reference 2. The calculation of dose conversion factors and site-related ingestion dose commitment factors for Sb-122 is documented in Reference 10.

• • The adult dose conversion factors, DFj, for Sb-124, Sb-125, Br-82, 7 Sb-126, Sb-127 and La-141 are not published in Reference 2. The site- 8 related dose commitment factors for Sb-124, Sb-125, Br-82, Sb-126, Sb-127 and La-141 were calculated using the "Adult Ingestion Dose Factors" given in Table A-3 of Reference 11, and Equation 1-11 of Part II, Section 1.3.1 of this Manual.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-23 01/93

I Undt I SSW -Train+/-A _i- °-o 0 IRE4269 I Una I SSW -Train B _ af t'fRE~4270 _ Shutdown I Undt 2 SSW -Traln Ampoundmen 0

m l Unit 2 SSW -Traln Ba -

2RE4270 z

C) I:

0 1 ~1975 gal '-

300 gpm Unit I Turbine IRE-5100 Building SumP p11 j io II2 i 1975 gal 300 gpm L. _ Unit 2 Turbine 2RE-5100 iN) Building Sump o No 4 -- L Unit 1 Unit 2 Unit I Unit 2 Auxiliary Builpin FIGURE 1.1 Diesel Gen. Diesel Gen. CCW Drain CCW Drain (Simplified diagram)

Sumps Sumps Tank Tank2oSumps Nos.1&2 los. 1 & 2 Nos. 3 & 11 KEY:

4 (D NWma Mmpath 35 gal ea. 2300 gal 2300 gal 135 gal ea.

O < 135 gal ea.

) 50 gpm ea. 51 5 gpm ea. 40 gpm 40 gpm 50 gpm ea. ---- - F paMI ECL

- - - - - Fb# pait V*ECL 0

THIS PAGE INTENTIONALLY LEFT BLANK 112 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-25 Rev. 12 12/95

• , p 33 ,"-foVI alP At~SADCW CNI8 "Joeft, cIGIlVNf N1W.2 pMp CUtfV\S PM

,.,Mf IDESI0J Co 00 St er Os 1.0 SC.

Ou'W alsJo t1.1 I

)ly OF&M 2S0

50 40 30 20 I I I I I I

. = = %I

_ __ = _I 10 9

8 7

6 5s 0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 GAMMA PHOTON ENERGY, MaV ENERGY RESPONSE TO GAMMA RADIATIONS FOR RD-33 TYPE DETECTOP Figure 1.3 tThe broken pofeWs Nd crve was generated from arly isotopic calibraaons using a chamber of slmtla geometry 8Based one o.mw per dsansgrawon COMANCHE PEAK - UNITS 1 AND 2 PART II 1-27 01/93

SECTION 2.0 GASEOUS EFFLUENTS 8

At CPSES, normal radioactive gaseous effluents are collected in a common exhaust air intake plenum, processed through charcoal and HEPA filters, and discharged to the atmosphere through the two common Plant Vent Stacks designated as Stack A and Stack B. Due to the fact that these release points are below the height of the nearest adjacent structure (i.e., containment building), all gaseous releases from these stacks are conservatively assumed to be entrained into the building wake and cavity regions, which results in a conservative ground-level release.

8 Routine gaseous effluent releases may occur from the Unit 1 and Unit 2 Containment Buildings (purges and vents), Waste Gas Decay Tanks (WGDT),

and the plant vent stacks (continuous ventilation). The normal ventilation exhaust via the plant vent stacks is considered a continuous release. Containment Building vents for pressure relief and WGDT discharges are treated as batch releases. Because Containment Building purges are only allowed during MODES 5 and 6 and because radioactivity is discharged rapidly from the containment atmosphere 10 during purges, the first portion (i.e., the release period during which most containment atmospheric radioactivity is discharged) of a 8 Containment Building purge is considered a batch release. The remainder of a purge is treated as a contribution to the continuous release already occurring through the plant vent stacks.

8 Operating experience has shown that occasional releases may be required from Pressurizer Relief Tank (PRT) vents for depressurizing the RCS during outages, from Volume Control Tank (VCT) vents during maintenance on the Waste Gas Processing System, from the Containment Buildings during Integrated Leak Rate Tests (ILRT), and from secondary steam releases (potentially radioactive during periods of primary-to-secondary leaks). These releases occur infrequently and are treated as batch releases.

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-1 Rev. 10 4/94

A summary of all gaseous effluent release points, release sources, flow rates (if applicable) and 8 associated radiation monitors is shown in Table 2.1. A flow diagram of all gaseous effluent discharge pathways is shown in Figure 2.1.

Each Plant Vent Stack is equipped with a Wide Range Gas Monitor (WRGM) and a Noble Gas 20 Monitor. These monitors are part of the plant Digital Radiation Monitoring System (DRMS) supplied by Sorrento Electronics (formerly General Atomics). Since all DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uCi/mI). The conversion factor for detector output from counts per minute to uCi/mI is determined during the calibration of each individual monitor, and is input into the data base for the monitor microprocessor.

The WRGMs are designated as monitors XRE-5570A and XRE-5570B for Stacks A and B, respectively. Each WRGM consists of a low range (I 0' to 10' uCi/cc), mid range (104 to 102 UCi/CC),

and high range (10 ' to 105 uCi/cc) noble gas activity detector. The WRGMs also have an effluent 4 release rate channel which uses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack flow rate detectors (X-FT-5570A-I/B-1) to provide an indication of noble gas release rate in uCi/sec. Alarm setpoints are established for the WRGM effluent release rate channel to fulfill the requirements of Radiological Effluent Control 314.3.3.5. Exceeding the WRGM effluent release rate channel high alarm setpoint also initiates automatic termination of Waste Gas Decay Tank releases.

The stack Noble Gas Monitors are designated as noble gas channels XRE-5567A and XRE-5567B for 20 Stacks A and B, respectively. The stack noble gas channels may be used as a back-up to the WRGM when no automatic control functions are required. Therefore, a methodology is provided for calculating the noble gas monitor setpoints.

COMANCHE PEAK - UNITS I AND 2 PART 11 2-2 Rev. 20 07/02

Other monitors that may be used for effluent monitoring and control are the Auxiliary Building 8 Ventilation Duct Monitor, XRE-570 1, and the Containment PIG Noble Gas Monitors, 1RE-5503 and 2RE-5503. XRE-5701 may be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary Building Ventilation Duct. XRE-5701 also provides the automatic control function for 8 termination of Waste Gas Decay Tank releases. I RE-5503 and 2RE-5503 monitor the Unit I and Unit 2 Containment atmospheres, respectively, and provide the only automatic control function for termination of Containment vents or purges.

2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 COMPLIANCE l8 2.1.1 Dose Rates Due to Noble Gases 8 For implementation of Radiological Effluent Control 3/4.11.2.1 .a, the dose rate to the total body and skin of an individual at the SITE BOUNDARY due to noble gases released from the site shall be calculated as follows:

A. Total Body Dose Rate Due to Noble Gases 8 Dt = DtV = X/Q) E K, Qr, [Eq.2-1] l v v (noble gases)

Where: D, = Total body dose rate at the SITE BOUNDARY due to noble gases 8 from all release sources (mRem/yr) 8 D= Total body dose rate at the SITE BOUNDARY due to noble gases from release source v (mRem/yr).

COMANCHE PEAK - UNITS I AND 2 PART 11 2-3 07/02

(X/Q) = Highest annual average relative concentration at the SITE BOUNDARY (3.3 x 106 sec/m 3 in the NNW sector at a distance of 1.29 miles from the plant*)

NOTE: The annual average X/Q is also used in 16 determining setpoints for containment purge or vent as required by Technical Specification 3.3.6.

K= -Total body dose factor due to gamma emissions 8 f from noble gas radionuclide i from Table 2.2 (mRem/yr per uCi/m3)

Q,= Total release rate of noble gas radionuclide i from the release source v (uCi/sec) (See C below for calculation of Q1t) v = Index over all release sources

b. Skin Dose Rate Due To Noble Gases I 8 Ds = E Dv = E (X/Q) Li + 1.1 M1) Qj, v v (noble gases)

[Eq. 2-2]

Where: D. = Skin dose rate at the SITE BOUNDARY due to 1 8 noble gases from all release sources.

(mRem/yr)

Dsv = Skin dose rate at the SITE BOUNDARY due to noble gases from release source v. (mRem/yr) 8

• Reference 4, Section 2.3.5.2.

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-4 Rev. 16 7/99

L= the skin dose factor due to beta emissions 8 from noble gas radionuclide i from Table 2.2 (mRem/yr per LCi/m 3 )

1.1 = conversion factor of mRem skin dose per mRad air dose.

M= air dose factor due to gamma emissions from 8 noble gas radionuclide i from Table 2.2 (mRad/yr per ALCi/m 3)

All other terms are as previously defined.

4+

C. Release Rate 8 Qi is defined as the total release rate (gCi/sec) of 8 radionuclide i from all release sources. Qi is given by:

Q. =* Qiv = z Xi FV [Eq. 2-3] 18 v V Where: Xiv = the measured concentration of radionuclide 8 i present in each release source v (jiCl/cm3)

Fv = the flow rate from each release source v 8 (cm3 /sec)

Qiv = the release rate of radionuclide i from 8 release source v (JCi/sec) v = index over all release sources 8 2.1.2 .

{_s Rates Dosn and Due to Radioiodines. Tritium. and Particulates A_@ And . . . . . .

8 Organ dose rates due to iodine-131 and iodine-133, 8 tritium, and all radioactive materials in particulate form with half-lives greater than eight days released from the site will be calculated to implement the requirements of Radiological Effluent Control 3/4.11.2.1.b as follows:

Do = £ Dov = Y (X/Q) £ Pi Qi v V IP&T [Eq. 2-4]

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-5 01/93

Where: 00 = the total organ dose rate due to iodine-131, iodine-133, particulates with 8 half-lives greater than eight days, and tritium from all release sources.

(mrem/yr.)

Dov = the organ dose rate due to iodine-131, 8 iodine-133, particulates with half-lives greater than eight days, and tritium from

- release source v (mrem/yr)

Pie = pathway dose rate parameter factor for 8 radionuclide, i, (for radioiodines, particulates, and tritium) for the inhalation pathway In mRem/yr per uCi/m3 (Table 2.3). The methodology used for determining values of Pi is given in Appendix A.

IP&T = iodine-131, iodine-133, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which 8 the summation function is to be performed.

All other variable are previously defined.

2.2 GASEOUS EFFLUENT MONITOR SETPOINTS 18 The gaseous monitor setpoint values, as determined using the 8 methodology In the following sections, will be regarded as upper bounds for the actual setpoint adjustments. Setpoints may be established at values lower than the calculated values if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.

If a calculated setpoint is less than the measured concentration 8 associated with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and the setpolnt recalculated.

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-6 01/93

2.2.1 Plant Vent Effluent Release Rate Monitors 8 XRE-5570A and XRE-5570B Effluent Release Rate Channels The WRGM effluent release rate channels monitor the release rate 8 of radioactive materials from each plant vent stack by combining inputs from the WRGM low range noble gas activity channel (uCi/cm3 ) indication and a stack flow rate (cm 3/sec) indication (X-FT-5570A-1/B-1) to yield an effluent release rate (uCi/sec).

By establishing an alarm setpoint for this monitor, an increase in either the noble gas activity or stack flow rate will cause an alarm trip. The WRGM effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases. The setpoint for each plant vent effluent release rate monitor will be calculated using the following methodology:

QSITE = the lessor of:

ONG0 X SF 125 O [Eq. 2.5]

De D OR ONG - x SF =750 - [Eq. 2.6]

D S Where: Qsite = Total site noble gas release rate limit 12 corresponding to a dose rate at or beyond the SITE BOUNDARY of 500 mrem/yr to the total body or 3000 mrem/yr to the skin. (uCi/sec)

ON= (noble gases) Q; 8

= Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1. Table 4.11-2.

500 = Dose rate limit to the total body of an 12 individual at or beyond the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-7 Rev. 12 12/95

3000 = Dose rate limit to the skin of the body of an individual at or beyond 12 the SITE BOUNDARY due to noble gases from all release sources.

(mRem/yr)

SF = Safety Factor of 0.5 applied to compensate for statistical fluctuations, 8 errors of measurement, and non-uniform distribution of release activity between the stacks (unitless)

Then the release rate setpoint for each stack monitor, Cf, in uCi/sec is determined as follows:

Cf = Q,,. *AF [Eq. 2-7]

Where: AF = Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitless). This factor will limit the release rate contribution from each stack to 1/2 the limit for the site.

2.2.2 Plant Vent Stack Noble Gas Activity Monitors XRE-557OA/XRE-5570B (WRGM 20 low range noble ias activity channel) and XRE-5567A/XRE-5567B (noble zas channel)

The WRGM low range noble gas activity channels provide noble gas concentration 8 data to the effluent release rate channels, as discussed in Section 2.2.1 above. The monitor design does not include an alarm setpoint for this channel that provides an audible alarm if the setpoint is exceeded. Therefore, setpoint adjustments are not performed for these channels. Radiological Effluent Control 3/'4.3.3.5, Table 3.3-8, 20 ACTION 36 allows for use of the stack noble gas monitors (XRE-5567A and XRE-5567B) as a backup for an inoperable WRGM effluent COMANCHE PEAK - UNITS I AND 2 PART 11 2-8 Rev. 20 07/02

release rate channel when no automatic control function is 8 required. The alarm setpoint for these channels, CG in uCi/cm 3, is determined using the following methodology:

Cf [Eq. 2-8] 8 CG = FPVS Where: FpVS = the maximum stack flow rate 8 (cc/sec) corresponding to 115,000 cfm during normal operations and

- 130,000 cfm during containment purges.

2.2.3 Sampler Flow Rate Monitors (X-RFT-5570A-1/8-1) J8 The WRGMs are designed to sample isokinetically from the plant vent stacks. Isokinetic sample flow is maintained 8 automatically by the monitor microprocessor. The sampler flow rate monitors are designed such that if there is a loss of sample flow, the stack monitor automatic control functions are initiated. The loss of sample flow alarm setpoints are established permanently in accordance with vendor specifications.

2.2.4 Auxiliary Buildinq Ventilation Exhaust Monitor (XRE-5701) J8 Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, 8 ACTION 34, allows for the Auxiliary Building Ventilation (ABV) Duct Monitor (XRE-5701) to be used as a backup for an inoperble WRGM for monitoring Waste Gas Decay Tank (WGDT) releases. XRE-5701 monitors WGDT releases by measuring activity in the Auxiliary Building Vent Duct and providing an automatic control function for termination of WGDT releases. If required, the alarm setpoint for XRE-5701 will be calculated using the following methodology.

