Text

Rev 8 to ODCM for Comanche Peak Steam Electric Station, Units 1 & 2
	ML20096H457
Person / Time
Site:	Comanche Peak
Issue date:	05/21/1992
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20096H451	List: ML20096H448; ML20096H457;
References
	PROC-920521, NUDOCS 9205270231
	Download: ML20096H457 (195)
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OFFSITE DOSE CALCULATION MANUAL FOR TU ELECTRIC COMANCHE-PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 a

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TABLE OF CONTENTS PJLER List of- Tables- vi List of Figures vii Cross Reference to Technical Specifications and REC viii References xi l

Introduction xii i i

PART I - RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 - DEFINITIONS I 1-0 SECTION 2.0 - NOT USED I 2-0 SECTIONS 3.0 AND 4.0 - CONTROLS AND SURVEILLANCE I 3/4-0 REQUIREMENTS 3/4.0 - Applicability I 3/4-1 4

3/4.3.3.4 - Radioactive Liquid Effluent I 3/4-3 Monitoring Instrumentation 3/4.3.3.5 - Radioactive Gaseous Effluent I 3/4-8 Monitoring Instrumentation 3/4.3.3.6 - Meteorological Monitoring I 3/4-13 l Instrumentation 3/4.7.15 - Sealed Source Leakage I 3/4-15 3/4.11.1.1 - Liquid Effluent Concentration I 3/4-17 3/4.11.1.2 - Liquid Effluent Dose 1 3/4-21 3/4.11.1.3 - Liquid Radwaste Treatment System I 3/4-22 3/4.11.1.4 - Evaporation Pond I 3/4-22a 3/4.11.2.1 - Gaseous Effluent Dose Rate I 3/4-23 3/4.11.2.2 - Gaseous Effluent Oose - Noble Gas I 3/4-27 3/4.11.2.3 - Gaseous Effluent Dose - Iodine-131 I 3/4-28 lodine-133, Tritium, and Radioactive

! -Material in' Particulate Form L

3/4.11.2.4 - Gaseous Radwaste Treatment System I 3/4-29 CDMANCHE PEAA - UNITS 1 AND 2 i Rev. P

TABLE OF CONTENTS Em 3/4.11.4 - Radioactive Effluents Total Dose 1 3/4-30 3/4.12.1 - Radiological Environmental Monitoring I 3/4-32 Program 3/4.12.2 - Land Use Census I 3/4-44 3/4.12.3 - Interlaboratory Comparison Program I 3/4-45 BASES I B 3/4-0 SECTION 5.0 - DESIGN FEATURES I 5-0 5.1.3 - Maps Defining Unrestricted Areas and I 5-1 Site Boundary for Radioactive Gaseous e and Liquid Eff:Jents SECTION 6.0 - ADMINISTRATIVE CONTROLS I 6-0 6.9.1.3 - Annual Radiological Environmental I 6-1 c Operating Report 6.9.1.4 - Semiannual Radioactive Effluent I 6--2 Release Report ,

6.14 Offsite Dose Calculation Manual I 6-4 PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUFNTS II 1-1 1.1 10CFR20 And Radiological Effluent Control II 1-2 Compliance 1.1.1 Isotopic Concentration of the Waste Tank II 1-3 1.1.2 Maximum Effluent flow Rate (f) 11 1-3 1.1.3 Dilution of Liquid Effluents II 1-4 1.1.4 Actual Oilution Factor (ADF) II 1-5 1.1.5 Required Dilution Factor (RDF) II 1-6 1.1.6 10CFR20 Compliance Il 1-7 COMANCHE PEAK - UNITS 1 AND 2 li Rev. 8

TABLE OF-CONTENTS--

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1.2 . Radiation Monitor Alarm Setpoints II 1-8 1.2.1 Primary Liquid Effluent Monitor II 1-8 (XRE-5253) 1.2.2 Turbine Building Sump Effluent. II 1-9 Radiation Monitors (1RE-5100 and 2RE-5100) 1.2.3 Service Water Effluent Radiation II 1-10 Monitors (1RE-4269/4270 and 2RE-4269/4270) 1.3 Dose Calculations for Liquid Effluents II 1-11 4 i

1.3.1 Calculation of Dose Oue to II 1-12 Liquid Releases 1.3.2 Calculation of Dose Due to II 1-13 Radionuclide Buildup in the Lake l 1.4 Dose Projections for Liquid II 1-14 ;

Effluents j 1.5 Definitions of Common Liquid Effluent Parameters 11 1-16 2.0 GASEOUS EFFLUENTS 11 2-1 2.1 Radiological Effluent Control 3.11.2.1 Compliance II 2-1 2.1.1 Dose Rates Due to Noble Gases II 2-3 2.1.2 . Dose Rates Due to Radiciodines, Tritium, and Particulates II 2-5 i

2.2 Gaseous Effluent Monitor Setpoints 11 2-6 2.2.1 Plant Vent Effluent Release Rate Monitors (XRE-5570A/XRE-55708) II 2-7 2.2.2 Plant Vent Stack Noble Gas Activity L

Monitors (XRE-5567A/XRE-55678) II 2-8 i 2.2.3 Sampler Flow Rate Monitors (X-RFT-5570A-1/X-RFT-55708-1) 11 2-9.

R: 2.2.4 Auxiliary Building Ventilation Exhaust 11 2-9 l Monitor (XRE-5701) l-2.2.5 Containment Atmosphere Gaseous Monitors II 2-10 (1RE-5503/2RE-5503)

CDMANCHE PEAK - UNITS 1 AND 2 iii Rev. 8

TABLE OF CONTENTS ~

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.P 2.3 Dose Calculations for Gaseous Effluents II 2-12 2.3.1 Dose Due to Noble Gases II 2-12 2.3.2 Dose Due to Radiciodines, Tritium, and Particulates 11 2-13 2.4 Dose Projections for Gaseous Effluents II 2-15 2.5 Dose Calculations to Suppport Other II 2-16 Requirements 2.6 Meteorological Model II 2-18 ,

2.6.1 Dispersion Calculations II 2-18 2.6.2 Deposition Calculations 11 2-20 2.7 Definition of Gaseous Effluent Parameters II 2-21 3.0 ,lADI0 LOGICAL ENVIRONMENTAL MONITORING II 3-1 3.1 Sampling Locations 11 3-1 3.2 'nterlaboratory Comparison Program II 3-1 APPENDIX A. Pathway Dose Rate Parameter (Pj) A-1 B. Inhalation Pathway Dose Factor B-1 -

C. Ground Plane Pathway Dose Factor C-1 D. Grass-Cow-Hilk Pathway Dose Factor D-1 E. Cow-Meat Pathway Dose Factor E-1 F. Vegetation Pathway Dose Factor F-1 G. Supplemental Guidance 5tatements G-1 CDMANCHE PEAK - UNITS 1 AND 2 iv Rev. 8

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List of Tab 1_es Table No. Title EfLqt PART I - RADIOLOGICAL EFFLUENT CONTROLS.

1.1 Frequency Notation I 1-5 1.2 Operational Modes I 1-6 i 3.3-7 Radioactive Liquid Effluent Monitoring I 3/4-4 l Instrumentation !

-4.3-3 Radioactive Liquid Effluent Monitoring I 3/4-6 Instrumentation Surveillance Requirements 3.3-8 Radioactive Gaseous Effluent Monitoring I 3/4-9 Instrumentation 4.3-4 Radioactive Gaseous Effluent Monitoring I 3/4-11 Instrumentation Surveillance Requirements 3.3-9 Meteorological Monitoring Instrumentation I 3/4-14 4.11-1 Radioactive liquid Waste Sampling and I 3/4-18 Analysis Program 4.11-2 Radioactive Gaseous iste Sampling and I 3/4-24 Analysis Program 3.12-1 Radiological Environmental Monitoring I 3/4-34 Program 3.12-2 Reporting-Levels for Radioactivity I 3/4-40 Concentrations in Environmental Samples 4.12-1 -Detection Capabilities for Environmental I 3/4-41 Sample Analyses (LL0s)

PART II - CALCULATIONAL METH000LOGIES

~1.1 . Summary of Liquid Release Pathways II 1-19 1.2 Site Related Ingestion Dose Commitment II 1-20 Factor (Aj )

2.1 Summary of Gaseous Release Pathways II 2-26 i

'2.2 Dose-Factors for Exposure to a Semi- _II 2-27 l- Infinite Cloud of Noble Gases-L 2.3 PathwayDoseRateParameter(Pj) -II 2-28 b

COMANCHE PEAX - UNITS 1 AND 2 v Rev. 8

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List of Tables Table No. Title Egg 3 -

2.4 Pathway Dose factors 11 2-29 ,

"2.5 Controlling Receptor Pathways and' 11 2-50 Locations, and Atmospheric Dispersion-Parameters (For Oose Calculations Required by Radiological-Effluent Control 3/4.11.2.3) 3.1 Environmental Sampling Locations II 3-3 F 8

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i COMANCHE PEAK - UNITS 1 AND 2 vi Rev. 8 l

List of Ficures-l Fiaure Title EfLqe PART 1- RADIOLOGICAL EFFLUENT CONTROLS 5.1-3 Site Boundary and Unrestricted Areas ! 5-2 PART II - CALCULATIONAL METHODOLOGIES 1.1 Liquid Effluent Discharge Pathways 11 1-24 1.2 Circulating Water ump o Curves II 1-26 ,

1 1.3. Energy Response to Gamma Radiations II 1-27 for RD-33 Type Detector i i

'2.1 . Gaseous Waste Processing System II 2-5?

2.2 Plume Depletion Effect for Ground 11 2-53 Level Releases 2.3- Vertical Standard Deviation of II 2-54 Material in a Plume 2.4 Relative Deposition for Ground- II 2-55 Level Releases 2.5 Open Terrain Correction Factor 11 2-56 3.1 Radiological Environmental Monitoring II 3-9 Locations i

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L COMANCHE PEAK - UNITS-1 AND 2 vii Rev. 8 I

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Cross Reference to Technical-Specifications and REC Number or Document Section Reauirement 00CM Section EART I-RADIOLOGICAL EFFLUENT CONTROLS (REC 1 Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation 3/4.3.3.4 and operability, surveillance, and 3/4.3.3.5 setpoint requirements Tech Specs 6.8.3.e.2 Limit liquid effluent concentration 3/4.11.1.1 Tech Specs 6.8.3.e.3 Effluent monitoring, sampling, and 3/4.11.1.1 and analysis requirements 3/4.11.2.1 Tect Specs 6.8.3.e.4 Limit doses due to ligaid effluents 3/4.11.1.2 ,

Tech Specs 6.8.3.e.5 Determine cumulative and projected 3/4.11.1.2, doses due to radioactive effluents 3/4.11.2.2, 3/4.11.2.3, 3/4.11.1.3, and 3/4.11.2.4 Tech Specs 6.8.3.e.6- Effluent treatment systems 3/4.11.1.3 and operability requirements 3/4.11.2.4 Tech Specs 6.8.3.e.7- Limit gaseous effluent dose rate 3/4.11.2.1 .

Tech ~ Specs 6.8.3.e,8 Limit noble gas air dose 3/4.11.2,2 l

Tech Specs 6.8.3.e.9 Limit gaseous effluent iodine and 3/4.11.2.3 particulate dose Tech Specs 6.8.3.e.10 Limit total dose 3/4.11.4 Tech Specs 6.8.3.f.1 Monitoring, sampling, and analysis 3/4.12.1-of radiation in tne environment Tech Specs 6.8.3.f.2 Land Use Census 3/4.12.2 Tech Specs 6.8.3.f.3 Interlaboratory Comparison Program 3/4.12.3 PART II - CALCULATIONAL METHODOLOGIES REC 3/4.11.1.1 Liquid effluent concentration 1.1 K'C 3/4.11.1.2 Dose due to liquid effluents 1.3 i REC. 3/4.11.1~.3 Dose projections for liquid 1.4 l releases l

l COMANCHE PEAK UNITS 1 AND 2 viii Rev 8

Cross Reference to Technical SDecifications-and REC

-Number or Document Section Reauirement C CH Section REC 3/4.11.2.1.a Dose rate due to noble gases 2.1.1 REC 3/4.11.2.1.b Dose rate due to iodine, tritium, 2.1.2 and particulates with half lives greater than eight days REC 3/4.11.2.2 Air dose due to noble gases 2.3.1 REC' 3/4.11.2.3 Doses due to iodines, tritium, 2.3.2 s and particulates with half-lives greater than eight days REC 3/4.11.2.4 Dose projections for gaseous 2.4 releases REC 3/4.11.4 Total dose due to releases of 2.5 radioactivity and direct

adiation REC 3/4.12.1 Description of radiological 3.1 environmental sampling locations REC 3/4.12.2 Dose calculations for identifying 2.5 changes to environmental sampling locations REC 3/4.12.3 De3cription of the Interlaboratory 3.2 Comparison Program REC 3.3.3.4 Radioactive liquid effluent monitoring channels alarm / trip setpoints o liquid waste monitor (XRE-5253) 1.2.1 o turbine building sump monitors 1.2.2

.(1RE-5100 and 2RE-5100) o service water monitors 1.2.3 (IRE-4269/4270 and 2RE-4269/4270)

COMANCHE PEAK - UNITS 1 AND 2 ix Rev. 8

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Cross Reference to Technical Specifications and REC Number or Document Section- Recuirement 00CM Section REC 3.3.3.5 Radioactive gaseous effluent monitoring channels alarm / trip setpoints-o -noble gas release rate monitors '2.2.)

XRE-5570A and XRE-55708 (WGRM release rate channels) o noble-gas activity monitors 2.2.2 XRE-5570A and XRE-5570B (WRGM low range activity channel)

XRE-5567A and XRE-5567B (PIG noble gas channel)-

o waste gas-holdup system monitor 2.2.4 (auxiliary building vent monitor)

XRE-5701 o sampler flow rate monitor 2.2.3 i XFT-5570A2/B2 Tech Specs 3.3.'3.1 Radiat ton monitoring channels alarm / trip setpoint '

t f o Containment atmosphere gaseous 2.2.5 monitors (containment vent ronitors) 1RE-5503 and 2RE-5503 i

Tech Specs 6.9.1.4 Assessment of radiation doses due 2.5 l-REC 6.9.1.4 to liquid and gaseous effluents released during the previous year Tech Specs 6.9.1.4 Assessment of doses to members of -2.5 REC 6.9.1.4 the public inside the site boundary Tech Specs 6.9.1.4 Assessment of doses to the most 2.5 REC 6.9.1.4 likely exposed member of the public from reactor releases and direct radiation l

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5 COMANCHE PEAK _ UNITS 1 AND 2 x Rev. 8

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REFERENCES

1. Boegli, J.S., R. R. Bellamy, W. L. Britz, and:R. L. Waterfield,

" Preparation of Radiological- Effluent Technical Specifications for NuclearPowerPlants,"NUREG-0133(October 1978).

2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, U. S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).

3. " Environmental Report," TU Electric, Comanche Peak Steam Electric _,

Station. !

4. "

Final Safety Analysis Report," TU Electric, Comanche Peak Steam Electric Station.

I

5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous l Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC l Regulatory Guide 1.111 (March 1976).

6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light - Water - Cooled Reactors, U.S.

NRC Regulatory buide 1.111, Rev. 1 (July 1977).

7. Meteorology and Atcmic Energy; Edited by Slade, D. H.; U. S. Department of Commerce (July 1968).

8. " Unit l' Technical Specifications," TU Electric Comanche Peak Steam Electric Station.

9. Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS -

to the Offsite Oose Calculation Manual or to the Process _ Control Program (GenericLetter89-01),USNRC, January 31, 1989.

10. -CPSES Technical Evaluation No. RP-90-3077, " Calculation of Site Related Ingestion Dose Commitment Factors.For Sb-122."

11. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I," USHRC Regulatory Guide 1.109 (March 1976).

CDMANCHE PEAK - UNITS 1 AND 2 xi Rev. 8

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l INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (00CM) is a supporting document of the CPSES Technical Specifications. Part I of the ODCM contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.3 and 6.9.1.4, and (3) Controls for Meteorological Monitoring Instrumentation and Sealed Source Leakage. Part II of the OOCH describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. Part II of the 00CM also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Liquid and Gaseous Radwaste Treatment System configurations are shown in Part II, Figures 1.1 and 2.1 The 00CM will be maintained at the plant for use as a reference guide and training document on accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the 00CM in order to assure that the 00CM represents the present methouclogy in all applicable areas. TV Electric initiated changes to the 00CM will be implemented in accordance with Section 6.14 of the Technical Specifications. ,

The 00CM follows the methodology and models suggested by NUREG-0133 (Ref. 1) and Regulatory Guide 1.109, Revision 1 (Ref. 2). Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementing the Radiological Effluent Control requirements.

This simplified approach will result in a more conservative dose evaluation, but requires the least amount of time for establishing compliance with regulatory requirements.

This manual is designed to provide necessary information in order to simplify the dose calculations. The dose calculations can be optionally expanded to several levels of effort. The complexity of the dose calculations can be expanded by several levels of effort, aiming toward a full calculation in accordance with Regulatory Guide 1.109. Future changes to the 00CM may be initiated to implement more complex calculations as systems become available and are validated that can reliably, economically and properly perform these more complex calculations. A beneficial approach to implementing the Radiological Effluent Control Program and Regulatory Guide 1.21 (Semiannual Radioactive Effluent Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses.

l COMANCHE PEAR - UNITS 1 AND 2 xii Rev. 8

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PART I RADIOLOGICAL EFFLUENT CONTROLS 3

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- SECTION 1.0 DEFINITIONS REV. 8 COMAdCHE PEAK UNITS 1 AND 2 PART I 1-0 1

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1.0 DEFINITIONS i The defined terms of-this section appear in capitalized type and are applicable throughout these Controls. l ACTION 1.1 ACTION shall be that part of a Control which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal-into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG l CHANNEL 0PERATIONAL TEST shall include adjustments, as necessary, of the !

alarm, interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the caannel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.6 A CHANNEL CHECK shall be~ the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with.other indications and/or status derived from independent instrument channels measuring the same parameter.

DIGITAL CHANNEL OPERATIONAL TESI 1.10 A DIGITAL CHANNEL OPERATIONAL TEST _shall consist of exercising the

digital computer-hardware using data base manipulation and injecting simulated process data to-verify OPERABILITY of alarm and/or trip functions.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 1-1

DErlNITIONS DOSE EQUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-l' 2,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Revision 1, October 1977.

FRE0VENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plan' This category does not include employees of the licensee, its contra or vendors. Also excluced from this cateaory are persons who enter ti.. e to service equipment or to make deliveries. This category does int. .;de persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE 00SE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid ?ffluent monitoring Alarm / Trip Setpoints, and in the con: 't of the Environmental Radiological Monitoring Program. The ODCM shali also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.

OPERABLE - OPERABILITY 1.20 A system, subsystem, t,ain, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART 1 1-2

QEETNITIONS 0PERATIONAL MODE MODE 1.21 An OPERATIONAL MODE (i.e.. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PRIMARY PLANT VENTILATION SYSTEM 1.24 A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate ferm in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environnent. Such a system is not considered to have any

-effect on noble gas effluents.

PURGE - PURGING 1.26 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.29 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

REPORTABLE EVENT 1.31 A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50.73.

SITE BOUNDARY 1.33 The SITE BOUNDARY shall be that line as shown in Figure 5.1-3.

SOURCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER o 1.38 THERMAL POWER shall be the total reactor core heat transfer rate to l- the reactor coolant.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 1-3 l

DEFINITIONS UNRESTRICTED AREA _

1.41 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, co mercial, institutional, and/or recreational purposes.

VENTING 1.42 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure.

idity.

concentration, or_other operating _ condition, in such a hanner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

WASTE GAS HOLOUP SYSTEM 1.43 A WASTE GAS HOLOUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant

- !ystem offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

I REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART 1-4

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. TABLE 1.1 FRE0'JENCY NOTAT1QM

- NOTATION- FREQUENCY l S- At least once per-12 hours.

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

W At least once per 7 days.

M At least once per 31 days Q At least once per 92 days.

SA At least once per-184 days.

SR At least once per 9 months.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

P- Completed prior to each release.

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l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 1 I l'

i TABLE 1.2 OPERATIONAL MODES AVERAGE

. REACTIVITY._ % RATED COOLANT.

MQQ[ CONDITION. Kpff THERMAL POWER

TEMPERATURE-

1. POWER OPERATION 1 0.99 > 5% 1 3500F 1

2. STARTUP. 2 0.99 5 5% 1 3500F l

3. HOT STANDBY < 0.99 0 2 3500F

4. HOT SHUTDOWN < 0.99 0 350cF>T avg

> 2000F

5. COLD SHUTDOWN < 0.99 0 5 2000F

6. REFUELING ** 5 0.95 C 5 1400F

Excluding decay heat.

- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

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REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I 1-6

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SECTION 2.0 NOT llSED i

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1 COMANCHE PEAK Uh!TS 1 AND 2 PART I 2-0 t - ~~ +2-vw- e --yt< v + < ews-nrw-,-h r -e--- r -

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SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS REV. 8 COMANCHE' PEAK UNITS 1 AND 2 PART 1 3/4-0

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l 3/4 CONTROLS AND SURVE1LLANCE REQUIREMENTS l

3/4.0 APPllCABILITY #

CONTROLS 3.0.1- Compliance with the Controls contained in the succeeding Controls is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, comp'etion of the ACTION requirements is not required.

3.0.3 When a Control is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apoly by p!)cing i;, as applicable, in;

a. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that perm" operation under the ACTION requirements, the action may be taken in accordar.ce with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual controls.

This control is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Control are not met and the associated ACTION requires a shutdcwn if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued oparation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual controls.

f The associated basis from the CPSES Technical Specifications 6pplies to this section.

I REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-1 i

!~

APPLICABILITY I

SURVEILLANCE REQUIREMENTS 4 .0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controit unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Euch Surveillance Requirement shall be performed within the 7 specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. Exceptions to these requirements are stated in the individual controls.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance Requirement 4.0.2, shall <

constitute noncompliance with the OPERABILITY requirements for a Control. I The time limits of the ACTION requirements are applicable at the time is I identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveil'ance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Control has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual controls.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-2

INSTRUMENTATION RADIDACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION !

l CONTROLS l 3.3.3.4 In accordance with CPSES TS 6.8.3.e.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-7 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints of these 8 channels shall be determined and adjusted in accorcance with the methodology and parameters in Part II of the OFFSITE 00SE CALCULATION ,

MANUAL (00CM). l APPLICABILITY: At all times.

ACTION:

. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, b With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE. take the ACTION shown in Table 3.3-7 Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability wa' not corrected in a timely manner.

c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE PEOUIREMENTS 4.3.3.4 Each radioactive liquid effluent monitoring instrumentation channel shall be demanstrated OPERA 8LE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-3.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-3

TABLE 3.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION O

35 MINIMUM p" CHANNELS gj INSTRUMENT OPERABLE ACTION ff 1. Radioactivity Monitors Providing Alarm ar.d 25 Automatic Termination of Release e

cg a. Liquid Radwaste Effluent Line (XRE-5253) 1 30 0 b. Turbine Building (Floor Drains) Sumps Ef fluent Lines 1/ sump 31 (IRE-5100 & 2RE-5100)

, ' EE l8 O 2. Radioactivity Monitors Providing Alarm But Not Providing

^)

Automatic Termination of Release

a. Service Water Systed Effluent Lines 1/ train 32 (1RE-4269, IRE-4270 & 2RE-4269, 2RE-4270) 4 x3 3$

l8

-d

3. Flow Rate Measurement Devices

a. Liquid Radwaste Ef fluent Line (XFT-5288) 1 33 u

e l

4 03

,a

l TABLE 3.3-7 (Continued)

ACTION STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a j release: i

a. At least two independent samples are analyzed in accordance 1 with Control 4.11.1.1.1, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and 3 discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathwcy.

ACTION 31- With the number of channels OPERABLE less than required by the 8 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microcurie /mi :

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131. (Refer to Notation 3 8 of Table 4.11-1 for the applicability of the LLO requirement.)

ACTION 32- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operations may continue provided that:

a. With the component cooling water monitors (1RE-4509, IRE-4510,&1Rj-4511)OPERABLEandindicatinganactivityofless than 1X10- microcurie /ml, a grab sample is collected and analyzedforradjoactivityatalowerlimitofdetectionof no more than 10- microcurie /mi at least every 31 days; or

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and 8 analyzedforprincipalgammaemitjersatalowerlimitof detection of no more than 5 x 10- microcurie /ml. (Refer to Hotation 3 of Table 4.11-1 for the applicability of the LLD_ requirement.)

NOTE: Collection of grab samples is not required when there is no 7 process flow at the monitor.

ACTION 33- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,-effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual. releases. Pump performance curves generated in placa may be used to estimate flow.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-5

4 I

i i

TABLE 4.3-3 I !

RADI0 ACTIVE LIGHID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS O

j

ANALOG DIGITAL gg - CHANNEL CHANNEL

, g; CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL j y INSTRUMENT CHECK CHECK CALIBRATION TEST TEST m

N 1. Radioactivity Monitors Providing Alarm and j

i Automatic Termination of Release

.. e

a. Liquid Radwaste Effluent Line (XRE-5253) D P R(4) N.A. 0(1)

b. Turbine Building (Floor Drains) Sumps

}; Effluerit Lines (1RE-5100 & 2RE-5100) D M R(4) N.A. 0(2) l8 o

' ^3 2. Radioactivity Monitors.Providing Alarm But Not Providing Automatic Termination of Release

,, a. Service Water System Effluent Lines (IRE-4269. 1RE-4270. 2RE-4269 & 2RE-4270) 0(3)

3 D M R(4) N.A.

l8 j

3. Flow Rate Measurement Devices

! bJ .

~~

P a. Liquii Radwaste Effluent Line C'

. (XFT-5288) D(5) N.A. R 0 N.A.

l 4-

! x2 t

^

I i ca 3.

d

TABLE 4.3-3 (Continued 1 TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or 1

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of l Counts, Loss of Sample Flow, or Check Source Failure).

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic flow diversion of this pathway (from the Lew Volume Waste Treatment Syste" to the Co-Current Waste Treatment System) and Control Room alarm ai.aunciation occur if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm / Trip I Setpoint, or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).

(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exist:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample r'ow, or Check Source Failure).

(4)TheinitialCHANNELCALIBRATIt. 4 hall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been relatea to the initial calibration, reference standards certified by NBS, or standards that have been obtained from suppliers that participate in measurement assurance activities with NBS shall be used.

(5) CHANNEL-CHECK shall consist of verifying indication of flow uuring periods of-release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, per_ iodic, or batch releases are made.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-7

INSTRUMENTATION RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.5 In accordance with CPSES TS 6.8.3.e.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their Alarm /Irip Setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The Alarm / Trip Setpoints of these 8 channels shall be determined and adjusted in accordance with the methodology and parameters in Part II of the ODCH.

APPLICABILITY: As shown in Table 3.3-8 ACTION:

a. With a rcdioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseous effluents monitor ^d by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceotably conservative. -

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if '

unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.

c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 1 SURVEILLANCE REQUIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIERATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Taole 4.3-a.

REV 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-8 l

lABLE 3.3-8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION c3 x MINIMUM CHANNELS INSTRUMENT- QPERABLE APPLICABTLITI ACTION

1. WASTE GAS HOLDUP SYSTEM 3E a. Noble Gas Release Rate i

Monitor - Providing Alarm SE and Automatic Termination

$ of Release v) [XRE-5570A & XRE-55708 (effluent release rate channel)] 1/ stack **

34

$E-c) 2. PRIMARY PLANT VENTILATION ru i a. Noble Gas Release Rate Monitor

[XRE-5570A & XRE-55708

,, (effluent release rate channel)] 1/ stack

36 I 3$

l

b. Iodine Sampler (WRGM sample skid) 1/ stack

37

{}

s

! s 4

P c. Particulate Sampler 1/ stack

37 43 (WRGH sample skid)

d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1, I/ stack

35 4 X-RFT-55708-1) ,

4 x

l, l

4

TABLE 3.3-8 (Continued)

TABLE NOTATIONS

At all times.

- During Batch Radioactive Releases via this pathway.

ACTION 34- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

a. The auxiliary building vent duct monitor-(XRE-5'<01) is confirmed OPERABLE, or

b. At least two independent samples of the tank's contents are analyzed, and

c. At least two technically qualified members of the facility staff indepensently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 35- With the number of channels OPERABLE less than required by the 4 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 36- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent reieases via this pathway may continue provided that:

(a) A Plant Vent Noble Gas Activity Monitor (XRE-5570A, XRE-5570B (low range activity) or XRE-5567A, XRE-55678) is OPERABLE, and the plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or (b) The Plant Vent Flow Monitor, PROC FLOW H (X-FT-5570A-1, 4 X-FT-55708-1), is OPERABLE, and an alternate Plant Vent Noble Gas Activity Monitor is OPERABLE (XRE-5567A, XRE-55678) or grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or (c) The plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and grab sample', are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway uay continue provided sample; are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-10 t

TABLE 4.3-4 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAL hh CHANNEL CHANNEL

[;

CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL g?

P' CHECK (HECK CALIBRATION TEST TEST INSTRUMENT.