The alarm setpoint calculation is based on the following assumption:

(1) a waste gas decay tank release is the only batch 8 release occurring (i.e., a containment purge or vent is not occurring at the same time).R Rev 8 IANCHE PEAK CaF - UNITS 1 AND 2 PART II 2-9 01/93

Based on assumption (1)above, there are a maximum of three 8 release sources that may contribute to the total release rate from the site during a WGDT release. These are the WGDT batch release. the continuous release from Stack A. and the continuous release from Stack B. Therefore, a release factor of 1/3 will be used for the ABV monitor setpoint determination. The total release rate from the site at the alarm setpoint release rate from each stack would correspond to a value of 2 Cf uCi/sec. To determine the ABV monitor setpoint. the release rate contribution from the ABV will be limited to 1/3 of the limiting site release rate:

Qaux = 1/3

• 2Cf = 2/3 Cf [Eq. 2-9] 8 Where: Qaux = Limiting release rate contribution from the 8 Auxiliary Building Vent during WGDT releases (uCi/sec)

Other terms have been previously defined. 8 To determine the setpoint. Ca,. for the ABV monitor in uCi/cc, 8 the limiting ABV release rate is divided by the Maximum ABV flow rate:

Qaux 2Cf 8 Caux = - = [Eq. 2-10]

3 Faux Faux Where: Faux = Maximum ABV flow rate (cc/sec) 8 corresponding to 106,400 cfm.

2.2.5 Containment Atmosphere Gaseous Monitors (1RE-5503 and 8 2RE-5503)

For implementation of Technical Specification 3.3.6. the 16 alarm setpoint for the Containment Atmosphere Gaseous Monitor for Containment Ventilation Isolation will be calculated using the following methodology. The alarm setpoint calculation is based on the following assumption:

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-10 Rev. 16 7/99

(1) a purge or vent from each containment may occur 8 simultaneously and no other batch release is occuring (i.e., a waste gas decay tank release is not occurring at the same time as a containment release).

Based on assumption (1) above, there are a maximum of 8 four release sources that may contribute to the total release rate from the site during a containment release.

These are a-Unit 1 Containment release, a Unit 2 Containment release the continuous release from Stack A, and the continuous release from Stack B. Therefore, a release factor of 1/4 will be used for the the containment monitor setpoint determination. The total release rate from the site at the alarm setpoint release rate from each stack would correspond to a value of 2Cf uCi/sec. To determine the containment monitor setpoint, the release rate contribution from a containment release will be limited to 1/4 of the limiting site release rate:

Qcont = *2 Cf = C [Eq. 2-11]

Where: Qcont = the limiting release rate 8 contribution from a containment release (uCi/sec)

Other terms have been previously defined. j8 To determine the setpoint, Ccont, for the containment 8 monitor in uCi/cc, the limiting containment release rate is divided by the maximum containment release flow rate:

Cnt = Qcont Cf [Eq. 2-12]

cot Fcont 2 cont Where: Fcont = the maximum containment release 8 flow rate (cc/sec) corresponding to 750 cfm for containment vents and 30,000 cfm for containment purges.

Rev 8 COMANCHE PI.EAK - UNITS 1 AND 2 PART II 2-11 01/93

2.3 DOSE CALCULATIONS FOR GASEOUS EFFLUENTS 8 The methodologies for calculating doses from gaseous effluents 8 are given in Sections 2.3.1 and 2.3.2 below. For purposes of demonstrating compliance with the dose limits of Radiological Effluent Controls 3.11.2.2 and 3.11.2.3, the calculated cumulative doses (i.e., the total dose for both units) will be compared to two times the dose limits for a unit. In other words, the dosesasslgned to each unit will be one-half the total doses from all releases from the site.

2.3.1 Dose Due to Noble Gases 8 For implementation of Radiological Effluent Control 8 3/4.11.2.2, the cumulative air dose due to noble gases to areas at and beyond the SITE BOU NDARY will be calculated at least once per 31 days and a cumulative summation of the air doses will be maintained for each calendar quarter and each calendar year. The air dose over the desired time period will be calculated-as follows:

A. Air Dose Due to Gamma Emissions 18 Dy = air dose due to gamma emissions from noble gas 8 radionuclides from all release sources (mrad)

Dy = 3.17 x 10 (X/Q)(noblegases) M. Q.i [Eq. 2-13] 8

- Where: 3.17 x 10-8 = the fraction of a year represented 8 by one second Q'i = the cumulative release of radlonuclide i during 8 the period of interest from all release sources (uCi)

(Q'i = Qi (uCi/sec) x release duration (sec)) 8 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-12 01/93

Q'1 is based on the noble gas activities in each plant vent stack 8 and WGDT or Containment Samples required by Radiological Effluent Control 3/4.11.2.1. Table 4.11-2.

All other variables are previously defined.

B. Air Dose Due to Beta Emissions 8 Do = Air dose due to beta emissions from noble gas radionuclides. (mrad)

"I-D = 3.17 x 10 ( (noble N1 of' [Eq.2-14)

Where: Ni = Air dose factor due to beta emissions from noble gas radionuclide i from Table 2.2.

(mRad/yr per uCi/m3 ).

All other variables are previously defined.

NOTE: If the methodology in this section is used in 12 determining dose to an individual rather than air dose due to noble gases, substitute K; for Mi, (Li + 1.1 Mi) for N1, and the Annual Average X/Q values from information listed and maintained current in the results of the annual Land Use Census for the highest annual average relative concentration (X/Q) at the SITE BOUNDARY.

2.3.2 Dose Due to Radioiodines. Tritium, and Particulates 8 For implementation of Radiological Effluent Control 3/4.11.2.3.

the cumulative dose to each organ of an individual due to iodine-131, iodine-133, tritium, and particulates with half-lives greater than 8 days will be calculated at least once per 31 days and a cumulative summation of these doses will be maintained for each calendar quarter and each calendar year. The dose over the desired period will be calculated as follows:

Dp = E 3.17 x 10.8 W' E RP i,ao i Q' [Eq.2-15]

paths I&PT COMANCHE PEAK - UNITS 1 AND 2 PART II 2-13 Rev. 12 12/95

Where: Dp - Dose due to all real pathways to organ. o. of an 8 individual in age group. a, from iodine-131.

iodine-133. tritium. and radionuclides in particulate form with half-lives greater than eight days from all release sources (mRem).

WI Dispersion parameter for estimating the dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. Locations of 12 interest are listed in the results of the annual Land Use Census.

WI X/Q for the inhalation pathway in sec/m 3. X/Q is the 8 annual average relative concentration at the location of interest. Values for X/Q are listed in the 12 results of the annual Land Use Census. If desired, 8 the highest individual receptor X/Q or X/Q value may be used, or W= D/Q for the food and ground plane pathways in m D/Q is the annual average deposition at the location of interest. Values for D/Q are listed in the 12 results of the annual Land Use Census. If desired, the highest individual receptor D/Q or D/Q value may 8 be used.

NOTE: For tritium. the dispersion parameter. W' is taken as 12 the annual average X/Q values from information listed and maintained current in the results of the annual Land Use Census for inhalation, food and ground plane pathways.

RPi a o = Dose factor for radionuclide i. pathway p. age group 8 3

a and organ o. in mRem/yr per uCi/m for the inhalation pathway and M 2 (mRem/yr) per uCi/sec for food and ground plane pathways. except for tritium which is in mRem/yr per uCi/m 3 for all pathways. The values for RPiao for each pathway. radionuclide. age group and organ are listed in Table 2.4.

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-14 Rev. 12 12/95

The methodioogies used for determining values of 8 RP1i do for each pathway are given in Appendices B through F.

Q'= Cumulative release of radionuclide. i. during the period of interest (uCi). Q'i is based on the activities measured in each plant vent stack from the analyses of the particulate and iodine samples required by Radiological Effluent Control 3/4.11.2.1. Table 4.11-2.

I&PT = Iodines, particulates with half-lives greater than eight days. and tritium. These are the isotopes over which the summation function is to be performed.

PATHS = The real pathways of exposure to individuals at 12 the locations of interest.

2.4 DOSE PROJECTIONS FOR GASEOUS EFFLUENTS 8 Radiological Effluent Control 3/4.11.2.4 requires that appropriate portions of 12 the PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent from a unit to areas at or beyond the SITE BOUNDARY would exceed. in a 31-day period, either:

0.2 mrad to air from gamma radiation; or 8 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

The following calculational method is provided for performing this dose projection:

At least once every 31 days the gamma air dose. beta air dose and the maximum organ dose for each unit for the previous three months will be divided by the number of days in the three month period and multiplied by 31. Also. this dose projection may COMANCHE PEAK - UNITS 1 AND 2 PART II 2-15 Rev. 12 12/95

include the estimated dose due to any anticipated unusual releases during the period for which the projection is made, such as Waste Gas 8 Decay Tank release. If the projected doses for a unit exceed any of the values listed above, appropriate portions of the PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM shall be used to reduce radioactivity levels prior to release.

8 2.5 DOSE CALCULATIONS TO SUPPORT OTHER REQUIREMENTS For the purpose of implementing the requirements of Radiological 10 Effluent Control 6;9.1.4, the Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses due to radioactive 10 liquid and gaseous effluents from the station during the previous year 8 of operation. This assessment shall be a summary of the doses determined in accordance with Section 1.3 for doses due to liquid effluents, Section 2.3.1 for air doses due to noble gases, and Section 2.3.2 for doses due to iodines, tritium, and particulates. This same report shall also 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. This assessment shall be 8 performed in accordance with the methodologies in Sections 1.3, 2.3.1, and 2.3.2, using either historical average or concurrent dispersion and deposition parameters for the locations of interest, and taking into account occupancy factors. All assumptions and factors used in the determination shall be included in the report.

For the purpose of implementing Radiological Effluent Control 3/4.12.2 dose calculations for the new locations identified in the land use 8 census shall be performed using the methodology in Section 2.3.2, substituting the appropriate pathway receptor dose factors and dispersion parameters for the location(s) of interest. Annual average dispersion parameters may be used for these calculations. If the land use census changes, the critical location (i.e., the location where an individual would be exposed to the highest dose) must be reevaluated for the nearest residence, the nearest milk animal, and the nearest COMANCHE PEAK - UNITS 1 AND 2 PART II 2-16 Rev. 10 4/94

vegetable garden. Additionally, when a location is identified that

• . yields a calculated dose 20% greater than at a location where environmental samples are currently being obtained, add the new location within 30 days to the Radiological Environmental Monitoring locations described in Section 3.1 of this manual.

For the purpose of Implementing Radiological Effluent Control 3/4.11.4, the total annual dose to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by summing the annual doses determined for a member of the 8 public in accordance with the methodology of Sections 1.3, 2.3.1, and 2.3.2 and the direct radiation dose contributions from the units and from outside storage tanks to the particular member of the public. This assessment must be performed in the event calculated doses from the effluent releases exceed twice the limits of Controls 3/4.11.1.2, 3/4.11.2.2, or 3/4.11.2.3. This assessment will be included in the 10 Annual Radioactive Effluent Release Report to be submitted the year after the assessment was required. Otherwise, no assessments are required.

For the evaluation of doses to real individuals from liquid releases, 8 j the same calculation methods as employed in Section 1.3 will be used.

However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides. The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide concentrations. For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as employed in Sections 8 j 2.3.1 and 2.3.2 will be used. In Section 2.3.1, the total body dose factor should be substituted for the gamma air dose factor (M1 ) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the meteorological conditions, and the consumption of food. Data obtained from the latest land use census should be used to COMANCHE PEAK - UNITS 1 AND 2 PART II 2-17 Rev. 10 4/94

determine locations for evaluating doses. The results of the 8 Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations.

The dose component due to direct radiation may be determined by 8 calculation or actual measurement (e.g., thermoluminescent dosimeters, micro-R meter, etc.). The calculation or actual measurement of direct radiation shall be documented in the Special Report that must be submitted if this determination is required.

2.6 METEOROLOGICAL MODEL 18 2.6.1 Dispersion Calculations 18 Atmospheric dispersion for gaseous releases is calculated 8 using a straight line flow Gaussian model similar to the Constant Mean Wind Direction model given in Regulatory Guide 1.111, Section C.1.c. The method given here is modified by including factors to account for plume depletion and effects of the open terrain. The average relative concentration is given by the following equation:

X = 2.0325 K j k (N r jk ( )) [Eq. 2-16]

Where:

X/Q = average concentration normalized by source 8 strength (sec/m 3).

2.032 = (2/vi )1/2 - (2 vr /16)-l. 8 5 = plume depletion factor at distance r for 8 the applicable stability class (Figure 2.2). Normally, a value of 1.0 is assumed when undepleted X/Q values are to be used in dose calculations.

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-18 01/93

K = terrain correction factor (Figure 2.5) 18 njk= the number of hours meteorological conditions are observed to be in a given wind direction, wind speed class, k, and atmospheric stability class, j.

N = total hours of valid meteorological data throughout the period of release.

NOTE: If hourly meteorological data are used, all variable 8 subscripts are dropped, njk and N are set equal to 1, and the hourly averaged meteorological variables are used in the model.

r = downwind distance from the release point tt 8 the location of interest (meters) 5jk = the average windspeed (midpoint of 8 windspeed class, k) measured at the 10 meter level during stability class j.

(meters/sec) j(r) = the vertical plume spread with a volumetric 8 correction for a release within the building wake cavity, at a distance, r, for stability class, J, expressed in meters.

NOTE: All parameters are considered dimensionless unless 8 otherwise indicated.

The equation for calculating Zj(r) is:

18 2 + 0.5 b2/10i (er [Eq. 2-17]

Y. (r) = the lesser of 3i a [Eq. 2-18]

Where:

aJ = the vertical standard deviation of 8 materials in the plume at distance, r, for atmospheric stability class, J, expressed in meters (Figure 2.3)

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-19 01/93

0.5 = the building shape factor. 8 b = the vertical height of the reactor 8 containment structure (79.4 meters) 2.6.2 Deposition Calculations 18 The relative deposition per unit area is calculated as follows: 8 D 9 [Eq. 2-19J Q 0.3927 r Where:

D/Q = deposition per unit area normalized by 8 source strength (m-2 )

Dg = relative deposition rate for a ground level 8 release (m-1) (Figure 2.4) z = the fraction of time the wind blows to the 8 sector of interest.

NOTE: If hourly meteorological data are used, z is set equal to 8 one.

0.3927 = the width in radians of a 22.50 sector. 8 Other variables are as previously defined. 8 NOTE: All parameters are considered dimensionless unless 8 otherwise indicated.