A y 1. WASTE GAS HOLDUP SYSTEM h a. Noble Gas Release Rate Monitor -

35 Providing Alarm a..d Automatic gj Termination of Release

_, [XRE-5570A. XRE-5570B(effluent release N.A.

rate channel)] P P R(3) Oll) p 8

y 2. PRIMARY PLANT VENTILATION

a. Noble Gas Release Rate Monitor

[XRE-5570A. XRE-5570B(effluent release N.A.

rate channel)] D # R(3) 0(2)

J 3

- b. Iodine Sampler M.A.

(WRGH sample skid) W(4) N.A. N.A. N.A.

w 2

i. c. Particulate Sampler (WRGM Sample Skid) W(4) N.A. N.A. N.A. N.A.

d. Sampler Flow Rate Mor.itor N.A. 4 D N.A. R 0 SMPL Flow 1 (X-RFT-5570A-1. 4 X-RFT-5570B-1) 5 y

CO

-- 3

TABLE 4.3-4 (Continued TABLE NOTATIONS

Prior to anv "elease from the WASTE GAS HOLDUP SYSTEM or containment PUMING or VENTING, not to exceed 31 days.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following condition exists;

a. Instrument indicates measured levels above the Alarm / Trip Setpoints or

b. Circuit failure, (Channel Out of Service - Loss of Power Loss of Counts, Loss of Sample Flow, or Check Source Failure).

(2) The DIGITAL CHANNIL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit tailure (Channel Out of Service - Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source failure).

(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or bsing stanttrds that have been obtained from suppliers that participate in measwrement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration, reference standards certified by NBS, or standards that have been obtained from suppliers that participate in measurement assursnce activities with NBS shall be used.

(4) The CHANNEL CHECK shall consist of visually verifying that the collection element (i.e., filter or cartridge, etc.) is in place for sempling.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-12

INSTPUMENTATION PETEOROLOGICAL HONITORING INSTRUMENTATION CONTROL S 3.3.3.6 The neteorological monitoring instrumentation channels shown in 8 Table 3.3-9 shall be OPERABLE.

APPLICABILITY: At all times. :

ACTION: '

a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to CPSES Technical l Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

SURVEILLANCE RE*'lIREMENTS 4.3.3.6 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by performance of a CHANNEL CHECK.

and At least once per 184 days by performance af a CHANNEL CAllBRATION.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-13

TABLE 3.3-9 PETEOR0 LOGICAL MONITORING INSTRUMENTATION HINIMUM INSTRUMENI LOCATION OPERABLE

1. WIND SPr"1 1 of 3

a. X-SY-4117 Nominal Elev. 60 m.

b. X-SY-4118 Nominal Eles. 10 m.

c. X-SY-4128* Nominal Elev. 10 m.

2. WIND DIRECTION 1 of 3 _

a. X-ZY-4115 Nominal Elev. 60 m.

b. X-ZY-4116 Nom'. nal E lev.10 m.

c. X-ZY-4126* Nominal Elev. 10 m.

3. AIR TEMPERATURE - AT 1 of 2

a. X-TY-4119 Nominal Elev. 60 m. and Nominal Elev. 10 m.

b. X-TY-4120 Nominal Elev. 60 m. and Nominal Elev.10 m.

5

Mounted on backup tower.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-14

INSTRUMENTATION 5.EALEO SOURCE CONTAMINATION CONTROLS 3.7.15 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gance emitting material or 5 microCuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.

APPLICABillTY: At all times.

ACTION With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with Commission Regulations.

SURVEILLANCE REOUIREMENTS 4.7.15.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample, 4.7.15.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.

a. Sources in use - At least once per 6 months for all sealed sou ces containing radioactive materials:

1) With a half-life greater than 30 days (excluding Hydrogen 3),

and

-2) In any form other than gas, s

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART 1 3/4-15

SURVEILLANCE REOUIREMENTS (Continued)

b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being '

placed into use; and i

c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tasted prior to installation or within 31 days prior to being subjected to core flux and following repair or maintenance to the source.

4.7.15.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-16

3/4.11 RAD 10 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with CPSES TS 6.8.3.e.2 and 3. the concentration cf B radioactive material released in liquid effluents from the site to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table 11. Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /ml total activity.

APPLICABILITY: At all times.

ACTION:

(a) With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

(b) The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

s SURVE111NCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed e.ccording to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in 8 accordance with the nethodology and parameters in Part 11 cf the 00CM to assure that the concentrations at the point of release are maintained witnin the limits of Control 3.11.1.1.

I REV. 8 CDMANCHE PEAK - UNITS 1 AND 2 PART I 3/4-17 l

mbus ammamus..-m.-am..*... . .

TABLE 4.11 1 Radioactive Uqt'Id Waste Sampling and Analysis Program LIQUID RELEASE SAMPLING MINIMlVM TYPE OF ACTIVITY LOWER LIVIT CF l

TYPE FREQUENCY ANALYSG ANALYOIS DETECTION (1)

FREQUENCY ( Clim!)

I A Batch Waste Re'ests (2) ' P P Principal Gamma 5.CE 07 Tanks tc the Circu'atmg Each Batch Each Batch Emrtters (3) 7 Water D:senarge

a. Waste Monnor l Tanks Dissolved & Entraved 1.CE 05 8 Gases (Gantna EnuttersK3)

b. laundry Holdvo I a Montte; Tanks M H3 i LCE M g

Gross Aloha 1CE07

c. Wastewater )

O Sr 89, St 90 5 CE-C8 Holdup Tanks (8)

Fe 55 1.C E-06

, l 7

18. BatenWaste Re! ease (2) P P Principal Gamma SCE07 Tanks to the LVW Pond Each Batch Each Batch Emrtters (3)

a. Cordensate _

Ni.4he: Backwash R6cwery Tanks (6,7)

b. Component Cooling Water Drain Tanks (7) g

c. Waste Water H3 1.CE 05 Holdup Tanks (6.8) 2A. Continuous Release 15) ) Daily Grab Composite Principal Gamma 5.CE 07 -

7 to the C!rculating Sample (9) over pond Emrtters (3)

Water D!scharge discharge

a. Low Volume Waste Pond Effluents Dissolved & Ent awwd 1.CE 05 '

Gases (Garivna EnittersM3) O H3 1.CE-05 Gross Alpha 1.CE 07 O St89,St90 5.CE-Ca Compostte (4)

Fe-55 1.CE 06 ,

28. Corcinuous Releases (5) W W Principal Gan ma 5.CE-07 to the LVW Pond Grab Sample Emnters (3)

a. Turbine Bldg. Sump No. 2 Effluents (6,7) 1131 1.CE 06

a. Turbine Bldg. Sump a No. 4 Effluents (6,7) H3 1.CE 05 COMANCHE PEAK - UNITS 1 AND 2 PART l 3/4-18 REV.8

1 TABLE 4.11-1 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a bla-k observation represents a "real" signal.

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

4.66 sb LLO =

E V 2.22 x 106 . y . exp (.Jult)

Wnera:

LLO = the "a prisri" lower limit of detection (microcurie per unit mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute).

E = the counting efficiency (counts per disintegratien),

V = the sample size (units of mass or volume),

2.22 x 106 = the numoer of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s- 1 ), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).

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

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

(2) A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then 8 thoroughly mixed by a method described in Part 11 of the 00CM to assure representative sampling.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-19 ,

l

TABLE 4.11-1 (Continued)

TABLE NOTATIONS (3) The principal gamma emmiters for which the LLO specificaticn applies 8 include the following radionuclides: Hn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, and Ce-141 for fission and corrosion products, and Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved or entrained gases. Ce-144 shall also be measured, but with an LLO of 5 x 10-6 This list does not mean that only~ these nuclides are to be considered. Other garra peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control I 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1 June 1974.

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

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) These wasto streams shall be sempled and analyzed, in accordance with 7 this table, if radioactive material is detected in the LVW Pond composite saaples in concentrations, that exceed 10% of the limits of 10 CFR 20, Appendix B, Table II, Column 2. This sampling 2 hall continue until 2 consecutive samples from the waste stream show that the concentration of radioactive materials in the waste stream is less than or equal to 10% of the limits of 10 CFR 20, Appendix 8. Table II, Column 2.

(7) All flow from these waste streams shall be divertad to the Waste Water 7 Holdup Tanks if activity is present in the waste stream in concentration; that exceed the limits of 10 CFR 20, Appendix B, Table II, Column 2. Sampling and analysis of the respective Tanks or sumps are not required when flow is diverted to the Waste Water Holdup Tanks.

(8) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the 7 Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed the limits of 10 CFR 20, Appendix B, Table II, Column 2. Otherwise, WWHis may be discharged to the Low Volume Waste Pond. WWHT discharges to the Circulating Water Discharge Tunnel shall be sampled and analyzed per item 1A.c of this table. WWHT discharges to the LVW Pond shall be sampled and analyzed per Item 18.c of tnis table.

(9) Samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while the release is 7 l occurring. To be representative of the liquid effluent, the sample

! volume shall be proportioned to the e ^1uent r stream discharge volume.

l The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-20

c RADI0 ACTIVE EFFLUENTS EQlE CONTROLS 3.11.1.2 In accordance with CPSES TS 6.8.3.e.4 and 6.8.3.e.5 the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive naterials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ. '

APPLICABILITY: At all times.

ACTLQH:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141 Safe Drinking Water Act.

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.1.2 Culmulative dose contributions from liquid effluents for the 8 current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part 11 of the 00CM at least once per 31 days.

REV. 8 COHANCHE PEAK UNITS 1 AND 2 PART I 3/4-21

RADIDACTIVE EFFLUENTS LIOUID RADWASTE TREATMENT SYSTEM CONTROL S 3.11.1.3 In accordance with CPSES TS 6.8.3.e.6, the Liquid Radwaste .

Treatment System shall be OPERABLE and appropriate portions of the system !

shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION: -

t

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatmeat System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a- Special Report that includes the following information:

1. Explanation of why liquid raduaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Ac' ion (s) taken to restore the inoperable equipment to OPERABLE status, and

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

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED 8 AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Part 11 of the 00CM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22

-_ _ _ - . _ . - . _ _ - - ~ - -. __

RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY 7 CONTROLS 3.11.1.4 The quantity of radioactive material contained in resins 7 transferred to the LVW Pond shall be limited by the following expression :

h eE_J e <1.0 J

excluding tritium, dissolved or entrained noble gases, and radionuclides 7 with less than an 8 day half life, where: 7 A

j= pond inventory limit for single radionuclide "j" (Curies), 7 3 " hnh kdi $$Ne 3" brofurk $) '

V =- volume of resins in the pond (gallons), and 7 264 = unit conversion factor (microCuries/ Curie per 7 milliliter / gallon).

APPLICABILITY: At all times. 2 ACTION:

a. With the quantity of radioactive material in the LVW Pond 7 exceeding the above limit. immediately suspend all additions of radioactive material to the pond.

b. The provisions of Controls 3.0.3 and 3.0.4 are not 2 applicable.

SURVEILLANCE RE0UIREMENTS 4.11,1.4 The quantity of radioactive material contained in each batch of 7 slurry (used powdex resin) to be transferred to the LVW Pond shall be determined to be within the above limit by analyzing a representative sample of the slurry, and batches to be transferred to the LVW Pond shall be limited by the expression:

% <0.006 e R N I/9*

C C1/mT where:j 3 Q=

j concentration of radioactive materials 7 wet, drained slurry (used powdex resin)(microCuries/gm) infor radionuclide "j",

excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8 day half-life. The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-60. Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent l_ quarterly composite analysis, I

REV. 8 l

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22a

s I

RADI0 ACTIVE EFFLUENTS LVW POND RESIN INVENTORY 7 i

SURVEILLANCE REOUIREMENTS (Continued) l l

C j= l CFR 20 Appen ix ble 11 Column conc 7 sjngleradionucijde@3,,Tfmicrocuries/miljliiterfntrationfor

, and i

R= Slurry v6 ume to resin weight ratio (ml/gm)

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22b

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASE00f .Ef FLUENTS DOSE RATE i

3.11.2.1 In accordance with CPSES TS 6.8.3.e.3 and 6.8.3.e.7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BDUNDARY (see Figure 5.1-3) shall be limited to the following: :

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

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

APPLICABILITY: At all times.

ACTION:

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

(b) The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed 8 acccrding to the sampling and analysis program of Table 4.11-2.

4.11.2.1.2 The results of the radioactivity analyses shall be used in 8 accordance with the methodology and parameters in Part II of the ODCM to assure that the dose rates at the SI1E 80VHDARY are maintained within the limits of Control 3.11.2.1.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-23 l

l

c) o 3

$c TABLE 4.Il-2 m ,

y Radioactive Gaseous Weste Sampling and Analysis Program (*) !

rn j- 3=

i X i e MINIMUM LOWER LIMIT OF 5 l c- SAMPLING ANALYSIS TYPE OF DETECTION (LLD)(1)

- 3 GASEOUS RELEASE TYPE FREQUENCY FREQUENCY LCTIVITY A'1LLYSIS spC1/ml) r 1 -a v>

1. Waste Gas Storage P P

- Tank Each Tank Each Tank Principal Gamma Emitters (2) lx10 O

Grab Sample

'. Containment Purge P P N Each Release (3) 1x10 f or Vent Each Release (3) Principal Canana Emitters (2)

Grab Sample 4

M H-3 (oxide) lxlO

3. Plant Vent M(3), (4), ($) Principal Gamma Emitters (2) lx10- !

~n

{ y Grab Sample M(3) H-3 (oxide) a Continuous (6) W(7) 1-1 I lyl0

~

ss Radioicdine 7

N Adsorber Continuous (6) W(7) Principal Gamma Emitters (2) lx10' Particulate

Sample

, Continuous (6) M Gross Alpha lxlO j Composite Par-ticolate Sample Continuous (6) , Q St -89 Sr-90 lx10~

Cemposite Per-ticulate Sample i $ Noble Ga s c c l

$ Cor ' i mu.o e f 6 ) Beta or Gamma Noble Gas lxlO 3

cn

,

Table notations next page

- This sample is continuously analyzed by a radiation monitor l

98LE 4;11-2 (Continued)

TABLE NOTATIONS

'(1) The LLD is defined, for purposes of these specit .;ations, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurenent system, which may include radiochemical separation:

. 4.66 s.'

LLO = __

E y . 2.22 x 10 6 . y . exp (4At)

Where:

LLO = the "a priori" lower limit of detection (micrtCorie per unit mass or volume),

s b = the standard devi rate or ofthecountingrateoftionofthebickroundcounting(counts ablanksampe$sappropriate per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec-1), and at= the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and t should be used in tne calculation.

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

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-25

l TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Coptinued)

(2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Cc-60, 2n-65, 1-131 Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above ruclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report, pursuant to Control 6.9.1.4, in the format outlined in Regulatory Guido 1.21, Appendix B, Revision 1. June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% cf RATED THERMAL POWER within a 1-hour period. This requirement does not apply if: (1) analysis of primary coolant activity performed pursuant to Technical Specification 4.4.7 shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not irAreased more than a factor of 3.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation ev'. dust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) The ratio of the sample flow rato to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calcula' ~on made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from the sampler. Sampling shall also _be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

-for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-26 l

RADIOACTIVE EFFLUENTS.

DOSE - NOBLE-GASES CONTROLS 3.11.2.2 In accordance with CPSES TS 6.8.3.e.5 and 6.8.3.e.8, the air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

e. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for ganna radiation and lest than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

aC1103

a. With the calculated air dose from radioactive noble gases in 8 gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent l releases will be in compliance with the above limits,

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS ,

4.11.2.2 Cumulative dose contributions for the current calendar quarter 8 and current calendar year for noble gases shall be determined in accordanc.e with the methodology and parameters in Part II of the ODCM at least once per 31 days.

l l

i L

l REV. 8 C0HANCHE PEAK UNITS 1 AND 2 PART I 3/4-27 l

' RAD 10 ACTIVE EFFLUENTS DOSE - 10 DINE-131. 10 DINE-133. TRITIUM. AND RA010 ACTIVE MATERIAL IN PARTICULATE FOM CONTROLS 3.11.2.3 In accordance with CPSES TS 6.8.3.e.5 and 6.8.3.e.9, the dose to a MEMBER OF THE PUBLIC from Iodine-131. Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iocine-131, lodine- 8 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days, pursuant to Specification F 9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter 8 and current calendar year for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the metholodogy and parameters in Part II of the ODCM at least once per 31 days.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-28

RADIDACTfVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with CPSES TS 6.8.3.e.6, the PRIMARY PLANT VENTILATION SYSTEM and the WASTE GAS-HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity-when the projected doses in 31 days due to gaseous effluent releases, from each unit, tc areas at and beyond the SITE BOUNDARY (see figure 5.1-3) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without 8 treatment and in excess of the above limits, prepare and submit to the NRC within 30 days, pursuant to specification 6.9.2, a Special Report that includes the following informatic":

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

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

b. The provisions of Control 3.0.3 and 3.0.4 are not applicabie.

SURVEILLANCE REOUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and 8 beyond the SITE BOUNDARY shall be-projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

L 4.11.2.4.2 The installed PRIMARY PLANT VENTIIATION SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

t REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-29

RADf0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL 00SE CONTROLS 3.11.4 In accordance with CPSES TS 6.8.3.e.10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses'from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a. , or 3.11.2.3b. , calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and 8 submit to the NRC within 30 days, pursuant to Specification 6.9.2,.a Special Report that defines the corrective action to be taken to_ reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a HEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been c;crected, the Special Report shall include a request for a va~1ance in accordance with the provisions of 40 CFR Part 190. Submittal of:the report is considered a timely request, and a variance is granted until staff action on the request is complete.-

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents 8 shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in Part II of the ODCM.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-30

. RADIOACTIVE EFFLUENTS (Continued) 3/4.11.4 TOTAL DOSE XV31EJ.LLANCE REOUIREMENTS 4.11.4.2 Cumulative dose contributions from direct radiation from the 8 units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Part II of the 00CM. This requirement is applicable only under conditions set forth in ACTION a. of l Control 3.11.4 i

l REV. 8 L C0HANCHE PEAK UNITS 1 AND 2 PART I 3/4-31 l

l l

3/4.12 RADIOLOGICAL ENVIRQNMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 In accordance with CPSES TS 6.8.3.f.1, the Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3, a description of the reason (s) for not conducting the program as required and the clan for preventing a recurrence,

b. - With the level.of radioactivity as the result of plant effluents 8 in.an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the NRC within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+

reporting level (1) reporting level (2)+...t 1.0 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3.

This report is not required if tne measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the annual-Radiological Environmental Operating Report required by Control 6.9.1.3.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

REV. 3 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-32

RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS ACTION (Continued)

c. With milk or fresh leafy vegetable sampbs unavailable from one 8 or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in Part II of the OGCM. The specif;c locations from which samples were unavailable may then be deleted from the monitoring program. Pursuent to Control 6.14, submit as a part of or concurrent with the Semiannual Radioactive Effluent Release Report, a complete, legible copy of the entire 00CM, including a revised figure (s) and table for the 00CM reflecting the new location (s).

d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.12.1 The radiological environmental moaitoring samples shall be 8 collected pursuant to Table 3.12-1 from the specific locations given in Table 3.1 and Figure 3.1 in Part II of the 00CM, and sita11 be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

REV. 8

COMANCHE PEAX UNITS 1 AND 2 PART I 3/4-33

TABLE 3.12-1 Radiological. Environmental Monitoring Program o

o y NUMBER'0F' A . REPRESENTATIVE si . EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY y AND/0R SAMPLE __ SAMPLE LOCATIONS (l) COLLECTION FREQUENCY OF ANALYSIS 9

1. Direct Radiation (2) . Forty routine monitorinn stations Quarterly. Gamma dose quarterly either with two or more dosimeters E or with one instrument for measur-El ing and recording dose rate

[] continuously, placed as follows:

5E An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY:

An outer ring of stations, one in v each meteorological sector in E the 6- to 8-km range from the t

] site: and id The balance of the stations to be f placed in special interest areas I$ such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

2. Airborne Radioiodine and Samples from five locations: Continuous sampler Radiciodine Cannister:

g; Particulates operation with sample I-131 analysis weekly

, collection weekly, g Three samples from close to or more frequently the three SITE B0UNDARY if required by dust Particulate Sampler:

locations, in different loading. Gross beta radio-sectors, of the highest activity analysis calculated annual average following filter ,

ground-level D/0: change: (4) and

gamma isotopic analysis (5) of composite (by location quarterly.

TABLE 3.12-1 (Continue <D c,

Radiological Environmental H0nitoring Program SS h; NUMBER OF S] REPRESENTATIVE m SAMPLES AND SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATHWAY AND/0R SAMPLE SAMPLE LOCATIONS (l) C0ttECTIGN FREQUENCY OF ANALYSIS

??

R One sample from the c vicinity of a community 5 having the highest calcu-lated annual average ground-D1

_. level 0/0: and 55 One sample from a control m location, as for example 15 to 30 km distant and in the least prevalent wind direction. (3) 3 3. Waterborne

$ Gamma isotopic anal-

a. Surface Squaw Creek Reservoir (6) Honthly composite of ,

ysis(3) monthly.

o, weekly grab samples.

Composite for tritium 3:

analysis quarterly, 20 w

Lake Granbury Honthly composite of Gamme isotopic anal-weekly grab samples ysis(5) monthly.

when Lake Granbury Composite for tritium is receiving letdown analysis quarterly.

from SCR. Otherwise, mon:hly grab sample.(7' A Gamma isotopic anal-5 Control-Brazos Rivei- Mon +,hly oo upstream of Lake Granbury ysis(5) monthly.

Couposite for tritium analysis quarterly.

Samples from two sources Quarterly Gamma isotopic (5)

b. Ground if likely to be affected(8) . and tritium analysis quarterly.

-, i

TABLE 3.12-1 (Continued) n Radiological Environmental Monitoring Program 3

$ NUMBER OF E2 - REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE'AND FREQUENCY

?' AND/0R SAMPLE SAMPLE LOCATIONS (l) COLLECTION FREQUENCY _ 0F ANALYSIS R

. 3. Waterborne (Continued)

c. Drinking One sample from Squaw Creek Composite of weekly 1-131 analysis of d Reservoir. grab samples over each composite sample 2-week period when when the dose calcu-

> I-131 analysis is lated for the con-

@5 performed: monthly sumption of the water m composite of weekly is greater than'l mrem grab samples other- per year (9) . Gross wise. beta and gamma iso-topic analyses (5) g monthly. Composite

-4 for tritium analysis quarterly.

w

'E d. Sediment One sample from downstream area Semiannually. Gamma isotopic analy-

$2 from with existing or potential sis (5) semiannually.

Shoreline recreational value.

4. Ingestion

a. Milk Samples from milking animals in Semimonthly when Gamma isotopic (5) three locations within 5 km animals are on and I-131 analysis

,, distance having the highest do:e pasture; monthly semimonthly when

[g potential. If there are none, at other times. animals are on pas-sample from milking animals in ture; monthly at 03 each of three areas between 5 other times.

to 8 km distant where doses are calculated to be greater than 1 mrem per yr.(9) One sample from milking animals at a control location. 15 to 30 km distant and in the least direction.(3) prevalent wind

d i

TABLE 3.12-1 (Continued) c, Radiological Environmental Monitoring Program S

g NUMBER OF S' REPRESENTATIVE rn EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY

E .

AND/OR SAMPLE SAMPLE LOCATIONS (l) COLLECTION FREQUENCY OF ANALYSIS M

t , '4. Ingestion (Continued)

C 55 b. Fish and One sample of at least two Sample semiannually. Gamma isotopic gj Invert 3brates recreationally important species analysis (5) on

_. in vicinity of plant discharge area. edible portions.

E5 One sample of same species in areas no not influenced-by plant discharge.

c. Food Products

One sample of each principal class At time of harvest (10) Gamma isotopic of food products from any area analysis (5) on 3 that is irrigated by water in which edible portion.

Z liquid plant wastes have been

- dischcrged.

w 3: A samole of broad leaf vegetation Monthly, when Gamma isotopic 5) la growa nearest each of two dif- available. and I-131 analyses.

ferent offsite locations of highest predicted annual average ground. level D/0 if milk sampling is not performed at all required locations.

(5)

One samnle of each of the similar Monthly, when Gamma isotopic A broad leaf vegetation grown 15 to available. and I-131 analyses.

5 30 km distant in the least pre-00 valent wind direction (3) if milk sampling is not performed at all required locations.

oReports from 3 ao ional airborne radiciodine sample locations may be supplemented for broad leaf l vegetation samples. '

l TABLE 3.12-1 (Continued)

TABLE NOTATIONS (1) for each and every sample location required by Table 3.12-1, specific 8 parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, arE provided in Table 3.1 and Figure 3.1 in Part II of the 00CM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative 8 media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in Part II of the ODCM. Pursuant to Control 6.14, submit as a part of or concurrent with the next Semiannual Radioactive Effluent Release Report a complete legible copy of the ODCM including a revised figure (s) and table for the ODCM reflecting the new location (s).

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

(3) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that prcvide valid background data may be substituted.

(4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-38 1

i m_ .

-- . - - ._ _ _. _m _ _ _ _ - _ . _ _ u_______ _ _ _ . _ _ _ _ _ _

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

(5) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to che effluents from the facility.

(6) The Reservoir shall be sampled in an area at or beyond but near the mixing zone. Also, the Reservoir shall be sampled at a distance beyond significant influence of the discharge.

(7) Lake Granbury shall be sampled near the letdown discharge and at a distance beyond significant influence of the discharge.

(8) Groundwater samples shall be taken when thi source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge. properties are suitable for contamination.

(9) The dose shall be calculated for the maximum organ and age group, using 8 the methodology and parameters in Part II of the ODCH.

(10) If harvest occurs more than once a year, sampling shall be performed during cach discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

i

!- REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-39 I

TABLE 3.12-2 Ftportirg levels for fbdioactivity Canrtratias in Efvirumstal Smples h 1ATER AIFHDE PARTIQA. ATE - FI91 MILK RID FRIUCTS

@ /# LYSIS (pCi/1) OR GGS (pCih0) (pC1/kg. w t) (pCi/1) (gCi/kg. w t) 9 m

o g H-3 m.Q10(*)

tti-54 1.0)0 30.000

[ Fe @ G 10.000 3 Co-58 1.000 30.000 d Co4D 300 10.000

_. 2n e x0 m.aD g Zr4b% @

o I-131 2(**) 0.9 3 100 N

Cs-134 30 10 1.000 fD 1.0CD Cs-137 50 m 2.000 70 2.0(D Bo-La-1-10 3)0 300

- (#') For drirkirg strr saples. This is O CfR Part 141 value. If m &irkirg wter pattwy exists, a valm of 30.000 pCi/l ny te trM.

w h (*) If no tirkirg wter pattwy exists, a valte of a pCi/l my te ussi.

A CD

TELE 4.12-1 Detectim Captilities for Erwirumrital Sarple Aulysis (1)(2) n 11wr Limit of Detectim (LID) (3)

S-o E

5 WATER AIPBORE P/MIO1 ATE FISi MIlX RID PRIUCTS SEDIle1T y #eLYSIS ($1/1) OR GASES ($i/m3) (;Ci/kg, wet) (pCi/1) (pCi/kg. wet) (%i/kg. drf)

N c-- Gruss Beta 4 0.01 C] H-3 EE*

m Ftr54 15 130 Fe @ 30 260 E Co e. m 1s im In-5 30 260 Zr4bs 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 @ 150

[ Cs-137 18 0.06 150 18 80 180 H Ba-la-140 15 15 w

'5

If re Tirtirg wItw pathe exists a value of 30CD pCi/l my te usa 1.

- If to d'inkirg witer pathe exists, a value of 15 pCi/l nay be use1.

A CO

. _ __________.___._.______m

I.A3J,E 4.12-1 (Continued)

IAPLE NOTATIONS (1) be . t does not mean that only these nuclides are to be considered.

Otner pnks that are identifiable, together with those of the above nuclides, shall also be analyzed and rcps ted in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) Th9 LLD is defined, for-purposes of these specifications, as the smallest concentrations of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

4.66sb LLD = E V Y exp (-Aat) 2.22 Where:

LLD = the "a priori" lower limit of detection (picocurie per unit mass ,

or volume),

sh= the standard deviation of the background counting rate or of the c5unting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec-1),and At = the elapsed time between the midpoint of sample collection and the time of counting (s).

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

REV. 8

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-42

TABLE 4.12-1 (Continued)

IABLE NOTATIONS (Continued)

(3) Continued It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fcct) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable 3,rnall sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLO's unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-43

Ee010 LOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROL S -

3.12.2 in accordance with CPSES TS 6.8.3.f.2, a land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

C greater than 50 m2 (500 ftt) producing broad leaf vegetation.

APPLICABILITY: At all tines.

ACTION:

a. With a Land Use Census identifying a location (s) that y: elds a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, pursuant to Control 6.9.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report,

b. With a Land Use Census identifying a location (s) that yields a 1 calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) within 30 days, to the Radiological Environmental Monitoring Program given in Part Il of the 00CM.

The sampling locations having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Control 6.14, submit as a part of or concurrent with the next Semiannual Radioactive Effluent Release Report a complete, legible copy of the entire OOCH including a revised figure (s) and table (s) for the ODCM reflecting the new location (s).

c. _The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey,. aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operatint " ? ort pursuant to Centrol 6.9.1.3.

Broad leaf vegetation scmpling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1, Item 4.c. shall be followed, including analysis of control samples.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-44

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4 12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with CPSES TS 6.8.3 f.3, analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samplec required by Table 3.12-1.

APPLICABILITY: At all times.

. ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0UIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in Part 8 II of the 00CH. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-45

, . , , _ .a. 4 i.a e * ** *#" ##-'

b

.j', pv c

t

-BASES t

REV. 8 COMANCriE . PEAK -~. UNITS 1 AND 2 PART I B 3/4-0

._ . _ _,-.~.. _

i

. INSTRUMENTATION l BASES

-3/4.3.3.4 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid' effluent instrumentation is provided to monitor and control,-as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The 8 Alarm / Trip Setpoints for these instruments shall be calculated and adjusted-

.in accordance with the methodology and parameters in Part II of the OOCH to ensure that the a'larm/ trip will occur prior to exceeding the limits of 10 CFR Part 20. -The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to -10CFR 50.

.3/4.3.3.5 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and. control, as applicable. the releases of radioactive materials in

_ gaseous effluents during actual or potential releases of gaseous effluents. 1 The Alarm / Trip Setpoints for these instruments shall be calculated and 8 adjusted in-accordance with the methodology and parameters in Part II of the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 1 64 of Appendix ~A to 10 CFR-Part 50.

3/4.3.3.6 METEOROLOGICAL INSTRUMENTATION

'~

The OPERABILITY of the meteorological instrumentation ensures that

-sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to.the atmosphere. This capability is required to

-evaluate the:need for initiating protective measures to protect the health and safety of. the public and is consistent with the recommendations of the second-proposed Revision 1--to Regulatory Guide 1.23, "Onsite Meteorological Programs," April ~1986.

p REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-1 7

I l

INSTRUMENTATION l l

BASES 3/4.7.15 SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 10CFR70.39(c) limits for plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sou'rces within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

REV. 8 L COMANCHE PEAK UNITS 1 AND ' PART I B 3/4-2

T3/4.11- RADIMCTIVE EFFLUENTS BASES 3 /4 .11.~ 1 LIOUID EFFLUENTS 13/4.11.1.1' CONCENTRATION This control is provided to ensure that the concentration of 8 rcficactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2)-the limits of 10 CFR Part 20.106(e) to the-population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is-the controlling radioisotope and its MPC in air-(submersion) was converted to an equivalent concentration in water using the methods described-in International Commission on Radiological Protection (ICRP) Pubilcation 2.

This control applies to the release of radioactive materials in liquid effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid

. waste samples are' tabulated in terms of the lower limits of detection

(LLDs). . Detailed discussion of the LLO and other detection limits can be found in Currie, L.A., " Lower Limit of Detection Definition and Elaboration of a' Proposed Position for Radiological Effluent and Environmental Measurements." NUREG/CR-4007 (September 1984), and in the HASL Procedures

~ Manual, HASL-300, 314.11.1.2 DOSE This= control is provided to imp, wnt the requirements of Sections

.II.A, III.A and IV.A of 10CFR50, Appendix I. The Control implements the guides; set forth in Section II'A'of Appendix 1. The ACTION statements pr_ ovide the required operating flexibility and at the same time implement the-guides' set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably-achievable." Also, for fresh water

. -sites with drinking water supplies that can be potentially affected by

~p lant operations, there is reasonable assurance that the operation of the

' facility will not result in radionuclide concentrations in the finished

' drinking water that are in excess of the requirements of 40CFR141. The 8 Ldose calculation methodology and parameters in Part II of the 00CM implement the requirments in Section III.A of Appendix I that conformance with the guides of Appendi_x I be shown by calculational' procedures based on

models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part II of the the OOCH for 8 calculating the doses due to the actual release rates of radioactive REV 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-3

RADI0 ACTIVE EFFLUENTS l

BASES , ;

QQ E (Continued) !

materials in liquid effluents-are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113

" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix I," April 1977.

This control applies to the release of radioactive sterials in liquid 8 effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.

3/4.11.1.3 LIOUID RA0 WASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 ' 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 anc e design objective given in Section 11.0 of Appendix I to 10 CFR Pa- 50. The specified limits governing the use of appropriate portions of ..e Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.

This control applies to the release of radioactive materials in liquid 8 effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit I and Unit 2. 8 3/4.11.1.4 LVW POND RESIN INVENTORY The inventory limits of the LVW Pond are based on limiting the consequences of an uncontrolled release of the .- nd inventory. The expression in Control 3.11.1.4 assumes the ponc inventory is uniformly mixed, and that the pond is located in an unrestricted area as defined in 10 CFR Part 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR Part 20 applies. This expression limits the total quantity of radioactive materials in resins discharged to the LVW Pond to a value such that the average concentration in the resins, calculated over the total volume of resins in the pond, will not exceed the Maximum Permissible Concentrations (HPCs) specified in 10 CFR 20, Appendix B, Table II, Column

2. Because Control 3.11.1.1 limits the concentration of liquid effluen

from other pathways to the LVW Pond to the 10 CFR 20 HPC values, also limiting the average concentration in resins to the HPC values will asscr-that the average concentration in the pond from all sources, calculated over the total volume of the pond (liquid and resins), will not exceed tne i

10 CFR 20 MPC values.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-4 i

RADI0 ACTIVE EFFLUENTS BASES LVW POND RESIN INVENTORY (Continued) 7 The batch limits of slurry to the LVW Pond assure that radioactive 7 material in the slurry transferred to the Pond are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in Control 4.11.1.4 assures no batch of slurry will be transferred to the Pond unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than'the ratio of the 10 CFR Part 50 Appendix I, Section II.A total body level to the 10 CFR 20.105(a), whole body dose limitation, or that:

y b

'" C ( 500 mrems/yr3 mrems/yr = 0.006 j 3 where:

c radioactive slurry c j= theUNRESTRICTEDAREgncentrationforradionuclide"j" POND, in microcuries/ milliliter, entering 7

and C 10 CFR 20 Appendix B j= concentration for single radiont:clide "3" Table TI, Column 2, in m'crocuries/mIlilliter. 7 The average concentration of radioacti-e materials in a particular 2 batch of resin slurry released to the LVW Pond is dependent upon the sit'rry volume-to resin weight ratio. Additionally, the wet drained slurry density is approximately 1 gm/ml and the absorption characteristics for gamma radiation are essentially that of water. Therefore, fGj( ml/gm) < 0.006 Q

% _A (0.006 R pCi/ml

U/9*

j c 3

where the terms are defined in tuntrol 4.11.1.4. 2 The batch limits provide assurance that activity input to the LVW Pond 7 will be minimized, and a means of identifying that the radioactive material released is within the inventory limitation of Control 3.11.1.4.

COMANCHE PEAK UNITS 1 AND 2 I B 3/4-5

3 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.7 GASEOUS EFFLUENTS 314,11.2.1 DDSE RATE This control is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 to UNRESTRICTED AREAS.

The annual dose limits are the doses associated with the concentrations of 10CFR20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to alnual average concentrations exceeding the limits specified in Table II of 10CFR20, Appendix B (10CFR 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The 8 methodology for calculating. doses for such MEMBERS OF THE PUBLIC shall be given in Part II of the ODCM. The specified release rate limits restrict, at all times. the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body o~ to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.

This control applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LL0s and other detectier limits can be found in Currie, L.A., " Lower Limit of Detection Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements." NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-303 i

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-6

R!al0ACllyE EFFLUENTS SASES 3/4.11.2.2 DOSE - NOBLF,__QAE S This control is provided to implement the requirements of Sections II.B. 11! A and IV.A of 10CFR50, Appendix 1. The control implements the guides set forth in Section 1.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radloactive material in gaseous effluents to UNRESTR.CTED AREAS will be keot "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of AppSndix 1 that confornance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure of a &

HEF3ER OF THE PUBLIC through appropriate pathways is unlikely to be L substantially underestimated. The dose calculation methodology and l8 parameters established in Part 11 of the OOCH for calculating the doses l due to the actual release rates of the radioactive noble gases in gasoous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseou: Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977 The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

. This control applies to the release of radioactive materials in paseous effluents from each unit at the site. The gaseous effluents from the 8 shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.

REV 8 C0HANCHE PEAK UNITS 1 AND 2 PART I B 3/4-7

.-____--__-------------a - - - - - - _ - - - - - - - - - -"

pg l,QA_plVE EFFLUENTJ BASES ,,,__

3fjLjl.2.3 DOSE - 100lNE-131.1.QQ.LNE-133. TRITIUM, AQ,R!d[QA_(ly[

MIfR_l Al. IN PARTICULATE FORM This control is provided to impler.ent the requirements of Sections II.C. I!!,A, and IV.A of 10CFR50. Appendix 1. The Controls are the guides set forth in Section ll.C of Appendix 1. The ACTION state e ts provide the requi'ed operating flexibility and at the same time implement the guides 1 set forth in Section IV.A of Appendix ! to assure that the releases of !

radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The 00CM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix ! that conformance with the guides of Appendix !

be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is miikely to be substantially underestimated. The calculational methodology 8

.ad parameters specified in Part 11 of the 00CM for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releasts from !icht-Water-Cooled Reactors," Revision 1. July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specification for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days is dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionucludes, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals grue with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the 8 shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.

REV. 8 C0f% CHE PEAK UNITS 1 AND 2 PART I B 3/4-8

E8010 ACTIVE EFFLUENTS HAES _ ___ _,

3/4.ILL 4 GASEQuS_Ma@lTE_T.EEATMENi 5YSTEfj The OPERABILITY of the WASTE GAS HOLOUP SYSTEM and the PRIMARY PLANT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatnent prior to release to the environment. Tne requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section 11.D of Appendix ! to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specifiad as a suitable fraction of the dose design objectives set forth in Sections 11.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the 8 shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-9

RADIDACTIVE EFFLUENTS BASES _

1/3111.4 TOTAL DOSE This control is provided to meet the dose limitations of 40 CFR Part l 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The ,

control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from urahtum fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containir.g up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1. and if direct radiation doses

' o+ +he units (including outside storage tanks, etc.) are kept sr.11 The

/;cti,1 Report will describe a course of action that should result in the 11E1tation-of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radious of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405(c), is considered to be a timely request and fulfills the

. requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-10

3/4.12 RADIOLOGICAL ENVIROWENTAL MONITORING SASES ,

3/a.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of HEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of A.;pendix 1 to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measureable concentrationt of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmentti exposure pathways. Guidance for this monitoring program ts provided by the Radiological Assessmant Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmer;tal sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine ervironmental ceasurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and c.her detection limits, can be found in Currie, L. A., " Lower Limit of Detection: Definition and Elaboratien of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the .'

HASL Procedures Manual HASL-300.

3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix ! to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the gardea was used for growing broad leaf vegetation (i.e., similar to lettuct and cabbage), and (2) a vegetation yield of 2 kg/m2, REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-11

RADIOLOGICAL ENVIRONMENTAL H0:41TORING BASES 3/4.12.3 INTERLABORATORY CQY?ARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy or the measurements of radioactive ma*.erials in e

environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Part 50.

l l

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-12

l' i

SECTION 5.0 DESIGN FEATURES COMANCHE PEAK - IINITS 1 AND 2 PART I 5-0 g

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f. - . . . _ . . - . . . - __ _ .. _. _ . - _ _ _ __ _

t 1,,0 DESIGN FEATURES HAP DEFINING UNRFSTRICIED AREAS AND EXCLUSION AREA BOUNDARY FOR RADIOACTIVE GASEOUS AND LiOUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED ARLAS within the SITE BOUNDARY that are accessible to HEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3.

The definition of UNRESTRICTED AREA used in implementing these Controls has been expanded over that in 10 CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the Exclusion (fenced) Area Boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a. l t

i CDMANCHE PEAK UNITS 1 AND 2 PART I 5-1 l

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SECTION 6.0 ADMINISTRATIVE CONTROLS

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REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I 6-0 l

a h_

- - _ - . _ - ~__ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _

1 i

ADMINISTRATIVE CONTROL 5 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING PEPORT*

6.9.1.3 Routine Annual Radiological Environmental Operating Reports 8 covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the I radiological environmental surveillance activities for the report period, including a comparison with preoperational studies and with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Control 3.12.2 The Annual Radiological Environmental Operating Reports shall include 8 the results of analysis of.all radiological environmental samples and of all environmental rad'ation measurements taken during the period pursuant to the locations specified in Table 3.1 and Figure 3.1 in Part 11 of the Offsite Dose Calculation Manual, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The r5 ports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps ** covering all sampling locations' keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1,; discussion of environmental sample measurements.that exceed the reporting levels of Table 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

A single submittal may be made for both units. 8

- One map shall cover stations near tb? SITE BOUNDARY; a second shall include the more distant stations REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 6-1

.. _.- _ . __ ._m . __ _ ._ _ . _ - - _ _ . _ _ _ _ _ _ _ _ . . _ . _ . _ _ _ _ _ _

ADMf NISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering 8 the operation of the units during the previous 6 months of operation shall be submitted within 60 days aftn January 1 and Juif 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Semiannual Radioactive Effluent Release Reports shall include a summa.y of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21

" Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from <

Light-Water-Cooled Nuclear Power Plants," Revision 1. June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof, i For so'id wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, Tvn C, large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde).

The Semiannual Radioactive Effluent Release Report to be submitted

- within 60: days after January 1 of each-year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and ;

precipitation (if measured), or in the form of_ joint frequency distributions of wind speed, wind direction, and atmospheric staoility.**

This same report shall include an assessment of'the radiation doses due to the radioactive liquid and gaseous effluents releated from the unit or statinn during the previous calendar year. -This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUPLIC due to their activities inside theSITEBOUNDARY(Figure 5.1-3)durino'hereportperiod. All assumptions used in making these assessments, i.e., specific activity, exposure. time, and location, shall be included in.these reports. -Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, is determined by sampling frequency and measurement, shall be used for s determining the gaseous patnway doses. The assessment of radiation doses 8 shall be performed in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL-(00CM).

-A single submittal may be made for both units. The submittal should 8

~

combine those sections that are ccmmon to both units'at the station.

In lieu of submission with the Semiannual Radioactive Effluent Release 4 Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART 1 6-2 P

t um-3 *

r -r 'v- - - = w*:e-m -w-- --e-~wv-++- m~--+- % w - -- ~4--+----wnmr-sv=--vmw-------=r --e.vm- -*=-w----+----. m,==-- - -- + - -

I ADMINISTPATIVE CONTRDLR ,__ _

SEM] ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed HEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel Cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190,

" Environmental Radiation Protection Standards for Nuclear Power Eperation."

Acceptable methods for calculating the dose contribution from 11guid and gaseous effluents are given in Regslatory Guide 1.109, REV. 8, October 1977.

The Semiannual Radioactive Effiuent Release Reports shall include a 8 list and description of unplanneo releases, from the site to UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Sem hnnual Radioactiv; Effluent Release Reports shall include a listing of new locations for case ca :ulations and/or environmental monitoring identified by the Land Vi> Census pursuant to Control 3.12.2.