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-20 01/93

2.7 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS 18 Term Definition AF Allocation Factor of 0.5 applied to account for releases 8 from both stacks simultaneously. This factor will limit the release rate contribution from each stack to 1/2 the limit for the site B vertical height of the reactor containment structure CG the alarm setpoint for each plant vent stack noble gas 8 activity monitor (uCi/cm3 )

Cf the alarm setpoint for each plant vent stack effluent release rate monitor (uCi/sec) caux the Auxiliary Building Ventilation Exhaust monitor alarm setpoint (uCi/cm3 )

Ccont the Containment Atmosphere Gaseous monitor alarm setpoint 8 (uCi/cm 3)

Dg relative deposition rate for a ground-level release (m-l)

Do the total organ dose rate due to tritium, iodines, and 8 particulates with half-lives greater than eight days from all gaseous release sources (mRem/yr)

Dov the organ dose rate due to tritium, iodines, and 8 particulates with half-lives greater than eight days from gaseous release source v (mRem/yr)

Dp dose to any organ of an individual from radioiodines, 8 tritium and radionuclides in particulate form with half-lives greater than eight days from all release sources (mRem)

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-21 01/93

Term Definition Ds Skin dose rate at the SITE BOUNDARY due to noble gases 8 from all release sources. (mRem/yr)

Dsv Skin dose rate at the SITE BOUNDARY due to noble 8 gases from release source v. (mRem/yr)

Dt Total body dose rate at the SITE BOUNDARY due to noble 8 gases from all release sources. (mRem/yr)

Dtv Total body dose rate at the SITE BOUNDARY due to 8 noble gases from release source v. (mRem/yr)

DJ6 Air dose due to beta emissions from noble gases from all 8 release sources. (mRad)

D0, Air dose due to gamma emissions from noble gases from all 8 release sources. (mRad)

D/Q Annual average relative deposition at the location of interest. (m-2 )

a Plume depletion factor at distance r for the appropriate stability class (radioiodines and particulates).

8 Fv Flow rate from each release source v. (cm3/sec) 8 Faux Maximum Auxiliary Building Ventilation flow rate 8 (cm3 /sec) corresponding to 106,400 cfm.

Fcont Maximum containment release flow rate (cm3 /sec) 8 corresponding to 750 cfm for containment vents and 30,000 cfm for containment purges.

FpVS Maximum stack flow rate (cc/sec) corresponding to 8 115,000 cfm during normal operations and 130,000 cfm during containment purges.

COMANCHE PEAK UNITS 1 AND 2 PART II 2-22 Rev. 8 ERRATA (6/93)

Term_ Definition K terrain recirculation factor (Unitless) 8 Ki total body dose factor due to gamma emissions from noble 8 gas radionuclide i (mRem/yr per uCi/m 3 )

Li skin dose factor due to beta emissions from noble gas 8 radionuclide i (mRem/yr per uCi/m 3)

"I Mi air dose factor due to gamma emissions from noble gas 8 radionuclide i (mRem/yr per uCi/m 3 )

Ni air dose factor due to beta emissions from noble gas 8 radionuclide i (mRem/yr per uCi/m 3) njk number of hours meteorological conditions are observed 8 to be in a given wind direction, wind speed class k, and atmospheric stability class J N total hours of valid meteorological data 8 Pi pathway dose rate parameter for radionuclide i, (other 8 than noble gases) for the inhalation pathway (mRem/yr per uCi/cm 3)

Qaux the limiting release rate contribution from the 8 Auxiliary Building Vent during WGDT releases (uCi/sec)

Qcont the limiting release rate contribution from a containment 8 release (uCi/sec)

Qi total release rate of radionuclide 1 from all release 8 sources (uCi/sec)

Rev 8 rnMAmrvw WUI~~IL1 DPAY IA~rM rAI-UlA

- IIMTTI I )

1 Amn ?

& -IS L DADT r Al .

TT 2-29

. . L L 01/93

8 Term Definition Defi niti on 8 Qtv1 Total release rate of radionuclide i from release source v. (uCi/sec)

Qs, Cumulative release of radionuclide i during the period of interest from all release sources. (uCi)

ONG Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from analyses of samples taken in accordance with Control 3/4.11.2.1. Table 4.11-2.

Q5E Total site noble gas release rate limit corresponding to a dose rate at 12 or beyond the SITE BOUNDARY of 500 mRem/yr to the total body or 3000 mRem/yr to the skin. (uCi/sec)

RPi ao: Dose factor for radionuclide i. pathway p, and age group a. and organ o 8 (mRem/yr per uCi/m 3 ) or(m2-mRem/yr per uCi/sec).

r Distance from the point of release to the location of interest for dispersion calculations. (meters)

SF Safety Factor of 0.5 applied to compensate for statistical fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks.

Xj(r) Vertical plume spread with a volumetric correction for a release within the building wake cavity, at a distance. r, for stability class. j.

expressed in meters.

aa Vertical standard deviation of the plume concentration (inmeters). at distance. r, for stability category j.

usek Wind speed (midpoint of windspeed class k) at ground level (m/sec) during atmosphere stability class j.

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-24 Rev. 12 12/95

Term Definition 8 WI Dispersion parameter for estimating the dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum exposures.

X/Q Annual average relative concentration at the location of interest.

(sec/M 3)

X/Q Highest annual average_relative concentration at the SITE BOUNDARY.

(sec/M 3) (3.3 x 10-6 sec/m 3 in the NNW sector) xi,, Measured concentration of radionuclide i present in each release source

v. (uCi/cm 3).

z Fraction of time the wind blows to the sector of interest. 8 1.1 Conversion factor of mRem skin dose per mRad air dose.

500 Dose rate limit to the total body of an individual at or beyond the 12 SITE BOUNDARY due to noble gases from all release sources. (mRem/yr) 3000 Dose rate limit to the skin of the body of the individual at or beyond the SITE BOUNDARY due to noble gases from all release sources.

(mRem/yr)

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-25 Rev. 12 12/95

C,)

0 C, TABLE 2.1 18 M

m

SUMMARY

OF GASEOUS RELEASE PATHWAYS

<n l8

1. RELEASES VIA THE PLANT VENT STACKS 8I-4 1 8 6-4 C--

I RELEASE SOURCE RELEASE TYPE MAY- FLOW RATE (rfm) MnmTTARDSt 18 Stack A Continuous 115.000 XRE-5570A/XRE-5567A Cy Stack B 8

Continuous 115,000 XRE-5570B/XRE-5567B 8 rN WGDT's Batch 20 XRE-5570A&B/XRE-5701 8 U-1 Cont. Vent. Batch 750 lRE-5503 -

U-1 8

Cont. Purge Batch 30,000 lRE-5503 f 8 U-2 Cont. Vent. Batch 750 2RE-5503 8 U-2 Cont. Purge Batch 30.000 2RE-5503 8 RA

--I

2. RELEASES VIA THE

'-4

_%3

- ILRT VENT lB rl REI FASF miortpF DcI CARC TVDr

• lMA aL.

UAYV

, rICLI rLUVI nkirr.

MAIlt t TIT) I

.. A.. -n r MUMIIUK:io)

---

I au L^.L.I 1 8 ILRT Batch 1 8

TABLE 2.2 18 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES*

Isotope 'Y-Body***(K) 0-Skin***(L) 'v-A1r**(M) 0-A1r**(N1 Kr-83m 7.56E-02 1.93E+01 2.88E.02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+O1 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

• Values taken from Reference 2, Table B-1

• • rad-m3 uCi-yr

• • • jRemM 3 uCi-yr Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-27 01/93

TABLE 2.3 PATHWAY DOSE RATE PARAMETER (Pi)*

• BASED ON THE INHALATION PATHWAY FOR THE CHILD AGE GROUP I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 2.60E+06 1.14E+05 9.88E+04 O.OOE+00 O.OOE+00 O.OOE+00 4.22E+04 CR-51 O.OOE+00 O.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 O.OOE+00 4.29E+04 9.51E+03 O.OOE+00 1.OOE+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+00 O.OOE+OO 1.llE+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+00 O.OOE+00 1.27E+06 7.07E+04 CO-58 O.OOE+00 1.77E+03 3.16E+03 O.OOE+00 O.OOE+00 1.l1E+06 3.44E+04 CO-60 O.OOE+00 1.31E+04 2.26E+04 O.OOE+00 O.OOE+00 7.07E+06 9.62E+04 NI-63--- 8.21E+05 4.63E+04 2.80E+04 O.OOE+00 O.OOE+00 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+00 7.14E+04 9.95E+05 1.63E+04 RB-86 O.OOE+00 1.98E+05 1.14E+05 O.OOE+00 O.OOE+00 O.OOE+00 7.99E+03 SR-89 5.99E+05 O.OOE+00 1.72E+04 O.OOE+00 O.OOE+00 2.16E+06 1.67E+05 SR-90 1.01E+08 O.OOE+00 6.44E+06 O.OOE+00 O.OOE+00 1.48E+07 3.43E+05 Y-91 9.14E+05 O.OOE+00 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+00 5.96E+04 2.23E+06 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+00 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 O.OOE+00 1.07E+03 O.OOE+00 7.03E+03 6.62E+05 4.48E+04 RU-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+00 1.84E+05 1.43E+07 4.29E+05 AG-llOM 1.69E+04 1.14E+04 9.14E+03 O.OOE+00 2.12E+04 5.48E+06 1.OOE+05 TE-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+00 4.77E+05 3.38E+04 TE-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+00 5.48E+03 CS-134 6.51E+05 1.O1E+06 2.25E+05 O.OOE+00 3.30E+05 1.21E+05 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 O.OOE+00 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 O.OOE+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+00 2.11E+01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 O.OOE+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 O.OOE+00 3.OOE+03 4.33E+05 9.73E+04 ND-147 1.08E+04 8.73E+03 6.81E+02 O.OOE+00 4.81E+03 3.28E+05 8.21E+04

---

_------------------__ 0____Ah -------------

COMANCHE PEAK - UNITS 1 AND 2 PART n 2-28 Rev 8 01/93

TABLE 24 PATHWAY DOSE FACTORS AGE GROUP: ALL PATHWAY: GROUND PLANE I ORGAN DOSE FACTORS NUCLIDE I---------------------

_ T. BODY SKIN N-3 O.OOE+OO O.OOE+OO P-32 O.OOE+OO O.OOE+OO CR-51 4.65E+06 5.50E+06 MN-54 1.39E+09 1.62E+09 FE-55 O.OOE+OO O.OOE+OO FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 CO-60 2.15E+10 2.53E+10 NI-63 O.OOE+OO O.OOE+OO ZN-65 7.47E+08 8.59E+08 RB-86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51E+04 SR-90 O.OOE+OO O.OOE+OO Y-91 1.07E+06 1.21E+06 ZR-95 2.45E+08 2.84E+08 NB-95 1.37E+08 1.61E+08 RU-103 1.08E+08 1.26E+08 RU-106 4.22E+08 5.06E+08 AG-llOM 3.44E+09 4.01E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 TE-129H 1.98E+07 2.31E+07 I-131 1.72E+07 2.09E+07 I-133 2.45E+06 2.98E+06 CS-134 6.86E+09 8.OOE+09 CS-136 1.51E+08 1.71E+08 CS-137 1.03E+10 1.20E+10 BA-140 2.06E+07 2.36E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07 8.05E+07 PR-143 O.OOE+OO O.OOE+OO ND-147 8.39E+06 1.O1E+07 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART n 2-29 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 P-32 1.70E+10 1.06E+09 6.58E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E+09 CR-51 O.OOE+OO O.OOE+OO 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN-54 O.OOE+OO 8.40E+06 1.60E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.57E+07 FE-55 2.51E+07 1.73E+07 4.04E+06 O.OOE+OO O.OOE+OO 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 2.67E+07 O.OOE+OO O.OOE+OO 1.95E+07 2.32E+08 CO-58 O.OOE+OO 4.71E+06 1.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.54E+07 CO-60 O.OOE+OO 1.64E+07 3.61E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 NI-63 6.72E+09 4.65E+08 2.25E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.71E+07 ZN-65 -_-1.37E+09 4.36E+09 1.97E+09 O.OOE+OO 2.91E+09 O.OOE+OO 2.74E+09 RB-86 O.OOE+OO 2.59E+09 1.21E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.10E+08 SR-89 1.45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-08 SR-90 4.67E+10 O.OOE+OO 1.15E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E-09 Y-91 8.57E+03 O.OOE+OO 2.29E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.72E+06 ZR-95 9.41E+02 3.02E+02 2.04E+02 O.OOE+OO 4.74E+02 O.OOE+OO 9.57E+05 NB-95 8.24E+04 4.58E+04 2.46E+04 O.OOE+OO 4.53E+04 O.OOE+OO 2.78E+08 RU-103 1.02E+03 O.OOE+OO 4.38E+02 O.OOE+OO 3.88E+03 O.OOE+OO 1.19E+05 RU-106 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.93E+04 O.OOE+OO 1.32E+06 AG-llOM 5.81E+07 5.38E+07 3.19E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.19E+10 TE-125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61E+07 O.OOE+OO 6.49E+07 TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 O.OOE+OO 1.53E+08 TE-129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 O.OOE+OO 3.02E+08 I-131 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 O.OOE+OO 1.12E+08 I-133 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 O.OOE+OO 6.04E+06 CS-134 5.64E+09 1.34E+10 1.1OE+10 O.OOE+OO 4.34E+09 1.44E+09 2.35E+08 CS-136 2.63E+08 1.04E+09 7.48E+08 O.OOE+OO 5.78E+08 7.92E+07 1.18E+08 CS-137 7.37E+09 1.O1E+10 6.60E+09 O.OOE+OO 3.42E+09 1.14E+09 1.95E+08 BA-140 2.69E+07 3.38E+04 1.76E+06 O.OOE+OO 1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71E+02 O.OOE+OO 1.52E+03 O.OOE+OO 1.25E+07 CE-144 3.57E+05 1.49E+05 1.92E+04 O.OOE+OO 8.85E+04 O.OOE+OO 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81E+OO O.OOE+OO 3.65E+O1 O.OOE+OO 6.90E+05 ND-147 9.40E+O1 1.09E+02 6.50E+OO O.OOE+OO 6.35E+O1 O.OOE+OO 5.22E+05 COMANCHE PEAK - UNITS 1 AND 2 Rev 8 PART 1 2-30 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 P-32 3.15E+10 1.95E+09 1.22E+09 O.OOE+OO O.OOE+00 O.OOE+00 2.65E+09 CR-51 O.OOE+00 O.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 O.OOE-i00 1.40E+07 2.78E+06 O.OOE+00 4.19E+06 O.OOE+00 2.88E+07 FE-55 4.46E+07 3.16E+07 7.37E+06 O.OOE+00 O.OOE+00 2.01E+07 1.37E+07 FE-59 5.19E+07 1.21E+08 4.68E+07 O.OOE+00 O.OOE+00 3.82E+07 2.86E+08 CO-58 O.OOE+00 7.94E+06 1.83E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.10E+08 CO-60 O.OOE+00 2.78E+07 6.27E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.62E+08 NI-63 1.18E+10 8.36E+08 4.01E+08 O.00E+00 O.OOE+00 O.OOE+00 1.33E+08 ZN 2.11E+09 7.32E+09 3.42E+09 O.OOE+00 4.69E+09 O.OOE+00 3.10E+09 RB-86 O.OOE+00 4.73E+09 2.22E+09 O.OOE+00 O.OOE+00 O.OOE+00 7.OOE+08 SR-89 2.68E+09 O.OOE+00 7.67E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.19E+08 SR-90 6.62E+10 O.OOE+00 1.63E+10 O.OOE+00 O.OOE+00 O.OOE+00 1.86E+09 Y-91 1.58E+04 O.OOE+00 4.24E+02 O.OOE+00 O.OOE+00 O.OOE+00 6.48E+06 ZR-95 1.65E+03 5.21E+02 3.58E+02 O.OOE+00 7.65E+02 O.OOE+00 1.20E+06 NB-95 1.41E+05 7.82E+04 4.30E+04 O.OOE+00 7.58E+04 O.OOE+00 3.34E+08 RU-103 1.81E+03 O.OOE+00 7.75E+02 O.OOE+00 6.39E+03 O.OOE+00 1.51E+05 RU-106 3.76E+04 O.OOE+OO 4.73E+03 O.OOE+00 7.24E+04 O.OOE+00 1.80E+06 AG-llOM 9.64E+07 9.12E+07 5.55E+07 O.OOE+00 1.74E+08 O.OOE+00 2.56E+10 TE-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 O.OOE+00 O.OOE+00 8.87E+07 TE-127M 8.45E+07 3.OOE+07 1.OOE+07 2.01E+07 3.42E+08 O.OOE+00 2.11E+08 TE-129M 1.lOE+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 O.OOE+00 4.14E+08 1-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 O.OOE+00 1.49E+08 I-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 O.OOE+00 9.09E+06 CS-134 9.83E+09 2.31E+10 1.07E+10 O.OOE+00 7.35E+09 2.81E+09 2.88E+08 CS-136 4.49E+08 1.77E+09 1.19E+09 O.OOE+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.21E+09 O.OOE+00 6.06E+09 2.36E+09 2.54E+08 BA-140 4.87E+07 5.97E+04 3.14E+06 O.OOE+00 2.02E+04 4.01E+04 7.51E+07 CE-141 8.89E+03 5.94E+03 6.82E+02 O.OOE+00 2.80E+03 O.OOE+00 1.70E+07 CE-144 6.59E+05 2.73E+05 3.54E+04 O.OOE+00 1.63E+05 O.OOE+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 O.OOE+00 6.73E+01 O.00E+OO 9.55E+05 ND-147 1.81E+02 1.97E+02 1.18E+01 O.OOE+00 1.16E+02 O.OOE+00 7 12E+05 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART n 2-31 01/93