The Semiannual Radioactive Effluent Release Reports sha'.1 also include 1 the following: an explanation as to why the inoperability of liquid or gastous effluent monitoring instrumentation was not corrected within the time specified in Controls 3.3.3.4 nr 3.3.3.5, respectively; and a description of the events leading to lir!uid holdup tanks or gas storage tanks exceeding the Technical Specification limits.

6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)

Changes to the ODCH:

a. Shall be documented and records of reviews performed shall be !

retained as required by Specification 6.10.3.o. 1his documentation shall contain; {

1) Sufficient information to support the change together with the appropriate analyses cr evaluations justifying the change (s)and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,

b. Shall become effective idter review and acceptance by the 50RC 1 and the approval of tne Vice President, Nuclear Operations.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 6-3

ADMINISTRATIVE CONTROLS

.6.14 OFFSITE DOSE CALCULAljfN MANUAL (ODCM) (continued)

c. Shall be submitted to the Connission in the form of a complete, legible copy of the entire ODCH as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by rarkings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

REV. 8 -

COMAMCHE PEAK UNITS 1 AND 2 PART I 6-4

_ w --- - -,--,-- --- , - - - - ------- - - - - - - -- - - - - - - - - - - - -

PART 11 CALCULATIONAL METHODOLOGIES s

- _ - ___ ______- _ _ - _ _ _ . _ _ _.____m_ _ _ - - - - - _ - _ _ - _ . _ _ ~M

SECTION 1.0 LIQUID EFFLUENTS The Comanche Peak Steam Electric Station (CPSES) is a 2 unit nuclear generating facility. Each unit is a 1150 MWe, 4-loop. Westinghouse 8 PWR. The units share a common primary liquid radwaste processing system. CPSES is located on Squaw Creek Reservoir (SCR), which serves as the point of supply and discharge for the plant Circulating water. Radioactive liquid effluent releases from the primary radwe.te processing system are batch type releases, from the Laundry Holdup & 7 Honitor Tanks (LHHT) and Waste Monitor Tanks (WMT), discharged to SCR via the Circulating Water Discharge Tunnel. Potentially radioective 8 liquid effluent releases from secondary systems include a contiruous release from the Turbine Building Sumps (TB Sump), and batch releases from the Component Cooling Water Drain Tanks (CCWDT), and the Condensate Polisher Backwash Recovery Tanks (CPBRT). These secondary pathways from each unit are normally discharged to the common Low Volume W'ste (LVW) Pond for chemical traatment. The LVW Pond normally 'ischarges to SCR via the circulating Water Discharge Tannel. 7 Alternatively, secondary waste streams me) be routed to the common 8 Waste Water Holdup Tanks (WWHT). The WWHTs may be released on a batch basis to the LVW Pond or to SCR vic the Circulating Water 7 Discharge Tunnel, depending on the levels of radioactivity present.

Table 4.11-1 of Part I of this document requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste strear in concentrations that exceed the limits of 10 CFR 20 Appendix B Table II, Column 2. Also, releases from the Station Servica Water (FSW) 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 :.re 8 isolated and thoroughly mixed by mechanical mixing or recirculating the tank contents, prior to sampling, to assure representative sampling. The recirculation or mixing times nece!.sary to assure representative sampling shall be specified in station procedures.

Rev. 8 C0HANCHE PEAK - UNITS 1 AND 2 PART 11 1-1

i A wummary of all liquid effluent release sources, volumes, flow rates, 7 and associated rad htion 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 7 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 RADIQLOGICAL EFFLUENT CONTROL 3/4.11.1.1 8 COMPLIANCE To demonstrate compliance with 10 CFR 20.106, 00CM 7 Radiological Eff luent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained 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 Pond is located in an UNRESTRICTED 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 II, Column 2, then all inputs to the LVW Pond are sampled and checked for compliance with 10 CFR 20. The following methodology is used to determine compliance with these limits.

I Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-2

1.1.1 Isotnoic Concentration AL the Waste Tank Determine the isotopic concentration in waste stream to be released:

ECi= ICg + (Ca + Cs + Ct + Cre) i g [Eq 1-1)

Where: ICj = Sum of the concentrations of each i radionuclide,intherelease(uCi/ml) 7 ICg= Sum of the concentrations of each measured g gamma emitter, g, (uC1/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 7 analyzed for gross alpha only)

Cs = Concentration of 895 r and 90S r as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent 7 Control 3/4.11.1.1 Table 4.11-1.

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

CFe= Concentration of 55F e as measured in 7 the most recent 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 /

source are.shown in Table 1.1. For pre-releass 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 8

! is used for pre-release calculations, no setpoint is required for the flow measuring device for the effluent release line.

l Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-3 l

_ - . -- ~ . - - -. - . .

1 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 j Dilution factor (RDF) to the Actual Dilution Factor (ADF) is 8 maintained 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 Licuid Effluents

a. Discharges to SCR via Circulating Water Discharge Tunnel I Since liquid effluents from the radwaste treatment 7 system. Waste Water Holdup Tanks and the LVW Pond are mixed with Circulating water prior to being discharged to Squaw 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. Thu is determined from the Ingersoll-Rand pump curves (Fig. 1.2) which indicate a flow rate 7 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 7

[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). 7 As an additional consideration, the available dilution flow 7 for any release may be corrected to allow for. simultaneous l releases from the Radwaste Processing System, a Waste Water i Holdup Tank, and/or the LVW Pond (i.e., a radwaste system l

I tank, a Waste Water Holdup Tank, and the LVW Pond may be discharged simultaneously.) For simultaneous releases, the Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-4 i

_ _ _ -- . _ _ _ ~. . - - _ - . ___ _ __ . ___.

available dilution flow for any release is reduced by the 7

required dilution flov for any other concurrent releases.

Also, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isotopes. It is 7 therefore necessary to account for recirculation of previously discharged radionuclides. This is accuplished s', follows:

F' = F (1 - I(C'j/MPCj)) [Eq 1-3] 7 Where: F'= Adjutted Circulating Water Flow Rate 7 l C'i = Concentration of radionuclide i in de 7 Reservoir (uCi/ml) as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Contivl 3/4.12.1. Table 3.12.1. This sample is taken at the Circulating water intake structure as indicated by location SW6 on-Table 3.1 and Figure 3-1_of this manual.

HPCj* =

Maximum Permissible Concentration of 7 Radionuclide i F= (275,000 gpm/ pump) x (# of pumps) x 0.9 7 NOTE: If C'j is less than LLD then F' = F and no adjusted 7 flow rate need be considered in the calculation of ADF. The LLD values used for this determination shall be the LLD valves for water given in Radiological Effluent Control 3/4.12.1, Table 4.12-1.

b. Discharges to the LVW Pond 7 Secondary release sources are discharged directly to 7 the LVW Pond with no dilution (i.e., F=0).

7 1.1.4 Actual Dilution Factor (ADF)

ADF is the ratio of the effluent flow rate plus.the 7 Circulating water flow rate divided by the effluent flow rate, t Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 1-5

ADF = (f + F)/f [Eq. 1-4] 7 Where: f = effluent flow rate (gpm) 7 F = dilution flow rate (gpm) 7 NOTE: If ravioactivity 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). 7 Also, if simultaneous releases are occurring, the 1 available dilution flow shall be reducad by the

~

required dilution flow for any otter concurrent release.

1.1.5 Reauired Dilution Factor (RDF1 The required dilution factor ensures that the maximum permissible concentrations expressed in 10CFR20, Appendix B, Table II, Column 2*, and a total concentration of dissolved or entrained noble gases of 2 x 10-4 uCi/mi are not exceeded

, during a discharge. The required dilution factor includes a 1 safety factor of 2 to provide a margin of assurance that the instantaneous concentration limits are not exceeded.

HPCs listed in 10CFR20 give values for each isotope in both a soluble and insoluble form. The lowest value for each isotope should be used. A value of 2 x 10-4 uCi/ml for dissolved or entrained noble gases shall be used.

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 1-6

l 1

l l

~

i RDF = (tj (Cj/MPCj)) x SF 7

=

(I g (C g/MPCg) + (Ca/MPCa + Cs/MPCs + 7 Ct/MPC t + C Fe/MPCF e)) x SF [Eq 1-5) 7 Where: HPCj* = Maximum Permissible Concentration of 7 Radionuclide i 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 7 limits 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 C 1w in Section 1.2.1.

1.1.6 10 CFR 20 Como11ance Compliance with 10 CFR 20 is demonstrated if the Actual 7 Dilution Factor (ADF) is greater than or equal to the Required DilutionFactor(RDF),or:

EQE 5 1.0 [Eq 1-6] 7 ADF l

l See footnote on page II 1-6.

l Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-7

1.2 33diation Monitor Alarm S1faginh 7 1.2.1 Primary Licuid Effluent Monitor XRE-5253 7 To ensure that releases from the primary radwaste pr> essing 7 system do not exceed 10 CFR 20, Appendix B, Table !!, Column 2 limits at the point of release to the UNRESTRICTED AREA, a radiation detector (XRE-5253) monitors discharges to the Circulating Water Discharge Tunnel. XRV-5253 is the 8 discharge isolation valve controlled by XRE-5253. The isolation valve shuts automatically if the detector alarms on 7 high radiation or a detector operation failure occurs. The i methodology for_ determining the setpoint for detector XRE-5253 is given below. It should be noted that the liquid effluent monitor setpoint values determined using the methodology from this section will be regarded as upper bounds for the actual setpoint adjustments. That is, sctpoints may be established at values lower than the calculatea 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.

C1 w = (ADF/RDF) x ! C g (Eg 1-7] 7 9

Where: Cw=

1 The liquid waste effluent monitor alarm setpoint. This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC-level releases (uCi/ml).

All other variables are as previously defined.

i l

i Rev. 8 l COMANCHE PEAK - UNITS 1 AND 2 PART II 1-8 l

When considering the mixture of nuclides in the liquid 7 effluent stream in terms of detector sensitivity, the mor.t 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 i probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant. In fact between 137C s and 60C o, 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 BUILDING SUMP EFFLUENT RADIATION MONITOR 1RE-5100 AND 8 2RE-51M The purpose of the turbine building sump monitor (1RE-5100 and 8 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 to the turbine building sump 7 are from the secondary steam system, activity is expected only if a significant primary-to-secondary leak is present. Since 8 detectable radioactivity is not normally present in the Turbinv Building Sumps, 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 7 l further data can be collected. Then, if this setpoint is exceeded, the monitor will direct control valves to divert the l

j Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 1-9 l

turbine building sumps discharges from the LVW Pond to the 8 Waste Water Holdup Tanks where the effluent can then be sampled and released in a baten mode to Squaw Creek Reservoir, if required by Radiological Effluent Control 7 3/4.11.1.1. Table 4.11-1. When radioactive materials are B detected in the Turbine Building Sumps, a setpoint then may be j established for 1RE-5100 or 2RE-5100 using the methodology in l Section 1.2.1 to ensure that 10 CFR 20 MPC limits are not exceeded in discharges to the LVW Pond.

1.2.3 SERVICE WATER EFFLUENT RADIATION MONITORS 1RE-4269/4270 AND 8 2RE-4269/4270 The concentration of r4dioactive material in the service water 7 i effluent line normally is expected to be insignificant.

Therefore, the monitor alert alarm setpoint r1ould be !

established as close to background as practival to prevent '

spurious alarms and yet alarm should an inadvertent release occur. To this end, the alarm setpoint will be initially established at three (3) times background until further data can be collected. If this effluent stream should become contaminated, radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows:

Csw = (I g Cg ) + OF [Eq 1-0) /

Where: Csw = the Service Water effluent monitor alarm 7 setpoint

j. Cg =

the concentration of each measured gamma 7 emitter g, observied in the effluent (uCi/ml)

DF =

Ij(C 1/MCPj) = the dilution factor 7 required to ensure maximum permissible concentrations are not exceeded.

For this release pathway no additional dilution is available.

Therefore, if the calculated DF is greater than 1,0, any 7 l releases occurring via this pathway will result in a violation l

i Rev. 8 l

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-10 L . . . - - - _ - . _ ,

of Radiological Effluent Control 3/4.11.1.1. If radioactivity is detected in this release st eam, do.7s due to releases frcm this stream shall be calculateu in accordance with the methodology given in Section 1.3, with the near field average dilution factor, F k, equal to 1.0, 1.3 00SE 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 4t 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 Waste Monitor Tanks, Laundry Holdup &

Monitor Tanks, Waste Water Holdup Tanks, and the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir. Although the LVW Pond is located in an UNRESTRICTED 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 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 calendaryear)willbecalculctedusingtnefollowing equation:

OT= IOk + I O(lake)m [Eq 1-91 k m Where DT= the dose commitment to the total body or any organ due 8 to all releates during the desired time interval from allreleasesources(mrem).

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

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-11

0(lake)m = the dose commitment received by the total body or any 7 or any 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). 7 .

.o oemonstrate 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 Liouid 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*E i ArtkCik i Fk [Eq 1-10] 7 Where: t =

k the time duration of the ~ fase k (hrs) 7 Cik = the isotopic concentre' JCi/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 list 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 ficw rate is based on the actual average flow into the Circulating water during the release.

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART-II l-12

Fk averaae undilu'. eft liauid efflyent floe rate l7 circulating water flow rate Ar= i the site related i:gestion dosa commitment 7 factor for the total body or any organ,r , for '

each identified gamma or beta emitter (mrem /hr per UC1/ml). Ai ris calculatad as follows:

Aj = 1.14x105 (Uw/Dw + UrbFj) DFj

[Eq 1-11]

Where: 1.14x105= Unit conversion factor 7 Uw = adult water consumption, 730 liters /yr. 7 Ur = adult fish co tumption, 21 kg/yr. 7 BFj = bioaccumulation factor for radionuclide 7 i, in fish from Table A-1, Ref. 2 (pCi/kg per pCi/1)

DFj = adult dose conversion factor for 7 radionuclide i, from T6 ole E-11, Ref. 2 (mrem /pCiingested)

Ow = dilution factor from the near field area 7 within one-quarter mile of the releat.e point to the potable water intake f;r the adult water consumption; 1.0 for CPSES (unitless).

Calculated values for Ajr are given in Table 1.2.

1.3.2 Calculation of Dose Due to Radionuclide Builduo in the Lake The dose contribution due to buildup of previously discharged 8 radionuclides in the lake must be considered in the committed dose calculation only if the radionuclides are detected in the water of Squaw Creek Reservoir or in fish from Squaw Creek 7 Reservoir. The contribution to the total dose due to this buildup is determined as follows:

0(lake)m = 1.14x10-4(!jDFj(C'iwUw + C'jfur ))t 7

[Eq 1-12]

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-13 w --( +,--w ---e-- ,s.,,,

Where: 1.14x10-4 = units conversion factor 7 C'jw = concentration of radionuclide i in the 7 reservoir as measured it the Circulating water intake structure shown as location SW6 on Table 3.1 and Figure 3.1 of this manual (pCi/1)

C'ir = concentration of radienaclide i in fish 7 sampled from Squaw Creek Reservoir from location F1 on Table 3.1 and Figure 3.1 of this r.nual (pCi/kg).

t = 74e trs (31 days) or other time period of 7 interest (hr)

All other variable are previously defined. 7 NOTE: This calculation is only required if activity is 7 detected in 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 00SE PROJECTIONS FOR LIOUID EFFLUENTS 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 7 doses due to the liquid effluent from each reactor unit to UCWTED AREAS would. exceed 0.06 mrem total body or 0.2 mre,t U .any organ in a 31-day period. The following calculational rethod is provided for performing this 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 7 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-14

releases during the period for which the projection is made. 7 If the projected dose for a unit exceeds 0.06 mrem total body 8 or0.]mremanyorgan,appropriateportionsoftheLiquid 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 1

1.5 DEFINITIONS OF COMMON LIOUID EFFLUENT PARAMETERl 7 Iff3 DEFINITION ADF ActualDilution' Factor (unitiess)'. This is defined as the 7 ratio of the effluent flow rate plus the circulating water flow rate divided by the effluert flow rate.

Ari -The site related ingestion dose commitment factor to the 7 total body or cny organ, r , for each identified gamma or beta emitter, i. (mrem /hr per UCi/ml)

BFj Biaccumulation factor for radionuclide, i, in fish from 7 Reg. Guide 1.109. (pCi/kg per pCi/1)

Ca The concentration of alpha emitters in liquid waste as 7 measured.in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)

Cre The concentration of 55F e in liquid waste as measured in 7 the-. analysis of the most recent quarterly composite sample required by Radiological Effluent Control.3/4.11.1.1, Table.4.11-1. (uCi/ml) cg The concentration of each measured gamma emitter, g in the 7 waste tank as measured in the analysis of the sample of each batch as required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1 (uCi/ml)

Cj The concentrations of radionuclide, i, in the waste tank. 7 (uCi/ml)

C'i The concentration of radionuclide i in the Reservoir as 7 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 on Table 3.1 and Figure-3-1 of this manual. (uCi/ml)

C'ir The concentration of radionuclide i in fish sampled from 7 the reservoir from location F1 on Table 3.1 and Figure 3-1 L of this manual (pCis g).

l Cik The isotopic concentration of radionuclide i found in the 7 pre-release sample for batch release k. Concentrations are determined primarily from gamma isotgpic gnalysis of gheliquideffluentsample. For 895 r, 9uSr, JH, 5F e and alpha emitters, the last measured value will be.

used. (uCi/ml) l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-16

C'iw The concentration of radionuclide i in the reservoir as 7 measured at the Circulating water intake structure shown as ,

location SW6 on Table 3.1 and Figure 3-1 of this manual (pC1/1).

Cw1 The liquid waste effluent monitor alarm setpoint. This 7 corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC-level releases. (uCi/ml)

Cs The concentration of 895 r and 90S r in liquid waste as 7 measured in the 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 Service Water effluent monitor alarm setpoint. 7 (uCi/ml)

Ct The concentration of 3H in liquid waste as measured in /

the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1 (uCi/ml)

DFj Adult dose conversion factor for radionuclide, i, from Rag, 7 Guide 1.109 (mrem /pCi ingested)

Ok The. dose commitment received by the total body or any organ 7 during the duration of batch release k of liquid effluents. (mrem)

D(lake)m The dose commitment received by the total body or any organ -7 during a desired time period, m, due to the buildup in the late of previously discharged radionuclides. (mrem)

DT The total dose commitment to the total body or any organ 7 due to all releases of liquid effluents during a desired time interval. (mrem)

Dw Dilution factor,'from the near field area within 1/4 mile 7 of the release point to the potable water intake for adult water consumption, 1.0 for CPSES (unitless) f Effluent flow rate. (gpm) 7 F Circulating water flow rate (or dilution flow rate). 7 (gpm)

F' . Adjusted Circulating water flow rate to account for builde l 7 of radionuclides in the Circulating water due to previout !

releases. (gpm) j REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 1-17

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

MPCa Maximum Permissible Concentration

of a mixture of 7 unidentified alpha emitters. (uCi/ml)

MPCF e Maximum Permissible Concentration

of 55F e. (uCi/ml) 7 MPC g Maximum Permissible Concentration

of each identified gamma 7 emitter, g. (uCi/ml)

MPCj Maximum Permissible Concentration

of radionuclide, i. 7 (uCi/ml)

MPCs Maximym Permissible Concentration

of a mixture of 89S r 7 and 9uSr. (uCi/ml)

HPCt Maximum Permissible Concentration

of tritium (3H ) 7 (uCi/ml) ,

SF . Safety Factor.of 2. Used in the calculation of the 7 Required Oilution Factor (ROF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are not exceeded. 7 RDF Required Oilution Factor (unitiess). This is defined as 7 the dilution factor that ensures the maximum permissible isotopic concentrations expressed in 10CFR20, Appendix B, Table II, Column 2, are not exceeded during a discharge.

tk The time duration of batch release k. (hours) 7 Ur Adult fish consumption. (kg/yr) 7 Uw Adult water consumption. (liters /yr) 7

MPCs are given in 10CFR20 Appendix B, Table II, Column 2.

Values are given for each isotope-in both a soluble and 7 insoluble form.

each isotope should Themostconservative(lowest}valuefor be used. A value of 2x10' uCi/ml for dissolved or entrained noble gas shall be used.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-18

l l

TABLE 1.1

SUMMARY

OF LIOUID RELEASE PATHWAYS

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

WMT-1 Batch 100 5340 XRE-5253 WMT-2 Batch 100 5340 XRE-5253 LHMT-1 Batch 100 5875 XRE-5253 LHMT-2 Batch 100 5875 XRE-5253 WWHT-1 Batch 200 25000 None WWHT-2 Batch 200 25000 None LVW Pond Continuous 1600 -

None

2. RELEASES TO THE LVW POND Release Source Release Type Max Flow Max Vol Monitor Rate (aom) (aal)

CPBRT Batch 25 8500 None CCWDT (Unit 1) Batch 40 2300 None 8 CCWDT (Unit 2) Batch 40 2300 None 8 WWHT-1 Batch 200 25000 None WWHT-2 . Batch 200 25000 None TBSump2 (Uniti Continuous 300 -

1RE-5100 TBSump4 (Unit 2 Continuous 300 -

2RE-5100 8

3. DIRECT RELEASES TO SCR (SAFE SHUT 00WN IMPOUNDMENT)

Release Source Release Type Max Flow Max Vol Monitor Rate (com) (cal)

Unit 1 SSW Train A Continuous 17,000 -

1RE-4269 8 Unit 1 SSW Train B Continuous 17,000 -

1RE-4270 8 Unit 2 SSW Train A Continuous 17,000 -

2RE-4269 8 Unit 2 SSW Train B Continuous 17,000 -

2RE-4270 8 J

l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-19

l

=

TABLE 1.2 ;

SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml)

ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI- ,

H-3 0.00E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E600 8.96E+00 C-14 3.15E+04 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 Na-24 5.48E+02 5.48E+02 5.48E+01 5.48E+02 5.48E+02 5.48E+02 5.48E+02 P-32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.20E+06 Cr-51 0.00E+00 0.00E+00 1.49E+00 8.94E-01 3.29E-01 1.98E+C3 3.76E+02 '

Mn-54 0.00E+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 Mn-56 0.00E+00 1.20E+02 2.12E+01 0.00E+00 1.52E+02 0.00E+00 3.82E+03 Fe-55 8.87E+02 6.13E+02 -1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 Fe-59 1.40E+G3 3.29E+03 1.26E+03- 0.00E+00 0.00E+00 9.19E+02 1.10E+04 Co-58 0.00E+00 1.51E+02 3.39E+02 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Co-60 0.00E+00 4.34E+02- 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.16E+03 Ni-63 4.19E+04 -2.91E+03 1.41E+03 0.00E+00 0.00E+00 0.00E+00 6.07E+02 Ni-65 1.70E+02 2.21E+01 1.01E+01 -0.00E+00 0.00E+00 0.00E+00 5.61E+02 Cu-64~ 0.00E+00 1.69E+01 7.93E+00 0.00E+00 4.26E+01 0.00E+00 1.44E+03 Zn-65 2.36E+04 7.50E+04 3.39E+04 0.00E+00 5.02E+04 0.00E+00 4.73E+04 Zn-69 5.02E+01 9.60E+01 6.67E+00 0.00E+00 6.24E+0! 0.00E+00 1.44E+01

-Br-83 0.00E+00 0.00E+00 4.38E+01 0.00E+00 0.00E+00 0.00E+00 6.30E+0L Br-84 0.00E+00 0.00E+00 5.67E+01 0.00E+00 0.00E+00 0.00E+00 4.45E-04 Br-85 0.00E+00 0.00E+00 2.33E+00 0.00E+00. 0.00E+00 0.00E+00 1.09E-15 L Rb-86 - 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.03E+04 Rb-88 0.00E+00 2.99E+02 1.59E+02 0.00E+00 0.00E+00 0.00E+00-4.00E-09 Rb-89 0.00E+00 1.98E+02 1.39E+02 0.00E+00 0.00E+00 0.00E+00 1.15E-Il Sr-89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-20' REV. 8 [

TABLE 1.2 !.

t-SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml)

ISOTOPE RONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI-Sr-90 1.18E+06 0.00E+00 2.88E+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04 :

Sr-91 8.79E+02 '0.00E+00 3.55E+01 0.00E+00 0.00E+00 0.00E+00 4.19E+03 Sr-92 3.33E+02 0.00E+00 1.44E+01 0.00E+00 0.00E+00 0.00E+00 6.60E+03 Y-90 1.38E+00 0.00E+00 3.69E-02 0.00E+00 0.00E+00 0.00E+00 1.46E+04 Y-91m- 1.30E-02 0.00E+00 5.04E-04 0.00E+00 0.00E600 0.00E+00 3.82E-02 Y 2.02E+01 0.00E+00 5.39E-01 0.00E+00 0.00E+00 0.00E+00 1.11E+04 Y-92 1.21E-01 0.00E+00 3.53E-03 0.00E+00 0.00E+00 0.00E+00 2.12E+03 Y-93 3.83E-01 0.00E+00 1.06E-02 0.00E+00 0.00E+00 0.00E+00 1.22E+04

-Zr-95 2.77E+00 8.88E-01 6.0lE-01 0.00E+00 1.39E+00 0.00E+00 2.82E+03 Zr-97 1.53E-01 3.09E-02 1.41E-02 0.00E+00 4.67E-02 0.00E+00 9.57E+03 Nb-95 4.47E+02 2.49E+02 1 34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 Mo-99 0.00E+00 4.62E+02 8.79E+01 0.00E+00 1.05E+03 0.00E+00 1.07E+03 Tc-99m 2.94E-02 8.32E-02 1.06E+00 0.00E+00 1.26E+00 4.07E-02 4.92E+01

-Tc-101 3.03E-02 4.36E-02 4.28E-01 0.00E+00 7.85E-01 2.23E-02 1.31E-13 Ru-103 .1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+01 0.00E+00 2.31E+03 Ru-105 1.65E+00 0.00E+00 6.51E-01 0.00E+00 .2.13E+01 0.00E+00 1.01E+03

-Ru-106 2.95E+02 0.00E+00 3.73E+01 0.00E+00 5.69E+02 0.00E+00 1.91E+04 Ag-110m 1.42E+01 1.31E+01 7.80E+00 J.00E+00 2.58E+01 0.00E+00 5.36E+03

-Te-125m 2.79E+03 -1.01E+03 -3.74E+02 8.39E+02 1.13E+04 0.00E+00 1.11E+04-Te-127m.7 05E+03 -2.52E+03 -8.59E+02 1.80E+03 2.86E+04 0.00E+00 2.36E404 Te-127 -1.14E+02 4.11E+01 2.48E+01 8.48E+01 4.66E+02 0.00E+00 9.03E+03-Te-129m 1.20E+04 -4.47E+03 1.89E+03 4.11E+03 5.00E+04 0.00E+00 6.03E+04 Te-129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.00E+00 2.47E+01- ,

COMANCHE PEAK - UNITS 1 AND 2 REV. 8 PART II 1-21

~+ . . .

TABLE 1,2- '-

SITE RELATED INGESTION DOSE COMMITMENT FACTOR A.

(mrem /hr per uC1/ml) "

ISOTOPE BONE' LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Te-131m 1.SOE+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.00E+00 8.74E+04 Te-131 2.05E+01 8.57E+00 6.47E+00 1.69E+01 8.98E+01 0.00E+00 2.90E+00 Te-132 2.62E+03 1.70E+03 1.59E+03 1.87E+03 1.63E+04 0.00E+00 8.02E+04 I-130 9.01E+01 2.66E+02 .1.05E+02 2.25E+04 4.15E+02 0.00E+00 2.29E+02 1-131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 I-132 2.42E+01 6.47E+01 2.26E+01 2.26E+03 1.03E+02 0.00E+00 1.22E+01 1-133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.00E+00 2.64E+02 1-134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+01 0.00E+00 2.99E-02 I-135 5.28E+01 1.38E+02 5.10E+01 9.11E+03 2.22E+02 0.00E+00 1.56E+02 Cs-134 3.03E+05_ 7.21E+05 5.89E+05- 0.00E+00 2.33E+05 7.75E+04 1.26E+04 Cs-136 3.17E+04 1.25E+05 9.01E+04 0.00E+00 6.97E+04 9.55E+03 1.42E+04 Cs-137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 Cs-138 2.69E+02 5,31E+02 2.63E+02 0.00E+00 3.90E+02 S 85E+01 2.27E-03 Ba-139 9.00E+00 6.41E-03 2.64E-01 0.00E+00 5.99E-03 3.64E-03 1.60E+01

.Ba-140 1.88E+03 2.37E+00 1.23E+02 0.00E+00 8.05E+01 1.35E+00 3.88E+03 Ba-141 4.37E+00 3.30E-03 1.48E-01 0.00E+00 3.07E-03 1.87E-03 2.00E-09 Ba-142 1.98E+00 2.03E-03 1.24E-01 0.00E+00 1.72E-03 1.15E-03 2.78E-18 La-140 3.58E-01 1.80E-01 4.76E-02 0.00E+00 0.00E+00 0.00E+00 1.32E+04 La-142 1.83E-02 7.55E-03 2.072-03 0.00E+00 0.00E+00 0.00E+00 6.08E+01 Ce-141 8.01E-01 5.41E-01 6.15E-02 0.00E+00 2.52E-01 0.00E+00 2.07E+03 Ce-143 1.41E-01 1.04E+02' 1.16E-02 0.00E+00 4.60E-02 0.00E+00 3.90E+03 Ce-144 4.18E+01 1.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04 Pr-143 1.32E+00 5.28E-01 6.52E-02 0.00E+00 3.05E-01 0.00E+00 5.77E+03 COMANCHE PEAK - UNITS 1 AND 2 REV. 8 PART II 1-22

TABLE 1.2 1

SITE RELATED INGESTION DOSE COMMITMENT FACTOR Aj7 (mrem /hr per uCi/ml)

ISOTOPE EDE LIVER T-BODY THYROID KIONEY LQNQ GI-LLI-Pr-144 4.31E-03 1.79E-03 2.19E-04 0.00E+00 1.01E-03 0.00E+00 6.19E-10 Nd-147 9.00E-01 1.04E+00 6.22E-02 0.00E+00 6.08E-01 0 00E+00 4.99E+03 W-187 3.04E+02 2.55E+02 3.90E+01 0.00E+00 0.00E+00 0.00E+00 8.34E+04 No-239 1.28E-01 1.25E-02 3.91E-03 0.00E+00 3.91E-02 0.00E+00 2.57E+03

Sb-122 1.98E+01 3.90E-f4 5.79E+00 2.69E-01 0.00E+00 1.03E+01 5.68E+03

- Sb-124 2.41E+02 4.54E+00 9.50E+01 5.81E-01 0.00E+00 1.87E+02 6.81E.03

- Br-82 0.00E+00 0.00E+00- 1.93E+02 0.00E+00 0.00E+00 0.00E+00 2.22E+02 lf

- Sb-125 1.91E+02 2.05E+00 3.84E+01 1.70E-01 0.00E+00 1.99E+04 1.69E+03 l7 The adult dose conversion factors, OFj, for Sb-172 are not publisned 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, OF1 , for Sb-124, Sb-125 and Br-82 l are not published in Reference 2. The site-related dose commitment factors for Sb-124, Sb-125 and Br-82 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.