TABLE 24 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK I ORGAN DOSE FACTORS NUCLIDE I------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 P-32 7.77E+10 3.64E+09 3.OOE+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+09 CR-51 O.OOE+OO O.OOE+OO 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 O.OOE+OO 2.10E+07 5.59E+06 O.OOE+OO 5.89E+06 O.OOE+OO 1.76E+07 FE-55 1.12E+08 5.94E+07 1.84E+07 O.OOE+OO O.OOE+OO 3.36E+07 1.10E+07 FE-59 1.20E+08 1.95E+08 9.70E+07 O.OOE+OO O.OOE+OO 5.65E+07 2.03E+08 CO-58 O.OOE+OO 1.21E+07 3.72E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+07 CO-60 O.OOE+OO 4.32E+07 1.27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+08 NI-63 2.97E+10 1.59E+O9 1.O1E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 ZN-65 , 4.14E+09 1.10E+10 6.86E+09 O.OOE+OO 6.95E+09 O.OOE+OO 1.94E+09 RB-86 O.OOE+OO 8.78E+09 5.40E+09 0.OOE+OO O.OOE+OO O.OOE+OO 5.65E+08 0.OOE+00 SR-89 6.63E+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.57E+08 SR-90 1.12E+ll O.OOE+OO 2.84E+10 0.OOE+OO O.OOE+OO O.OOE+OO 1.51E+09 Y-91 3.91E+04 O.OOE+OO 1.05E+03 0.OOE+OO O.OOE+OO O.OOE+OO 5.21E+06 ZR-95 3.84E+03 8.43E+02 7.51E+02 O.OOE+O0 1.21E+03 O.OOE+OO 8.80E+05 NB-95 3.18E+05 1.24E+05 8.86E+04 O.OOE+OO 1.16E+05 O.OOE+OO 2.29E+08 RU-103 4.29E+03 O.OOE+OO 1.65E+03 1.08E+04 O.OOE+OO 1.l1E*05 O.OOE+OO RU-106 9.25E+04 O.OOE+OO 1.15E+04 O.OOE+OO 1.25E+05 O.OOE+OO 1.44E+06 AG-llOM 2.09E+08 1.41E+08 1.13E+08 2.63E+08 O.OOE+OO 1.68E+10 TE-125M 7.39E+07 2.OOE+07 9.85E+06 2.07E+07 O.OOE+OO O.OOE+0O 7.13E+07 TE-127M 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 O.OOE+OO 1.69E+08 TE-129M 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 O.OOE+OO 3.31E+08 I-131 1.31E+09 1.31E+09 7.46E+08 4.34E+ll 2.16E+09 O.OOE+OO 1.17E+08 I-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 Q.OOE+OO 8.58E+06 CS-134 2.27E+10 3.72E+10 7.85E+09 O.OOE+OO 1.15E+10 4.14E+09 2.01E+08 CS-136 1.O1E+09 2.79E+09 1.80E+09 O.OOE+OO 1.49E+09 2.21E+08 9.80E+07 CS-137 3.23E+10 3.09E+10 4.56E+09 O.OOE+OO l.O1E+10 3.62E+09 1.93E+08 BA-140 1.18E+08 1.03E+05 6.86E+06 O.OOE+OO 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 O.OOE+OO 4.79E+03 O.OOE+OO 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 O.OOE+OO 2.82E+05 O.OOE+OO 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+O1 O.OOE+OO 1.17E+02 O.OOE+OO 7.75E+05 ND-147 4.45E+02 3.61E+02 2.79E+O1 O.OOE+00 1.98E+02 O.OOE+OO 5.71E+05 COMANCHE PEAK - UNITS 1 AND 2 Rev 8 PART n 2-32 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 P-32 1.60E+11 9.42E+09 6.21E+09 O.OOE+00 O.O0E+OO O.OOE+00 2.17E+09 CR-51 O.OOE+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 O.OOE+00 3.91E+07 8.85E+06 O.OOE+00 8.65E+06 O.OOE+00 1.43E+07 FE-55 1.35E+08 8.74E+07 2.34E+07 0.OOE+OO O.OOE+00 4.27E+07 1.llE+07 FE-59 2.25E+08 3.93E+08 1.55E+08 O.OOE+00 O.OOE+00 1.16E+08 1.88E+08 CO-58 O.OOE+00 2.43E+07 6.06E+07 O.OOE+00 O.OOE+00 O.OOE+00 6.05E+07 CO-60 O.OOE+00 8.83E+07 2.08E+08 O.00E+00 O.OOE+00 O.OOE+00 2.10E+08 NI-63 3.50E+10 2.16E+09 1.21E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.08E+08 ZN-65 - 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 O.OOE+00 1.61E+10 RB-86 O.OOE+00 2.23E+10 1.10E+10 O.OOE+00 0.00E+00 O.OOE+00 5.70E+08 SR-89 1.26E+10 O.OOE+00 3.62E+08 O.OOE+00 O.00E+OO O.OOE+00 2.59E+08 SR-90 1.22E+11 O.OOE+00 3.10E+10 0.00E+OO O.00E+00 O.OOE+00 1.52E+09 Y-91 7.34E+04 O.OOE+00 1.95E+03 O.OOE+0O O.OOE+OO O.OOE+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.18E+03 O.OOE+OO 1.79E+03 O.OOE+OO 8.27E+05 NB-95 5.94E+05 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.0OE+OO 2.07E+08 RU-103 8.68E+03 O.OOE+00 2.90E+03 O.OOE+00 1.81E+04 O.OOE+00 1.06E+05 RU-106 1.91E+05 O.OOE+00 2.38E+04 O.OOE+00 2.25E+05 O.OOE+OO 1.45E+06 AG-110M 3.86E+08 2.82E+08 1.87E+08 O.OOE+00 4.03E+08 O.OOE+00 1.46E+10 TE-125H 1.51E+08 5.05E+07 2.04E+07 5.08E+07 O.OOE+00 O.OOE+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+00 1.70E+08 TE-129H 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 O.OOE+00 3.33E+08 I-131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 0.0OE+OO 1.15E+08 I-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 O.OOE+00 8.96E+06 CS-134 3.65E+10 6.81E+10 6.88E+09 O.OOE+00 1.75E+10 7.19E+09 1.85E+08 CS-136 1.98E+09 5.83E+09 2.18E+09 O.00E+00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.89E+08 BA-140 2.42E+08 2.42E+05 1.25E+07 O.OOE+OO 5.75E+04 1.49E+05 5.94E+07 CE-141 4.34E+04 2.65E+04 3.12E+03 0.00E+00 8.17E+03 0.0OE+OO 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 O.OOE+OO 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+00 2.07E+02 O.OOE+00 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 O.OOE+00 3.50E+02 O.OOE+00 5.75E+05 MN PEAK

...... -.... 1---.-.----.----

AND 2...... PR.2-33...............93.

COMANCHE PEAK - LUS 1 AND 2 PR 233Rev 8 2-3301/93 PART

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT I ORGAN DOSE FACTORS NUCLIDE I--------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 P-32 4.63E+09 2.88E+08 1.79E+08 O.OOE+00 O.OOE+00 O.OOE+00 5.21E+08 CR-51 O.OOE+00 O.OOE+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN-54 O.OOE+00 9.18E+06 1.75E+06 O.OOE+00 2.73E+06 O.OOE+00 2.81E+07 FE-55 2.93E+08 2.03E+08 4.73E+07 O.OOE+00 O.OOE+00 1.13E+08 1.16E+08 FE-59 2.66E+08 6.25E+08 2.39E+08 O.OOE+00 O.OOE+00 1.75E+08 2.08E+09 CO-58 O.OOE+00 1.82E+07 4.09E+07 O.OOE+OO O.OOE+00 O.OOE+00 3.70E+08 CO-60 O.OOE+00 7.52E+07 1.66E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.41E+09 NI-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+OO O.OOE+00 O.OOE+00 2.73E+08 ZN-65--- 3.56E+08 1.13E+09 5.12E+08 O.OOE+OO 7.57E+08 O.OOE+00 7.13E+08 RB-86 O.OOE+O0 4.87E+08 2.27E+08 O.OOE+00 O.OOE+00 O.OOE+00 9.59E+07 SR-89 3.02E+08 O.OOE+00 8.66E+06 O.OOE+00 0.00E+00 O.OOE+00 4.84E+07 SR-90 1.24E+10 O.OOE+00 3.05E+09 O.OOE+00 O.OOE+00 O.OOE+00 3.60E+08 Y-91 1.13E+06 O.OOE+00 3.03E+04 O.OOE+OO O.OOE+00 O.OOE+00 6.24E+08 ZR-95 1.87E+06 6.01E+05 4.07E+05 O.OOE+00 9.43E+05 O.OOE+00 1.90E+09 NB-95 2.30E+06 1.28E+06 6.87E+05 O.OOE+00 1.26E+06 O.OOE+00 7.76E+09 RU-103 1.05E+08 O.OOE+00 4.53E+07 O.OOE+O0 4.02E+08 O.OOE+00 1.23E+10 RU-106 2.80E+09 O.OOE+00 3.54E+08 O.OOE+00 5.41E+09 O.OOE+00 1.81E+ll AG-llOM 6.68E+06 6.18E+06 3.67E+06 O.OOE+O0 1.22E+07 O.OOE+00 2.52E+09 TE-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 O.OOE+00 1.43E+09 TE-127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 O.OOE+00 3.74E+09 TE-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 O.OOE+00 5.71E+09 I-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 O.OOE+00 4.06E+06 I-133 3.68E-01 6.41E-01 1.95E-01 9.42E+01 1.12E+00 O.OOE+00 5.76E-01 CS-134 6.58E+08 1.57E+09 1.28E+09 O.OOE+O0 5.07E+08 1.68E+08 2.74E+07 CS-136 1.21E+07 4.78E+07 3.4$E+07 O.OOE+00 2.66E+07 3.65E+06 5.43E+06 CS-137 8.72E+08 1.19E+09 7.82E+08 O.OOE+O0 4.05E+08 1.35E+08 2.31E+07 BA-140 2.90E+07 3.64E+04 1.90E+06 O.OOE+O0 1.24E+04 2.08E+04 5.96E+07 CE-141 1.41E+04 9.51E+03 1.08E+03 O.OOE+00 4.42E+03 O.OOE+00 3.64E+07 CE-144 1.46E+06 6.10E+05 7.83E+04 O.OOE+00 3.62E+05 O.OOE+OO 4.93E+08 PR-143 2.09E+04 8.40E+03 1.04E+03 O.OOE+O0 4.85E+03 O.OOE+00 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 O.OOE+O0 4.78E+03 O.OOE+00 3.93E+07 COMANCHE PEAK - UNITS 1 AND 2 Rev 8 PART U 2-34 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 P-32 3.91E+09 2.42E+08 1.52E+08 O.OOE+00 O.OOE+00 O.OOE+00 3.29E+08 CR-51 O.OOE+00 O.OOE+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 MN-54 O.OOE+00 7.OOE+06 1.39E+06 O.OOE+00 2.09E+06 O.OOE+00 1.44E+07 FE-55 2.38E+08 1.69E+08 3.94E+07 O.OOE+00 O.OOE+00 1.07E+08 7.31E+07 FE-59 2.12E+08 4.95E+08 1.91E+08 O.OOE+00 O.OOE+00 1.56E+08 1.17E+09 CO-58 O.OOE+00 1.40E+07 3.24E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.94E+08 CO-60 O.OOE+00 5.83E+07 1.31E+08 O.OOE+00 O.OOE+00 O.OOE+00 7.60E+08 NI-63 1.52E+10 1.07E+09 5.15E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.71E+08 ZN-65_ 2.50E+08 8.68E+08 4.05E+08 O.OOE+00 5.56E+08 O.OOE+00 3.68E+08 RB-86 O.OOE+00 4.06E+08 1.91E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.OOE+07 SR-89 2.55E+08 O.OOE+00 7.29E+06 O.OOE+00 O.OOE+OO O.OOE+OO 3.03E+07 SR-90 8.04E+09 O.OOE+OO 1.99E+09 O.OOE+00 O.OOE+00 O.00E+00 2.26E+08 Y-91 9.54E+05 O.OOE+00 2.56E+04 O.OOE+00 O.OOE+00 O.OOE+00 3.91E+08 ZR-95 1.50E+06 4.73E+05 3.25E+05 O.OOE+00 6.95E+05 O.OOE+00 1.09E+09 NB-95 1.79E+06 9.95E+05 5.48E+05 O.OOE+00 9.64E+05 O.OOE+00 4.25E+09 RU-103 8.56E+07 O.OOE+00 3.66E+07 O.OOE+00 3.02E+08 O.OOE+00 7.15E+09 RU-106 2.36E+09 O.OOE+00 2.97E+08 O.OOE+O0I 4.54E+09 0.OOE+00 1.13E+ll AG-llOM 5.06E+06 4.78E+06 2.91E+06 0.OOE+00I 9.13E+06 0.OOE+00 1.34E+09 TE-125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07I 0.O0E+O0 0.00E+00 8.94E+08 TE-127H 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 O.OOE+00 2.35E+09 TE-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 O.OOE+00 3.56E+09 I-131 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 O.OOE+00 2.47E+06 I-133 3.08E-O1 5.22E-01 1.59E-O1 7.29E+01 9.16E-01 O.OOE+00 3.95E-01 CS-134 5.23E+08 1.23E+09 5.71E+08 O.00E+OO 3.91E+08 1.49E+08 1.53E+07 CS-136 9.43E+06 3.71E+07 2.49E+07 O.OOE+OO 2.02E+07 3.18E+06 2.99E+06 CS-137 7.24E+08 9.63E+08 3.35E+08 O.OOE+00 3.28E+08 1.27E+08 1.37E+07 BA-140 2.39E+07 2.93E+04 1.54E+06 O.00E+OO 9.94E+03 1.97E+04 3.69E+07 CE-141 1.18E+04 7.87E+03 9.05E+02 O.OOE+00 3.71E+03 O.OOE+00 2.25E+07 CE-144 1.23E+06 5.08E+05 6.60E+04 O.OOE+00 3.03E+05 O.OOE+00 3.09E+08 PR-143 1.76E+04 7.03E+03 8.76E+02 O.OOE+00 4.08E+03 O.OOE+00 5.79E+07 ND-147 6.23E+03 6.78E+03 4.06E+02 O.OOE+00 3.98E+03 O.OOE+00 2.44E+07 COMANCHE PEAK - UNITS 1 AND 2 Rev 8 PART 2-35 R 01/93

TABLE 24 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT I ORGAN DOSE FACTORS NUCLIDE I------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 P-32 7.38E+09 3.45E+08 2.85E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.04E+08 CR-51 O.OOE+OO O.OOE+OO 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 O.OOE+OO 8.01E+06 2.13E+06 O.OOE+OO 2.25E+06 O.OOE+OO 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 O.OOE+OO O.OOE+OO 1.37E+08 4.49E+07 FE-59 3.77E+08 6.10E+08 3.04E+08 O.OOE+OO O.OOE+OO 1.77E+08 6.35E+08 CO-58 O.OOE+OO 1.64E+07 5.03E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.58E+07 CO-60 O.OOE+OO 6.93E+07 2.04E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.84E+08 NI-63 2.91E+10 1.56E+09 9.91E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.05E+08 ZN-65,-- 3.76E+08 l.OOE+09 6.22E+08 O.OOE+OO 6.31E+08 O.OOE+OO 1.76E+08 RB-86 O.OOE+OO 5.76E+08 3.54E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.71E+07 SR-89 4.82E+08 O.OOE+OO 1.38E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.87E+07 SR-90 1.04E+10 O.OOE+OO 2.64E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+08 Y-91 1.80E+06 O.OOE+OO 4.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+08 ZR-95 2.66E+06 5.86E+05 5.21E+05 O.OOE+OO 8.38E+05 O.OOE+OO 6.11E+08 NB-95 3.10E+06 1.21E+06 8.63E+05 O.OOE+OO 1.13E+06 O.OOE+OO 2.23E+09 RU-103 1.55E+08 O.OOE+OO 5.96E+07 O.OOE+OO 3.90E+08 O.OOE+OO 4.01E+09 RU-106 4.44E+09 O.OOE+OO 5.54E+08 O.OOE+OO 6.OOE+09 O.OOE+OO 6.91E+10 AG-llOM 8.39E+06 5.67E+06 4.53E+06 O.OOE+OO 1.06E+07 O.OOE+OO 6.74E+08 TE-125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 O.OOE+OO O.OOE+OO 5.49E+08 TE-127M 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 O.OOE+OO 1.44E+09 TE-129M 1.79E+09 5.OOE+08 2.78E+08 5.77E+08 5.26E+09 O.OOE+OO 2.18E+09 I-131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 O.OOE+OO 1.48E+06 I-133 5.72E-01 7.08E-01 2.68E-01 1.31E+02 1.18E+OO O.OOE+OO 2.85E-O1 CS-134 9.23E+08 1.51E+09 3.19E+08 O.OOE+OC' 4.69E+08 1.68E+08 8.16E+06 CS-136 1.63E+07 4.48E+07 2.90E+07 O.OOE+OO 2.39E+07 3.56E+06 1.57E+06 CS-137 1.33E+09 1.28E+09 1.89E+08 O.OOE+OO 4.16E+08 1.50E+08 8.OOE+06 BA-140 4.42E+07 3.87E+04 2.58E+06 O.OOE+OO 1.26E+04 2.31E+04 2.24E+07 CE-141 2.22E+04 1.11E+04 1.65E+03 O.OOE+OO 4.86E+03 O.OOE+OO 1.38E+07 CE-144 2.32E+06 7.26E+05 1.24E+05 O.OOE+OO 4.02E+05 O.OOE+OO 1.89E+08 PR-143 3.33E+04 1.OOE+04 1.65E+03 O.OOE+OO 5.42E+03 O.OOE+OO 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 O.OOE+OO 5.20E+03 O.OOE+OO 1.50E+07 Rev 8 COMANCHE PEAK - UNTS 1 AND 2 PART I 2-36 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

.-3 O.OOE+OO O.........OOE+OO......

O.OOE+O O.OOEOO .OE .00E-- OO-.O.OOE+OO--.

H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO P-32 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CR-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO HN-54 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-60 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

........ ....... ............ O.O.E....O.....E...

NI-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ZN-65_- O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

..- .. . O......... O........

ZR-95 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NB-95 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-106 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OE O.OOE+00 AG-llOH O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-125M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-127M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+00 TE-129H O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-131 O.OOE+OO O.OOE+OO O.OOE+OO O.O0OE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

0. OOE+00 O.OOE+OO CS-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+O. O.OOE+0O O. OOE+00 CS-136 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O. OOE+00 O.OOE+OO O.OOE+OO CS-137 O.OOE+00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-140 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CE-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

...................................... O.OOE+OO O...........OE... O.OOE+OO...._

CE-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PR-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rev 8 COMANCHE PEAK - UNITS I AND 2 PART II 2-37 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 P-32 2.05E+10 1.27E+09 7.92E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E+09 CR-51 O.OOE+OO O.OOE+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN-54 O.OOE+OO 1.01E+06 1.93E+05 O.OOE+OO 3.01E+05 O.OOE+OO 3.10E+06 FE-55 3.27E+05 2.26E+05 5.26E+04 O.OOE+OO O.OOE+OO 1.26E+05 1.30E+05 FE-59 3.87E+05 9 .09E+05 3.48E+05 O.OOE+OO O.OOE+OO 2.54E+05 3.03E+06 CO-58 O.OOE+OO 5.66E+05 1.27E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+07 CO-60 O.OOE+OO 1.97E+06 4.35E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+07 NI-63 8.08E+08 5.60E+07 2.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+07 ZN 1.65E+08 5.24E+08 2.37E+08 O.OOE+OO 3.51E+08 O.OOE+OO 3.30E+08 RB-86 O.OOE+OO 3.12E+08 1.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.14E+07 SR-89 3.05E+09 O.OOE+OO 8.76E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.89E+08 SR-90 9.84E+10 O.OOE+OO 2.41E+10 O.OOE+OO O.OOE+OO O.OOE+OO 2.84E+09 Y-91 1.03E+03 O.OOE+OO 2.76E+O1 O.OOE+OO O.OOE+OO O.OOE+OO 5.68E+05 ZR-95 1.13E+02 3.63E+O1 2.46E+O1 O.OOE+OO 5.70E+O1 O.OOE+OO 1.15E+05 NB-95 9.92E+03 5.52E+03 2.97E+03 O.OOE+OO 5.45E+03 O.OOE+OO 3.35E+07 RU-103 1.22E+02 O.OOE+OO 5.27E+O1 O.OOE+OO 4.67E+02 O.OOE+OO 1.43E+04 RU-106 2.45E+03 O.OOE+OO 3.10E+02 O.OOE+OO 4.73E+03 O.OOE+OO 1.59E+05 AG-llOM 6.99E+06 6.47E+06 3.84E+06 O.OOE+OO 1.27E+07 O.OOE+OO 2.64E+09 TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 O.OOE+OO 7.81E+06 TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 O.OOE+OO 1.84E+07 TE-129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 O.OOE+OO 3.64E+07 I-131 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 O.OOE+OO 1.34E+08 I-133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41E+07 O.OOE+OO 7.28E+06 CS-134 1.70E+10 4.04E+10 3.30E+10 O.OOE+OO 1.31E+10 4.34E+09 7.07E+08 CS-136 7.92E+08 3.13E+09 2.25E+09 O.OOE+OO 1.74E+09 2.38E+08 3.55E+08 CS-137 2.22E+10 3.03E+10 1.99E+10 O.OOE+OO 1.03E+10 3.42E+09 5.87E+08 BA-140 3.24E+06 4.07E+03 2.12E+05 O.OOE+OO 1.38E+03 2.33E+03 6.67E+06 CE-141 5.82E+02 3.94E+02 4.47E+O1 O.OOE+OO 1.83E+02 O.OOE+OO 1.51E+06 CE-144 4.30E+04 1.80E+04 2.31E+03 O.OOE+OO 1.07E+04 O.OOE+OO 1.45E+07 PR-143 l.90E+01 7.60E+00 9.40E-O1 O.OOE+OO 4.39E+OO O.OOE+OO 8.30E+04 ND-147 1.13E+01 1.31E+01 7.82E-O1 O.OOE+00 7.65E+OO O.OOE+OO 6.28E+04 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART 112-38 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK I ORGAN DOSE FACTORS NUCLIDE ---------------------------------------------------------------------

BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 P-32 3.78E+10 2.34E+09 1.46E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.18E+09 CR-51 O.OOE+OO O.OOE+OO 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.O1E+06 MN-54 O.OOE+OO 1.68E+06 3.34E+05 O.OOE+00 5.02E+05 O.OOE+0O 3.45E+06 FE-55 5.79E+05 4.11E+05 9.58E+04 O.OOE+0 O.OOE+00 2.61E+05 1.78E+05 FE-59 6.74E+05 1.57E+06 6.08E+05 O.OOE+00 O.OOE+00 4.96E+05 3.72E+06 CO-58 O.OOE+00 9.53E+05 2.20E+06 O.OOE+00 O.OOE+00 O.OOE+00 1.31E+07 CO-60 O.OOE+00 3.34E+06 7.52E+06 O.OOE+00 O.OOE+00 0.OOE+00 4.35E+07 NI-63 1.42E+09 1.OOE+08 4.81E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.60E+07 ZN-65 2.53E+08 8.78E+08 4.10E+08 O.OOE+00 5.62E+08 O.OOE+00 3.72E+08 RB-86 O.OOE+00 5.67E+08 2.67E+08 O.OOE+O0 O.OOE+00 O.OOE+00 8.40E+07 SR-89 5.62E+09 O.OOE+00 1.61E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.69E+08 SR-90 1.39E+ll O.OOE+00 3.43E+10 O.OOE+00 O.OOE+00 O.OOE+O0 3.90E+09 Y-91 1.90E+03 O.OOE+00 5.09E+01 O.OOE+00 O.OOE+00 O.OOE+00 7.78E+05 ZR-95 1.98E+02 6.25E+01 4.30E+01 O.OOE+00 9.18E+01 O.OOE+00 1.44E+05 NB-95 1.69E+04 9.38E+03 5.16E+03 O.OOE+00 9.09E+03 O.OOE+OO 4.01E+07 RU-103 2.17E+02 O.OOE+00 9.29E+O1 O.OOE+00 7.66E+02 O.OOE+00 1.82E+04 RU-106 4.50E+03 0.00E+00 5.68E+02 O.OOE+00 AG-llOM 8.69E+03 O.OOE+0O 2.16E+05 1.16E+07 1.09E+07 6.65E+06 O.OOE+00 2.09E+07 TE-125M 3.61E+06 O.OOE+00 3.07E+09 1.30E+06 4.82E+05 1.01E+06 O.OOE+00 O.OOE+00 1.06E+07 TE-127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 O.OOE+00 2.52E+07 TE-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+00 4.96E+07 I-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 O.OOE+0O 1.79E+08 I-133 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 O.OOE+00 1.09E+07 CS-134 2.95E+10 6.93E+10 3.22E+10 O.OOE+0O 2.20E+10 8.41E+09 8.62E+08 CS-136 1.35E+09 5.30E+09 3.56E+09 O.OOE+00 2.89E+09 4.55E+08 4.27E+08 CS-137 4.02E+10 5.34E+10 1.86E+10 O.OOE+00 1.82E+10 BA-140 7.07E+09 7.60E+08 5.84E+06 7.16E+03 3.76E+05 0.OOE+00 2.43E+03 4.81E+03 9.O1E+06 CE-141 1.07E+03 7.12E+02 8.18E+01 O.OOE+OO 3.35E+02 O.OOE+0O 2.04E+06 CE-144 7.90E+04 3.27E+04 4.25E+03 O.OOE+OO 1.95E+04 O.OOE+00 1.99E+07 PR-143 3.48E+01 1.39E+01 1.73E+00 O.OOE+00 8.08E+00 O.OOE+00 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+00 O.OOE+00 1.39E+01 O.OOE+00 8.54E+04 COMANCHE PEAK - UNITS 1 AND 2 Rev 8 PART 112-39 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS-GOAT-HILK I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 P-32 9.32E+10 4.36E+09 3.59E+09 O.OOE+OO O.OOE+00 O.OOE+00 2.58E+09 CR- 51 O.OOE+00 O.OOE+O 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 O.OOE+O0 2.52E+O 6.71E+05 O.OOE+00 7.06E+05 O.OOE+00 2.11E+06 FE-55 1.45E+06 7.71E+O 2.39E+05 O.OOE+00 O.OOE+00 4.36E+05 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 O.00E+00 O.OOE+00 7.34E+05 2.64E+06 CO-58 O.OOE+00 1.46E+06 4.46E+06 O.OOE+00 O.OOE+00 O.OOE+00 8.49E+06 CO-60 O.OOE+00 5.18E+06 1.53E+07 O.OOE+00 O.OOE+O0 O.OOE+00 2.87E+07 NI-63 3.56E+09 1.91E+08 1.21E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.28E+07 ZN-65, 4.96E+08 1.32E+09 8.22E+08 O.OOE+O0 8.33E+08 O.OOE+00 2.32E+08 RB-86 O.OOE+00 1.05E+09 6.47E+08 O.OOE+00 O.OOE+00 O.OOE+O0 6.77E+07 SR-89 1.39E+1O O.OOE+00 3.97E+08 O.OOE+OO O.OOE+O0 O.OOE+00 5.39E+08 SR-90 2.35E+11 O.OOE+00 5.95E+10 O.OOE+OO O.OOE+O0 O.OOE+00 3.16E+09 Y-91 4.69E+03 O.OOE+00 1.25E+02 O.OOE+OO O.OOE+00 O.OOE+00 6.24E+05 ZR-95 4.60E+02 1.01E+02 9.OOE+O1 O.OOE+00 1.45E+02 O.OOE+00 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 O.OOE+OO 1.40E+04 O.OOE+00 2.75E+07 RU-103 5.14E+02 O.OOE+00 1.98E+02 O.OOE+00 1.29E+03 O.OOE+00 1.33E+04 RU-106 1.11E+04 O.OOE+00 1.38E+03 O.00E+00 1.50E+04 0.00E+00 1.73E+05 AG-110M 2.51E+07 1.69E+07 1.35E+07 O.OOE+00 3.15E+07 O.OOE+00 2.01E+09 TE-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 O.OOE+OO O.OOE+00 8.55E+06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+00 2.02E+07 TE-129M 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56E+07 O.OOE+00 3.97E+07 1-131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 O.OOE+00 1.40E+08 I-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+00 1.03E+07 CS-134 6.80E+10 1.12E+11 2.35E+10 O.OOE+O0 3.46E+10 1.24E+10 6.01E+08 CS-136 3.04E+09 8.36E+09 5.41E+09 O.OOE+00 4.45E+09 6.64E+08 2.94E+08 CS-137 9.68E+10 9.26E+10 1.37E+10 O.OOE+O0 3.02E+10 1.09E+10 5.80E+08 BA-140 1.41E+07 1.24E+04 8.23E+05 O.OOE+00 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31E+03 1.95E+02 O.OOE+00 5.74E+02 O.OOE+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+04 O.OOE+00 3.38E+04 O.OOE+00 1.59E+07 PR-143 8.61E+01 2.59E+01 4.27E+00 O.OOE+00 1.40E+O1 O.OOE+OO 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 O.OOE+00 2.37E+01 O.OOE+00 6.85E+04 CO MA NCHE. PE AK.-. U MTS 1. A ND 2P A RT 2- 400/..

. . . . . . . . .9 COMANCHE PEAK - UNITS 1 AND 2 PR12-0Rev 8

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK I ORGAN DOSE FACTORS NUCLIDE j----------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+OO 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 P-32 1.92E+11 1.13E+10 7.44E+09 O.OOE+OO O.00E+OO O.OOE+OO 2.60E+09 CR-51 0.OOE+OO 0.OOE+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 MN-54 0.O0E+OO 4.68E+06 1.06E+06 O.OOE+00 1.04E+06 0.OOE+OO 1.72E+06 FE-55 1.76E+06 1.14E-.06 3.03E+05 O.OOE+00 O.OOE+00 5.55E+05 1.44E+05 FE-59 2.92E+06 S.IOE+06 2.01E+06 O.OOE+00 O.OOE+00 1.51E+06 2.44E+06 CO-58 O.OOE+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 CO-60 O.OOE+00 1.06E+07 2.50E+07 O.OOE+00 O.OOE+00 0.OOE+OO 2.52E+07 NI-63 4.19E+09 2.59E+08 1 .46E+08 O.OOE+00 O.O0E+OO O.OOE+00 1.29E+07 ZN - 6.67E+08 2.29E4-09 1.05E+09 O.OOE+00 1.11E+09 O.OOE+00 1.93E+09 RB-86 O.OOE+00 2.67E+09 1.32E+09 O.OOE+00 O.OOE+00 O.OOE+00 6.83E+07 SR-89 2.65E+1O 0.0OE+OO 7.59E+08 O.OOE+00 O.OOE+00 O.OOE+00 5.44E+08 SR-90 2.55E+ll O.0OE+OO 6.50E+10 O.OOE+00 O.OOE+OO O.OOE+00 3.19E+09 Y-91 8.80E+03 O.OOE+00 2.34E+02 O.OOE+00 O.OOE+00 O.OOE+00 6.31E+05 ZR-95 8.17E+02 1.99E+02 1.41E+02 O.OOE+00 2.15E+02 O.OOE+OO 9.91E+04 NB-95 7.13E+04 2.93E+04 1.70E+04 O.OOE+OO 2.10E+04 O.OOE+00 2.48E+07 RU-103 1.04E+03 O.OOE+00 3.48E+02 O.OOE+00 2.17E+03 O.OOE+00 1.27E+04 RU-106 2.28E+04 O.OOE+00 2.85E+03 O.OOE+00 2.70E+04 O.OOE+00 1.73E+05 AG-110M 4.63E+07 3.38E+07 2.24E+07 O.OOE+00 4.84E+07 O.OOE+00 1.75E+09 TE-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 O.OOE+00 O.OOE+00 8.62E+06 TE-127M 5.06E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.OOE+OO 2.0E+07 TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 O.OOE+00 3.99E+07 1-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 O.OOE+00 1.37E+08 I-133 4.36E+07 6.35E+07. 1.86E+07 1.15E+10 7.46E+07 O.OOE+00 1.07E+07 CS-134 1.09E+ll 2.04E+11 2.06E+10 O.OOE+00 5.26E+10 2.15E+10 5.55E+08 CS-136 5.94E+09 1.75E+10 6.52E+09 O.OOE+00 6.96E+09 1.42E+09 2.65E+08 CS-137 1.54E+ll 1.81E+11 1.28E+10 O.OOE+00 4.85E+10 1.96E+10 5.65E+08 BA-140 2.90E+07 2.90E+04 1.50E+06 0.0OE+O0 6.89E+03 1.78E+04 7.13E+06 CE-141 5.21E+03 3.18E+03 3.74E+02 0.0OE+O0 9.79E+02 O.OOE+00 1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 O.OOE+00 4.62E+04 0.OOE+O0 1.60E+07 PR-143 1.78E+02 6.66E+01 8.83E+00 O.OOE+00 2.48E+01 O.OOE+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.OOE+O0 4.19E+01 O.00E+00 6.89E+04 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 01/93 PART n2-41

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: VEGETATION I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 P-32 1.40 E+09 8.69E+07 5.40E+07 0.OOE+O0 O.OOE+OO O.OOE+OO 1.57E+08 CR-51 0 .00 E+OO O.OOE+OO 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN-54 0.00 E+O0 3.13E+08 5.97E+07 O.OOE+00 9.31E+07 O.OOE+0O 9.58E+08 FE-55 2.10 E+08 1.45E+08 3.38E+07 O.OOE+O0 O.OOE+OO 8.08E+07 8.31E+07 FE-59 1.26 E+08 2.97E+08 1.14E+08 O.OOE+OO O.OOE+OO 8.29E+07 9.89E+08 CO-58 0.00 E+OO 3.07E+07 6.89E+07 O.OOE+OO O.OOE+OO O.OOE+O0 6.23E+08 CO-60 0.00 E+OO 1.67E+08 3.69E+08 O.OOE+O0 O.OOE+OO O.OOE+0O 3.14E+09 NI-63 1.04'E+10 7.21E+08 3.49E+08 O.OOE+O0 O.OOE+OO O.OOE+O0 1.50E+08 ZN 3.17 E+08 1.O1E+09 4.56E+08 O.OOE+O0 6.75E+08 O.OOE+OO 6.36E+08 RB-86 0.00:E+O0 2.19E+08 1.02E+08 O.OOE+O0 O.OOE+O0 O.OOE+OO 4.32E+07 SR-89 9.981E+09 O.OOE+O0 2.86E+08 O.OOE+00 O.OOE+O0 1.60E+09 SR-90 6.051E+11 O.OOE+O0 1.48E+ll O.OOE+O0 O.OOE+O0 O.OOE+O0 1.75E+10 Y-91 5.12]E+06 O.OOE+OO 1.37E+05 O.OOE+O0 O.OOE+OO O.OOE+0O 2.82E+09 ZR-95 1.17E+06 3.77E+05 2.55E+05 O.OOE+O0 5.91E+05 O.OOE+OO 1.19E+09 NB-95 1.42E+05 7.92E+04 4.26E+04 O.OOE+O0 7.83E+04 O.OOE+OO 4.81E+08 RU-103 4.77E+06 O.OOE+O0 2.06E+06 O.OOE+O0 1.82E+07 O.OOE+00 5.57E+08 RU-106 1.93E+08 O.OOE+O0 2.44E+07 O.OOE+O0 3.72E+08 O.OOE+OO 1.25E+10 AG-llOM 1.05E+07 9.75E+06 5.79E+06 O.OOE+00 1.92E+07 O.OOE+0O 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 O.OOE+0O 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 O.OOE+0O 1.17E+09 TE-129M 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 O.OOE+0O 1.26E+09 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 O.OOE+0O 3.05E+07 I-133 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 O.OOE+OO 3.26E+06 CS-134 4.67E+09 1.11E+10 9.08E+09 O.OOE+O0 3.59E+09 1.19E+09 1.94E+08 CS-136 4.28E+07 1.69E+08 1.22E+08 O.OOE+O0 9.41E+07 1.29E+07 1.92E+07 CS-137 6.36E+09 8.70E+09 5.70E+09 0.OOE+OO 2.95E+09 9.81E+08 1.68E+08 BA-140 1.29E+08 1.62E+05 8.47E+06 O.OOE+O0 5.52E+04 9.29E+04 2.66E+08 CE-141 1.97E+05 1.33E+05 1.51E+04 O.OOE+O0 6.20E+04 O.OOE+OO 5.10E+08 CE-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+OO 8.16E+06 O.OOE+O0 1.11E+10 PR-143 6.25E+04 2.51E+04 3.10E+03 O.OOE+O0 1.45E+04 O.OOE+0O 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31E+03 O.OOE+OO 2.25E+04 O.OOE+OO 1.85E+08 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART N2-42 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: VEGETATION I ORGAN DOSE FACTORS NUCLIDE -------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 P-32 1.60E+09 9.91E+07 6.20E+07 O.OOE+00 O.OOE+OO O.OOE+00 1.34E+08 CR-51 O.OOE+00 O.OOE+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 O.OOE+00 4.54E+08 9.01E+07 O.OOE+00 1.36E+08 O.OOE+00 FE-55 9.32E+08 3.26E+08 2.31E+08 5.39E+07 O.OOE+00 0.OOE+00 1.47E+08 1.OOE+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.OOE+00 O.00E+00 1.32E+08 9.91E+08 CO-58 O.OOE+00 4.36E+07 1.01E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.01E+08 CO-60 O.OOE+00 2.49E+08 5.60E+08 O.OOE+00 0.OOE+00 O.OOE+00 3.24E+09 1O.L. l.blE+lU 1.13E+09 5.45E+08 o.(00E 7+00 O.OOE+00 O.OOE+00 1.81E+08 ZN-65 4.24E+08 1.47E+09 6.86E+08 O.C0OE +00 9.42E+08 RB-86-- 0.OOE+00 6.23E+08 O.OOE+00 2.73E+08 1.28E+08 0.C0OE 7+00 0. OOE+00 O.OOE+00 4.04E+07 SR-89 SR-90 1.52E+10 7.51E+11 0.OOE+00 4.34E+08 O.C O.OOE+00 1.85E+11 O.C0OE +00 IOE+00 O.OOE+00

.I 0.OOE+00 1.80E+09 O.OOE+00 0.OOE+00 2.11E+10 Y-91 7.84E+06 O.OOE+00 2.10E+05 0.00OE +00 O.OOE+00

- - - - - - - O.OOE+00 3.22E+09 10-7i I./ZL+Vb 5.43E+U5 3.73E+05 O.OOE+00 7.98E+05 O.OOE+00 1.25E+09 NB-95 1.92E+05 1.07E+05 5.87E+04 O.OOE+00 1.03E+05 RU-103 0.OOE+00 4.56E+08 6.82E+06 O.OOE+00 2.92E+06 O.OOE+00 2.41E+07 0.OOE+00 5.70E+08 RU-106 3.09E+08 0.OOE+00 3.90E+07 O.OOE+00 5.97E+08 AG-110M 0.OOE+00 1.48E+10 1.52E+07 1.43E+07 8.72E+06 0.OOE+00 2.74E+07 TE-125M 0.OOE+00 4.03E+09 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.OOE+00 0.OOE+00 4.37E+08 TE-127M 5.52E+08 1.96E+08 6.56E+07 ..00E+00 1.37E+09 1.31E+08 2.24E+09 TE-129M 3.61E+08 1.34E+08 5.72E+07 O.OOE+00 1.37E+09 1.17E+08 1.51E+09 I-131 7.69E+07 1.08E+08 5.78E+07 0.OOE+00 1.36E+09 3.14E+10 1.85E+08

_.-_E_- - -

I-133 1.94E+06 3.29E+06 1.OOE+06 4.59E+08 5.77E+06 O.OOE+00 2.49E+06 CS-134 7.10E+09 1.67E+10 7.75E+09 O.OOE+00 5.31E+09 2.03E+09 2.08E+08 CS-136 4.39E+07 1.73E+08 1.16E+08 O.OOE+00 9.41E+07 1.48E+07 1.39E+07 CS-137 1.01E+10 1.35E+10 4.69E+09 0.OOE+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.39E+08 1.71E+05 8.97E+06 0.OOE+00 5.78E+04 1.15E+05 2.15E+08 CE-141 2.83E+05 1.89E+05 2.17E+04 0.OOE+00 8.90E+04 O.OOE+0O

.....-.--. 5.41E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 O.OOE+00 1.30E+07 0.OOE+00 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E+03 O.OOE+00 1.62E+04 O.OOE+00 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 O.OOE+00 2.31E+04 0.OOE+00 1.42E+08 COMANCHE PEAK - UNITS 1 AND 2 Rev 8 PART 112-43 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: VEGETATION I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 P-32 3.35E+09 1.57E+08 1.29E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.25E+07 CR-51 O.OOE+OO O.OOE+OO 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 O.OOE+OO 6.65E+08 1.77E+08 O.OOE+OO 1.86E+08 O.OOE+OO 5.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 O.OOE+OO O.OOE+OO 2.40E+08 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21E+08 O.OOE+OO O.OOE+OO 1.87E+08 6.71E+08 CO-58 O.OOE+OO 6.44E+07 1.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+08 CO-60 O.OOE+OO 3.78E+08 1.12E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34E+09 O.OOE+OO O.OOE+OO O.OOE+00 1.42E+08 ZN-6 - 8.12E+08 2.16E+09 1.35E+09 O.OOE+OO 1.36E+09 0.OOE+00 3.80E+08 RB-86 O.OOE+OO 4.51E+08 2.77E+08 O.OOE+OO O.OOE+OO O.OOE+00 2.90E+07 SR-89 3.60E+10 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+09 SR-90 1.24E+12 O.OOE+OO 3.15E+ll O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 Y-91 1.87E+07 O.OOE+OO 4.99E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.49E+09 ZR-95 3.86E+06 8.48E+O5 7.55E+05 O.OOE+OO 1.21E+06 O.OOE+OO 8.85E+08 NB-95 4.11E+05 1.60E+05 1.14E+05 O.OOE+O0 1.50E+05 O.OOE+0O 2.96E+08 RU-103 1.53E+07 O.OOE+OO 5.90E+06 O.OOE+OO 3.86E+07 O.OOE+OO 3.97E+08 RU-106 7.45E+08 O.OOE+OO 9.30E+07 O.OOE+OO 1.O1E+09 O.OOE+OO 1.16E+10 AG-110 3.21E+07 2.17E+07 1.73E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.58E+09 TE-125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 O.OOE+OO O.OOE+0O 3.38E+08 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 O.OOE+OO 1.07E+09 TE-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 O.OOE+OO 1.02E+09 I-131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 O.OOE+OO 1.28E+07 I-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 O.OOE+OO 1.76E+06 CS-134 1.60E+10 2.63E+10 5.55E+09 O.OOE+OO 8.15E+09 2.93E+09 1.42E+08 CS-136 8.28E+07 2.28E+08 1.47E+08 O.OOE+OO 1.21E+08 1.81E+07 8.OOE+06 CS-137 2.39E+10 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 1.43E+08 BA-140 2.79E+08 2.44E+05 1.63E+07 O.OOE+OO 7.96E+04 1.46E+05 1.41E+08 CE-141 6.57E+05 3.28E+05 4.86E+04 O.OOE+OO 1.44E+05 O.OOE+OO 4.09E+08 CE-144 1.27E+08 3.99E+07 6.79E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21E+03 O.OOE+OO 2.36E+04 O.OOE+OO 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 O.OOE+OO 3.18E+04 O.OOE+OO 9.18E+07 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART 112-44 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: VEGETATION I ORGAN DOSE FACTORS NUCLIDE I-------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 P-32 0.00 E+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00

. O. E. . O O... OOE+00 CR-51 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 MN-54 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 10.00E+00 0.00E+00 FE-55 0.OOE+00 O.OOE+00 0.OOE+O0 0.OOE+00 0.00E+OO O.00E+OO 0.OOE+00 O.OOE+.

FE-59 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+OO CO-58 O.OOE+00 0.OOE+OO O.OOE+0O O.OOE+00 0.OOE+00 O.OOE+00 CO-60 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 ....................

NI-63 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 ZN-65.- 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 RB-86 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 SR-89 0.OOE+00 O. OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 SR-90 0.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 0.OOE+OO 0.00E+00 0.00E+00 Y-91 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 O.00E+00 0.00E+OO ZR-95 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 NB-95 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 RU-103 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 RU-106 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 0.OOE+OO AG-110M O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 TE-125M 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 TE-127M O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 TE-129M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 I-133 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 CS-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 CS-136 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 CS-137 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 BA-140 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 CE-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR-143 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 ND-147 O.OOE+00 O.00E+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART n 2-45 01/93

TABLE 24 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: INHALATION I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 P-32 1.32E+06 7.71E+04 5.01E+04 O.OOE+00 O.OOE+00 O.OOE+00 8.64E+04 CR-51 O.OOE+00 O.OOE+00 1.OOE+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 O.OOE+00 3.96E+04 6.30E+03 O.OOE+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+00 O.OOE+00 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+00 O.OOE+00 1.02E+06 1.88E+05 CO-58 O.OOE+00 1.58E+03 2.07E+03 O.OOE+00 O.OOE+00 9.28E+05 1.06E+05 CO-60 O.OOE+00 1.15E+04 1.48E+04 O.OOE+00 O.OOE+00 5.97E+06 2.85E+05 NI-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+00 O.OOE+00 1.78E+05 1.34E+04 ZN-65-=- 3.24E+04 1.03E+05 4.66E+04 O.OOE+00 6.90E+04 8.64E+05 5.34E+04 RB-86 O.OOE+00 1.35E+05 5.90E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.66E+04 SR-89 3.04E+05 O.OOE+00 8.72E+03 O.OOE+00 O.OOE+00 1.40E+06 3.50E+05 SR-90 9.92E+07 O.OOE+00 6.10E+06 O.OOE+00 O.OOE+00 9.60E+06 7.22E+05 Y-91 4.62E+05 O.OOE+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+00 5.42E+04 1.77E+06 1.50E+05 NB-95 1.41E+04 7.82E+03 4.21E+03 O.OOE+00 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 O.00E+00 6.58E+02 O.OOE+00 5.83E+03 5.05E+05 1.10E+05 RU-106 6.91E+04 O.OOE+00 8.72E+03 O.OOE+00 1.34E+05 9.36E+06 9.12E+05 AG-110M 1.08E+04 1.OOE+04 5.94E+03 O.OOE+00 1.97E+04 4.63E+06 3.02E+05 TE-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE-129H 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+00 6.28E+03 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+00 2.87E+05 9.76E+04 1.04E+04 CS-136 3.90E+04 1.46E+05 1.10E+05 O.OOE+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 O.OOE+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+00 1.67E+O1 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+00 8.48E+05 7.78E+06 8.16E+05 PR-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+00 2.16E+03 2.81E+05 2.OOE+05 ND-147 5.27E+03 6.10E+03 3.65E+02 O.OOE+00 3.56E+03 2.21E+05 1.73E+05 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART 0 2-46 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: INHALATION I ORGAN DOSE FACTORS NUCLIDE l---------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P-32 1.89E+06 l.1OE+05 7.16E+04 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E+04 CR-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.OOE+03 MN-54 O.OOE+OO 5.11E+04 8.40E+03 O.OOE+OO 1.27E+04 1.98E+06 6.68E+04 FE-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+OO O.OOE+OO 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+OO O.OOE+OO 1.53E+06 1.78E+05 CO-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO 1.34E+06 9.52E+04 CO-60 O.OOE+OO 1.51E+04 1.98E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 1.24E+06 4.66E+04 RB O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+04 SR-89 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71E+05 SR-90 1.08E+08 O.OOE+OO 6.68E+06 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Y-91 6.61E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.OOE+04 7.51E+05 9.68E+04 RU-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 AG-liOM 1.38E+04 1.31E+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05 TE-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 5.36E+05 7.50E+04 TE-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 CS-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.1OE+05 1.78E+04 1.09E+04 CS-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+01 3.52E+03 O.OOE+OO 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21E+06 1.34E+07 8.64E+05 PR-143 1.34E+04 5.31E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1.82E+05 Rev 8 c 1QMANCHE PEAK - UMTS 1 AND 2 PART 1 2-47 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: INHALATION I ORGAN DOSE FACTORS NUCLIDE I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 2.60E+06 1.14E+05 9.8'E

_- _- _ -_ BE+04 O.OOE+OO O.OOE+OO O.OOE+OO

- _- _.- _- _ _ 4.22E+04 CR-51 O.OOE+OO O.OOE+OO 1.5 1E+02 MN-54 8.55E+01 2.43E+01 1.70E+04 1.08E+03 O.OOE+OO 4.29E+04 9.5 .E+03 FE-55 O.OOE+OO 1.OOE+04 1.58E+06 4.74E+04 2.52E+04 7.7 'E+03 2.29E+04 O.OOE+OO O.OOE+OO 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 CO-58 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 CO-60 O.OOE+OO 1.31E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 RB-86 O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 SR-89 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05 SR-90 1.O1E+08 O.OOE+OO 6.44E+06 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 RU-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1,84E+05 1.43E+07 4.29E+05 AG-llOM 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.OOE+05 TE-125H 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 4.77E+05 3.38E+04 TE-127H 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+OO 5.48E+03 CS-134 6.51E+05 1.O1E+06 2.25E+05 O.OOE+OO 3.30E+05 1.21E+05 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05

_--____-_-___- --- _- -_- _---.--.-_ O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 CS-137 _

9.07E+05 8.25E+05 1.28E+05 O.OOE+OO BA-140 2.82E+05 1.04E+05 3.62E+03 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO CE-141 2.11E+01 1.74E+06 1.02E+05 3.92E+04 1.95E+04 2.90E+03 O.OOE+OO

._-- _-_-_-_.-_-_-_--.---.---.---..-----.-----__ 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+OO PR-143 1.17E+06 1.20E+07 3.89E+05 1.85E+04 5.55E+03 9.14E+02 O.OOE+OO ND-147 3.OOE+03 4.33E+05 9.73E+04 1.08E+04 8.73E+03 6.81E+02 O.OOE+OO

-- 4.81E+03 3.28E+05 8.21E+04 COMANCHE PEAK - UNITS 1 AND 2 PART H 2-48 Rev 8 01/93

TABLE 24 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: INHALATION I ORGAN DOSE FACTORS NUCLIDE I---------------------------------------------------------------------

I BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+OO 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 P-32 2.03E+06 1.12E+05 7.74E+04 O.OOE+00 O.OOE+00 O.OOE+OO 1.61E+04

%-K- DJ U.UOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN- 54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.OOE+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+00 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+00 O.OOE+OO 1.02E+06 2.48E+04 CO 58 O.OOE+O0 1.22E+03 1.82E+03 O.OOE+00 O.OOE+00 7.77E+05 1.11E+04 CO-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+00 O.OOE+00 4.51E+06 3.19E+04

.... ....... .,,,,,,,,,,,... ... ................................ W ----

NI-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+00 O.OOE+00 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+00 3.25E+04 6.47E+05 5.14E+04 RB 6 O.OOE+00 1.90E+05 8.82E+04 O.OOE+OO O.OOE+00 O.OOE+OO 3.04E+03 SR-89 3.98E+05 O.OOE+00 1.14E+04 O.OOE+00 O.OOE+00 2.03E+06 6.40E+04 SR-g90 4.09E+07 O.OOE+0O 2.59E+06 0.001+00 O.OOE+00 1.12E+07 1.31E+05 Y-91 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+00 O.OOE+00 2.45E+06 7.03E+04 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.OOE+OO 3.11E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03 O.OOE+O0 6.79E+02 O.0OE+O0 4.24E+03 5.52E+05 1.61E+04 RU-106 8.68E+04 O.OOE+00 1.09E+04 O.OOE+00 1.07E+05 1.16E+07 1.64E+05 AG-liOM 9.98E+03 7.22E+03 5.00E+03 O.OOE+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+00 4.47E+05

........................................ 1.29E+04 TE-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 TE-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18C+04 1.68E+06 6.90E+04 I-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 O.OOE+OO

........................................ 1.06E+03 I-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+0O 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 O.OOE+0O 1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 5.29E+04 O.O+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+00 5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 O.OOE+O0 5.38E+05 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+00 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.00E+02 0.OOE+O0 3.15E+03 3.22E+05 3.12E+04 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART I 2-49 01/93

TABLE 2.5 18 (Sheet 1)

CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1). AND 5 ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3)

TABLE RELOCATED: 12 CURRENT INFORMATION LISTED AND MAINTAINED CURRENT IN RESULTS OF ANNUAL LAND USE CENSUS COMANCHE PEAK UNITS 1 AND 2 PART II 2-50 Rev. 12 12/95

THIS PAGE INTENTIONALLY LEFT BLANK 112 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-51 Rev. 12 12/95

GASEOUS WASTE PROCESSING SYSTEM FIGURE 2.1 (Skirpirfied diagram)

DISCHARGE TO ATMOSPHERE DISCHARGE TO ATMOSPHERE C) 0 z

Ix C

z

-1 z

'U 61.

-4 FLOW DIAORAMS.

MI-0289 a M1"270 N.3 WASTE OAS I(Prialm irfIrorn VohlmeI Control Tank) (5) In addition to HI-Rad. drcult failure. los of counts, loss of flow or channel out of servicewit Inltat, the contrdo functions.

(C) Fifters are present betwe*n the AIR INTAKE PLENUM ANt EXHAUST AIR PLENUM. There are sbte*n benks of 0< (1) Wide Range Gas Monitor, 1l-Rod Indication closes vets. HCV-014 litern da ded Into TRAIN A endTRAIN S Each benk conskts of a cerbon filler. 2HEPA far a carbon inI. and (Waste Gas Reoleese) a HEPA tiler In series (2) Hi-Rad Indication by monitor closes vatlve (3) Hi-Red Indlcation Initates contlinment Isolation.

(4) Eight gaseous decay tanks can be Indivldualty purged (There re tvwo additional tanks for shutdown).

C-) _ _ _

C-)

0.9 __ _

CA 0.7 z0.7 20.6 lT1i0X

,- ¢-AS S- 0 w

2 F t 0.4- - - - . _ _- - - - - -

IL 0.

0 .2- - _ _- - - - -_ _ _ - - - -

0.1 - - -_ _ _ - - - - - .

0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANGE (KILOMETERS)

Plume Depletion Effect for Ground-Level Releases (All Atniospheric Stability Clasne)

Figure 2.2

1000 I-IL

'U 10, 10.1 1.0 10 IOU PLUNIE TRAVEL DISTANCE (KILOMETERS)

Vortkcal Stwndard Deviaibon of Matral in a Plums (Lettws denate Pasquill Stability Class)

NOTE: THESE ARE' STANDARD RELATIONSHIPS AND MAY HAVE TO BE MODIFIED F1OR CERTAIN TYPES OF TERRAIN AND/OR CLIMATIC CONDITIONS15(E.G., VALLEY, DESERT. OVER WATER).

Figure 2.3 COMANCHE PEAK - UNITS 1 AND 2 01/93 PART 112-54

1(- F

- - I9 .9~.9--, I  ! I orI I I I t I

I w

10-6 I

a w

'I-1a- 7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

R*4rdve Deposition for Ground-LLl Relans (All Atmospheric Stability Clasm)

Figure 2.4 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-55 0 1/93

Cr C,

D 4A m Eu

-0 m

c 4 - - - - - - -

z)

I-0 0 4

IL z

-a w a:

0a:

0) 0.1 To II III 4 __

I.U

-1 . I DISTANCE (KILOMETERS)

II ._____________111 10 111 l_

100 0

-L 0

wa Open Terrain Correction Factor Figure 2.5

SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 SAMPLING LOCATIONS Sampling locations as required in Radiological Effluent Control 3/4.12. 1, Table 3.12-1 are 12 listed and maintained current in the results of the annual Land Use Census.

NOTE: For the purpose of implementing Radiological Effluent Control 3/4.12.1, sampling locations will be modified as required to reflect the findings of the Land Use Census. Dose calculations used in making this determination will be performed as specified in Section 2.5.

The sampling locations maintained in the results of the annual Land Use Census are the 12 minimum locations required for compliance with Radiological Effluent Control 3/4.12. 1. If desired, additional locations may be monitored as special studies to evaluate potential pathways of exposure without adding such locations to the monitoring program.

3.2 INTERLABORATORY COMPARISON PROGRAM For the purpose of implementing Radiological Effluent Control 3/4.12.3, TXU Energy has 20 contracted with an outside laboratory to provide radiological environmental analytical services with required participation in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program is conducted by a third-party laboratory which supplies 12 environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing laboratory but not to the participant laboratories. The purpose of the program is to provide an independent check on the participant laboratory's analytical procedures and to alert the participants to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing laboratory. Several months later, the issuing laboratory reports the known values to the COMANCHE PEAK - UNITS I AND 2 PART II 3-1 Rev. 20 7/02

12 participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. TXU Energy's contracted outside laboratory participates in an 20 environmental sample crosscheck program for representative sample media. The results of the 16 program are included in the Annual Radiological Environmental Operating Report, as required by CPSES ODCM Section 6.9.1.3.

COMANCHE PEAK - UNITS 1 AND 2 PART II 3-2 Rev. 20 7/02

TABLE 3.1 ENVIRONMENTAL SAMPLING LOCATIONS TABLE RELOCATED; 12 ENVIRONMENTAL SAMPLING LOCATIONS ARE LISTED AND MAINTAINED CURRENT IN THE RESULTS OF THE ANNUAL LAND USE CENSUS COMANCHE PEAK - UNITS 1 AND 2 PART II 3-3 Rev. 12 12/95

FIGURE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS FIGURE RELOCATED: 12 RADIOLOGICAL ENVIRONMENTAL MONITIORING LOCATIONS ARE LISTED AND MAINTAINED CURRENT IN THE RESULTS OF THE ANNUAL

- LAND USE CENSUS COMANCHE PEAK - UNITS 1 AND 2 PART II 3-4 REV. 12 12/95

APPENDIX A PATHWAY DOSE RATE PARAMETER Pi (inhalation) = K' (BR) DFAj [Eq. A-lI where:

Pj = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem/yr per microcurie/m 3 . The dose factors are based on the critical individual organ for the child age group.

K' = conversion factor, 106 pCi/microcurie BR = 3700 m3 /yr, breathing rate for child (Ref. 2, Table E-5)

DFAi = the maximum organ inhalation dose factor for the child age group for the ith radionuclide (mRem/pCi). Values are taken from Table E-9, Reg. Guide 1.109 (Ref. 2)

Resolution of the units yields:

Pi (inhalation) = 3.7 x 109 DFAj (mRem/yr per uCi/m3 )

(Eq. A-2]

The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.

COMANCHE PEAK - UNITS 1 AND 2 PART II A-1 01/93

APPENDIX B INHALATION PATHWAY DOSE FACTOR (RIi,a,o) a = k' (BR) (DFA.

1,a~oi,a,o ) (mrem/yr per microcurie/m 3) [Eq. B-1i where: I k' = conversion factor, 106 pCi/microcurie BR = breathing rate, 1400, 3700, 8000, and 8000 m3 /yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2, Table E-5)

DFAi,a,o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi. The total body is considered as an organ in the selection of DFAI,a,o. Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Ref.2)

COMANCHE PEAK - UNITS 1 AND 2 PART II B-1 01/93

APPENDIX C GROUND PLANE PATHWAY DOSE FACTOR (RG1 )

RG= k' k" (SF) DFGi [(1-e Xit)/Aj] [Eq. C-1]

where:

kg = conversion factor, 106 pCi/microcurie k"' = conversion factor, 8760 hr/yr A: = decay constant for the ith radionuclide, sec -1 t = the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec.

(15 yrs)

DFGi =the ground plane dose conversion factor for the ith radionuclide (mrem/hr per pCi/m 2). Values are taken from r- Table E-6, Reg. Guide 1.109 (Ref. 2). These values apply to all age groups. Dose factors are provided for the total body and skin only. Doses to all other organs are assumed equal to the total body dose.

SF = 0.7, shielding factor, from Table E-15, Reg. Guide 1.109 (Ref. 2)

COMANCHE PEAK - UNITS 1 AND 2 PART II C-1 01/93

APPENDIX D GRASS COW-MILK PATHWAY DOSE FACTOR (RC iao)

RC i,a,o k + XW)] x (Fm) x (r)x (DFL. a O) X X UAP) / (Xi1(QF

[fp x fs)/ Yp) + ((1-fp x fS) e ith)/YSI e Xjtf [Eq. D-1]

where:

k' = conversion factor, 106 picocurie/microcurie (pCi/uci)

QF = cow consumption rate, 50 kg/day, (R.G. 1. 109)

UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109)

Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m 2 (NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m 2, (NUREG 0133)

Fm = stable element transfer coefficient (Table E-1, R.G.

1.109) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, R.G. 1.109)

DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)

Xi = decay constant for the ith radionuclide, sec-1 Xw - decay constant for weathering, 5.73 x 10-7 sec -1 (NUREG-0133) tf = 1.73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-15, R.G. 1.109)

COMANCHE PEAK - UNITS 1 AND 2 PART II D-1 01/93

APPENDIX D (CONTINUED) th = 7.78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, R.G.

1.109) fp = 1.0, the fraction of the year that the cow is on pasture.

fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture.

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

RC = k'k"' Fm QF UAP DFLtao (.75 (.5/H)) [Eq. D-2]

t,a,o where:

k9-*Ir = 103 grams/kg H = 8 grams/m 3, absolute humidity of the atmosphere

.75 = fraction of total feed grass mass that is water

.5 = ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG-0133)

DFLt,a,o = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)

All other parameters and values are as given above.

NOTE: Goat-milk pathway factor, RC.,a'o will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2, R.G. 1.109. QF F for goats is 6 kg/day from Table E-3, R. G. 1.109 18 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART I]I D-2 01/93

APPENDIX E COW-MEAT PATHWAY DOSE FACTOR (RMiao)

R i,a,o = k' (QF X UAP)/(Xi + Xw) x (Ff) x (r) x (DFLj ) x M(fp x f )/Y ) + (( - f f ) ex Aith)/Y I x e-x tf

[Eq. E-1]

where:

kg = conversion factor, 106 picocurie/microcurie (pCi/uCi)

QF = cow consumption rate, 50 kg/day, (R.G. 1.109)

UAP = Receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109)

Ff-- = the stable element transfer coefficients, days/kg.

(Table E-1, R.G. 1.109) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, R.G. 1.109)

DFLi,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)

Xi = decay constant for radionuclide i, sec-l xw = decay constant for weathering, 5.73 x 10-7 sec -1 (NUREG-0133) tf = 1.73 x 106 sec, the transport time from pasture to receptor (NUREG-0133) th = 7.78 x 106 sec, the transport time from crop to receptor (NUREG-0133)

COMANCHE PEAK - UNITS 1 AND 2 PART II E-1 01/93

APPENDIX E (CONTINUED)

Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m 2 (NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/m2, (NUREG 0133)

= 1.0, the fraction of the year that the cow is on pasture.

= 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore RM is based on (X/Q):

RM = k'k"' Ff QF UAP (DFLt ao) x 0.75 x (0.5/H) [Eq. E-2]

t,a,o where:

All terms are as defined above and in Appendix D.

COMANCHE PEAK - UNITS 1 AND 2 PART II E-2 01/93

APPENDIX F VEGETATION PATHWAY DOSE FACTOR (RViao)

RY =

1,a~~o k'x [r/ (Yv ( x.i + x))]

w x (DFL iaoAaO) x [(IN) fLLexte-itL

+ US f e -x ithJ [Eq. F-1]

Ag9 where:

kg= 106 picocurie/microcurie (pCi/uCi)

ULA = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64kg/yr for infant, child, teenager, or adult age

~- groups respectively. (R.G. 1.109)

USA = the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G. 1.109) fL = the fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 (NUREG-0133) f9 = the fraction of the stored vegetation grown locally .76 (NUREG-0133) tL = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds (Table E-15, R.G.

1.109 (24 hrs))

th = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds (Table E-15, R.G. 1.109 (60 days))

COMANCHE PEAK - UNITS 1 AND 2 PART II F-1 01/93

APPENDIX F (CONTINUED)

Yv = the vegetation areal density, 2.0 kg/m 2 (Table E-15, 18 R.G. 1.109)

All other parameters are as previously defined.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, RVi is based on (X/Q) 4 kk"' EUL RVt,a,o =

[A ~L + usA ffgI (DFLt,a0o) (.75 (.5/H)) [Eq. F-2]

where:

All terms are as defined above and in Appendix D.

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II F-2 01/93

I APPENDIX G SUPPLEMENTAL GUIDANCE STATEMENTS HAVE BEEN DELETED l8 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II G-1 01/93

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL (ODCM)

EFFECTIVE PAGE LISTING BELOW IS A LEGEND FOR THE EFFECTIVE PAGE LISTINGS:

Revision 0 (TXX-89118) Submitted to the NRC March 2, 1989 Revision 1 (TXX-89595) Submitted to the NRC August 25, 1989 Revision 2 (TXX-8971 1) Submitted to the NRC November 27, 1989 Revision 3 April 10, 1990 Revision 4 October 9, 1990 Revision 5 December20, 1990 Revision 6 ,t July 3, 1991 Revision 7 December 4, 1991 Revision 7A August 6, 1992 Revision 8 (Unit 2 Operations) January 1, 1993 Revision 9 September 28, 1994 Revision 10 April 22, 1994 Revision 11 November 7, 1994 Revision 12 December 8, 1995 Revision 13 February 14, 1996 Revision 14 October 1, 1996 Revision 15 March 3, 1999 Revision 16 July 27, 1999 Revision 17 October 7, 1999 Revision 18 December20, 1999 Revision 19 October 16, 2001 Revision 20 July 8, 2002 COMANCHE PEAK - UNITS 1 AND 2 EPL- I REV. 20 7/02

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Page No. Revision No.

Cover Sheet 20 i 16 ii 16 iii 9 iv 7/99 v 16 vi 8 vii 12 viii 16 ix 7/99 x 20 xi 8 xii 20 PART I Divider Page 01/93 I 1-0 16 I 1-1 16 I 1-2 16 I 1-3 19 I1-4 07/99 I 1-5 16 I 1-6 16 12-0 01/93 I 3/4-0 01/93 I3/4-1 16 I 3/4-2 16 I 3/4-3 16 I 3/4-4 10 I 3/4-5 15 I 3/4-5a 4/94 I 3/4-6 9 I 3/4-7 13 I 3/4-8 16 I 3/4-9 01/93 I 3/4-10 01/93 13/4-11 01/93 I 3/4-12 8 I 3/4-13 18 13/4-14 18 13/4-15 01/93 13/4-16 01/93 COMANCHE PEAK - UNITS I AND 2 EPL - 2 REV. 20 7/02

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Pape No. Revision No.

13/4-17 16 I 3/4-18 20 13/4-19 8 I 3/4-20 07/02 I 3/4-20a 20 13/4-21 16 13/4-22 16 I 3/4-22a 8 I 3/4-22b 8 ERRATA 13/4-23 16 13/4-24 01/93 13/4-25 01/93 13/4-26 20 13/4-27 16 I 3/4-28 16 I 3/4-29 16 13/4-30 16 13/4-31 8 13/4-32 16 I 3/4-33 12 I 3/4-34 01/93 I 3/4-35 01/93 I 3/4-36 01/93 I 3/4-37 14 I 3/4-38 15 I 3/4-39 8 I 3/4-40 01/93 I 3/4-41 01/93 I 3/4-42 01/93 I 3/4-43 01/93 I 3/4-44 16 I 3/4-45 12 I B 3/4-0 01/93 1B3/4-1 18 I B 3/4-2 01/93 I B 3/4-3 12 I B 3/4-4 12 I B 3/4-5 8 ERRATA I B 3/4-6 12 IB3/4-7 12 I B 3/4-8 12 I B 3/4-9 8 I B 3/4-10 16 COMANCHE PEAK - UNITS I AND 2 EPL-3 REV. 20 7/02

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Page No. Revision No.

I B 3/4-11 12 I B 3/4-12 01/93 I5-0 01/93 I5-1 12 I 5-2 8 I6 01/93 I 6-1 12 I 6-2 16 I6-3 16 I6-4 16 PART II Divider Page 01/93 1 1-1 14 II 1-2 12 1 1-3 8 II 1-4 12 11 1-5 12 II 1-6 12 11 1-7 12 11 1-8 12 II 1-9 15 II 1-9a 1s II 1-9b 15 H 1-10 8 1 1-11 8 I 1-12 8 II 1-13 8 ERRATA H 1-14 20 111-15 8 II 1-16 20 II 1-17 15 II 1-18 12 II 1-19 14 II 1-20 8 II 1-21 16 II 1-22 16 11 1-23 8 11 1-24 20 II 1-25 12 11 1-26 01/93 II 1-27 01/93 COMANCHE PEAK - UNITS I AND 2 EPL - 4 REV. 20 7/02

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Pane No. Revision No.

112-1 10 II 2-2 20 II 2-3 07/02 1 2-4 16 II 2-5 8 112-6 8 112-7 12 11 2-8 20 1 2-9 8 112-10 16 112-11 8 1 2-12 8 1 2-13 12 II 2-14 12 1 2-15 12 112-16 10 II 2-17 10 II2-18 8 II 2-19 8 II 2-20 8 II2-21 8 112-22 8 ERRATA 112-23 8 1 2-24 12 II 2-25 12 11 2-26 8 ERRATA II 2-27 8 II 2-28 8 II 2-29 8 1 2-30 8 II2-31 8 1 2-32 8 II 2-33 8 II 2-34 8 II 2-35 8 II 2-36 8 II 2-37 8 II 2-38 8 II 2-39 8 II 2-40 8 II 2-41 8 112-42 8 II 2-43 8 COMANCHE PEAK - UNITS 1 AND 2 EPL-5 REV. 20 7/02

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Page No. Revision No.

112-44 8 112-45 8 112-46 8 II 2-47 8 1 2-48 8 112-49 8 1 2-50 12 112-51 12 112-52 20 112-53 01/93 1 2-54 01/93 112-55 01/93 II 2-56 01/93 113-1 20 II 3-2 20 II 3-3 12 II3-4 12 IIA-1 01/93 1 B-1 01/93 IIC-1 01/93 IID-1 01/93 IID-2 8 IIE-1 01/93 II E-2 01/93 IIF-i 01/93 II F-2 8 IIG-1 8 COMANCHE PEAK - UNITS 1 AND 2 EPL - 6 REV. 20 7/02