COMANCHE-PEAK - UNITS 1 AND 2 FART II 1-23 REV. 8

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COMANCHE PEAK - UNITS 1-AND-2 REV. 8 PART II 1-27 \

SECTION 2.0 GASE0US EFFLUENTS 8

At CPSES, normal radioactive gaseous effluents are collected in a 8 common exhaust air intake plenum, processed throt,gh 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 gasecus releases from these stacks are conservatively assumed to be entrained into the building wuke and cavity regions, which results in a conservative ground-level release.

Routine gaseous effluent releases may occur from the Unit I and a 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 radicactivity is discharged rapidly from the containment atmosphere during purges, the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Containment Building purges are considered batch releases. The remainder of a purge is treated as a contribution to the continuous release already occurring through the plant vent stacks.

Operating experience has shown that occaisional releases may be 8 required from Pressurizer Relief Tank (PRT) vents for depressurizing the RCS during outages, from Volume Control Tank (VCT) ve:its during maintenance on the Waste Gas Processing System, from the Containment Buildings during Intergrated leak RateTest(ILRT),andfromsecondarysteamreleases(potentially radioactive during periods of primary-to-secondary leaks).

These releases occur infrequently ar.d are treated as batch releases.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-1

A summary of all gaseous effluent release points, release 8 sources, flow rates (if applicable) and 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 8 ;

-(WRGM) and a Particulate. Iodine, and Noble Gas (PIG) 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. , pCi/ml). The conversion factor for detector output from counts per minute to pCi/ml 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-55708 for Stacks A and B, respectively. Each WRGH consists of a low range (10-7 to 10-1 pCi/cc), mid range (10-4 to 102 gCi/cc),

and high range-(10-1 to 105 Ci/cc) noble gas activity detector. The WRGMs also have an effluent release rate channel 4 which uses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack flow rate detectors (X-FT-5570A-1/B-1) to provide an indication of noble gas release rate in pCi/sec. Alarm setpoints are established for the WRGM effluent release rate channel to fulfill the requirements of Radiological _ Effluent Control 3/4.3.3.5. Exceeding the WRGM effluent release rate channel high alarm setpoint also initiates automatic termination of Waste Gas Decay Tank releases.

The stack DIGS are designated as particulate channels XRE-5568A and XRE-5538B iodine channels XRE-5575A and XRE-55758, and noble gas channels XRE-5567A and XRE-55678 for Stacks A and B, l respectively. The stack PIG noble gas channels may be used as a l _back-up_to the WRGH when no automatic control functions are i

{

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-2 L ;

I required. Therefore, a methodology is provided for calculating the PIG noble gas monitor setroints. Methodologies are not 8 provided for calculating setpoints for the PIG particulate and i iodine channels, since these channels are not required by the Radiological Effluent Controls Program, and because it is not practical to establish instaneous setpoints for integrating type monitors (reference 1).

Other monitors that may be used for effluent monitoring and 8 control are the Auxiliary Building Ventilation Duct Monitor, XRE-5701, and the Containment PIG Noble Gas Monitors, 1RE-5503 and 2RE-5503. XRE-5701 may be used to monitor Waste Gas Decay Tank releases oy monitoring the Auxiliary Building Ventilation Duct.

XRE-5701 also provides the automatic control function for terrrination of Waste Gas Decay Tank releases. 1RE-5503 and 2RE- 8 5503 monitor the Unit 1 and Unit 2 Containment atmospheres, respectively, ar.d provide the only automatic control function for termination of Containment vents or purges.

2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 COMPLIANCE 8 2.1.1 Dose Rates Due to Noble Gases For implementation of Radiological Effluent Control 8 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 dqte rate due to noble casel 8 D=%Dtv t = E (X/Q) % K; Q y

. [Eq. 2-1 1 y v (nrble gases)

Where: Ot= the total body dose rate at the SITE 8 BOUNDARY due to noble gases from all releasesources(mrem /yr)

Ov=

t the total body dose rate at the SITE 8 BOUNDARY due to noble gases from release source v (mrem /yr).

l. REV. 8 COMANCHE PEAK - UNITS 1 AND PART II 2-3

. m - . _ -- _ -- -. _ _ _ _ _ . _ _ _ . . _ _ _

(X/Q)= the highest annual average relative concentration at the SITE BOUNDARY (3.3x10-6sec/m3 in the NNW sector at a distance of 1.20 miles from the plant *.)

NOTE: TheannualaverageX7Qisalsousedin determining setpoints for containment purge or vent as required by Technical Specification 3.3.3.1.

Kj = total body dose factor due to gamma 8 emissions from noble gas radionuclide i from Table 2.2 (mrem /yr per Ci/m3)

Qiy = the total release rate of noble gas 8 radionuclide i from the release source v (pCi/sec) (See C belovt for calculation of Qiv) v = index over all release sources 8 B. = Skin dose rate due to noble cases D=EDsy=

s E(M O) E (L + 1.1 M i ) 0;y v v (noble gases) 8 Where: Ds = the skin dose rate at the SITE BOUNDARY due 8 to noble gases from all release sources.

(mrem /yr)

Dsy= the skin dose rate at the SITE BOUNDARY due 8 to noble gases from release source v.

(mRcm/yr)

Reference 4, Section 2.3.5.2. 8 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-4

t.1 = the skin dose factor due to beta emissions 8-from noble gas radionuclide i from Table 2.2 (mrem /yr per pCi/m3) 1.1 = conversion factor of mrem skin dose per mrad air dose.

Mi= air dose factor due to gamma emissions from 3 noble gas radionuclide i from Table 2.2 (mrad /yr per pCi/m3)

All other terms are as previously defined, C. Release Rate 8 Qi is defined as the total release rate (pCi/sec) of 8 radionuclide i from all release sources. Qi is given by:

Q4= IQ $y

= IX $yF y (Eq. 2-3] 8 y v Where: Xjy = the measured concentration of radionuclide 8 i present in each release source v

( Ci/cm3)

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

Qjy = the release rate of radionuclide i from 8 release source v (pCi/sec) v = index over .11 release sources 8 2.1.2 Dose Rates Due to Radiciodines. Tritium, and Particulates 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:

D=EDay o = E (X/Q) E P; Qi v v IP&T IE 4 -4I 2

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-5

Where: D o = 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.)

Day = the organ dose rate duc to iodine-131, 8 iodine-133, particulates with half-lives

. eater than eight days, and tritium from release source v (mrem /yr)

Pj = pathway dose rate parameter factor for 8 radionuclide, i, (for radiciodines, 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, porticulates 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 MSE005 EFFLUENT MONITOR SETPOINTS 8 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 valve should exceed the maximum range of the monitor, the setpoint shall be adjust 2d 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 releas ay be made. Under such circumstances, contributing source terms shall be reduced and the setpoint recalculated.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2' PART II 2-6

4 2.2.1 Plant Vent Effluent Release Rate Montiqti 8.

XRE-5570A and XRE-55708 Effluent Release Rate Channels The WRGM effluent release rate channels monitor the 8 release rate of radioactive materials from each plant vent stack by combining inputs from the WRGM low range noble ,

gas activity channel (uti/cm3) indication and a stack flow rate (cm3/sec) indication (X-FT-5570A-1/8-1) 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 contrcl function for termination of Waste Gas Decay Tank Releases. The setpoint fo, each plant vent effluent release rate monitor will be calculated using the following methodology:

500 X SF = 125 Q,g 3 ,

,Q NG D D t

)

Q site = the lesser of 3000 X SF = 750 QNG Q

NG D D

[Eq.2.6]

s s Where: Qsite a the total site noble gas release rate limit 8 corresponding to a dose rate at the SITE B0UNDARY of 500 mrem /yr to the total body or 3000 mrem /yr to the skin (uCi/sec)

QNG = (noblegases)Qj 8

=

the actual release rate of noble gases from 8 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 =

the dose rate limit to the total body of an 8 individual at the SITE BOUNDARY due to noble gases from all release sources.

(mrem /yr)

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-7

3000 = the dose rate limit to the skin of the body 8 of an individual at the SITE BOUNDARY due to noble gases from all release sources.

(mrem /yr)

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

Then the release rate setpoint for each stack monitor, 8 Cr, in uCi/sec is determined as foilows:

Cr = Qsite AF (Eq. 2-7)

Where: AF = Allocation Factor of 0.5 appliec to account for releases from both plant stacks simultaneously (unitiess). This factor 8 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 8 XRE-5570A/XRE-5570B (WRGH low ranae noble cas activity 8 channe H and XRE-5567A/XRE-55678 (PIG noble cas channel).

The WRGM low range noble gas activity channels provide 8 noble gas concentration 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, ACTION 36 allows for use of the stack PIG noble gas monitors (XRE-5567A and XRE-l 55678) as a backup for an inoperable WRGH effluent l

l i

~

REV. 8

! COMANCHE PEAK - UNITS 1 AND 2 PART II 2-8 i

l releaseratechannelwhenndautomaticcontrolfunction-.is- '8 -

required. The alarm setpoint for these channels,-CG in 'l

, uC1/cm3,-is determined using the following methodology:

g [Eq. 2-8] 8 CG FPVS Where: Fpy3 = the maximum stack flow rate 8 (cc/sec)correspondingto 115,000 cfm during normal operations and 130,000 cfm during containment purges.

2.?.3 Samoler Flow Rate Monitors (X-RFT-5570A-1/8-1) 8 ,

The WRGMs are-designed to sample isokinetically from the plant vent stacks. Isokinetic sample flow is maintained 8

automatica11y'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 Buildino Ventilation Exhaust Monitor (XRE-5701) 8 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 WGOT 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).

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-9

Based on assumption (1) above, there are a maximum of 8 three release sources that may contribute to the total release rate from the site during a WGOT 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 2Cr 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:

O aux = 1/3 2Cf= 2/3 C f [Eq. 2-9]

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

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

Q 2C C

aux F

3F

[Eq. 2-10]

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

2.2.5 Containment Atmosphere Gaseous Monitors (1RE-5503 and 2RE-5503) 8 For implementation of Technical Specification 3/4.3.3.1, 8 the 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:

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-10

(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 8. 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 2Cr 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:

Q cont * *2 f* f Where: Qcont = the limiting release rate 8 contribution from a containment release (uCi/sec)

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

C cont " cont "2F cont [Eq. 2-12]

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

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-11 05/92

8 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 denonstrating 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 doses assigned 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 Cor.rol 8 3/4.11.2.2, the cumulative air dose due to noble gases to areas at and beyond the SITE BOUNDARY 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 8 Dy = air dose due to gamma emissions from noble gas 8 radionuclides from all release sources (mrad)

D y = 3.17 x 10-8 (X/Q) (noble gases) "i O'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 radionuclide i during_ 8 the period of interest from all release sources (uCi)

(Q'i = Q1 (uCi/sec) x release duration (sec)) 8 REV. 8 COMANCHE PEAK - UNITS 1 AND-2 PART II 2-12

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

All other variables are previously defined.

B. Air Dose Due to Beta Emissions 8 O

g

=

air dose due to beta emissions from noble gas 8 radionuclides (mrad)

Dg = 3.17 x 10-8 (X/Q) (noble gases) Ng Q'j [Eq.2-14] 8 Where: Ni= the air dose factor due to beta emissions from 8 noble gas radionuclide i from Table 2.2 (mrad /yr per uCi/m3),

All other variables are previously defined. 8 Note: If the methodology in this section is used in 8 determining dose to'an individual rather than air dose due to noble gases, substitute Kj for Mj, (Lj + 1.1 Mj) for Hj, and the Annual Average X/Q values from Table 2.5 for the highest annual average relative concentration (X/Q) at the SITE BOUNDARY.

2.3.2 Dose Due tg Radiciodines. Tritium. and Particulates -8 For implementation of Radiological Effluent Control 8 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:

T Y

-8 W IP&T PR i,a,o i W j [Eq.2-15]

Dp = PATHS 3.17 x 10 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-13

'Where: Dp o dose due to all real pathways to organ, o, 8 of an individual in age group, a, from ,

iodine-131, iudine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days fror all releasesources(mrem).

W' = the dispersion parameter for estimating the 8 dose to an individual at th; location where the combinstion of existing pathways and receptor age groups indicates the maximum potential exposures. Locations of interest are listed in Table 2.5, W' = X/Q for the inhalatitc. pathway in sec/m3, X/Q is the annual average relative 8 concentration at the location of interest.

Values for X/Q are listed in Table 2.5.

If_ desired, the highest individual receptre X/Q or X/Q valve may be used, or W' = D/Q for the food and ground plane pathways 8 in m-2 D/Q is the annual average deposition at the location of interest.

Values for D/Q are listed in Table 2.5.

If desired, the highest individual receptor

~

D/QorDTQvaluemaybeused.

NOTE: For tritium, the dispersion parameter, W' 8 is taken as the annual average X/Q values from Table 2.5 for inhalation, food and ground plane pathways.

RP1 ,a,o = dose factor for radionuclide i, 8 pathway p, age group a and organ o, in mrem /yr per UCi/m3 for ti.t-inhalation pathway and m2(mrem /yr) per uCi/sec for food and ground plar.e pathways, except for tritium which is in mrem /yr per uCi/m3 for all pathways. The values for RPi ,a,o for each pathway, radionuclide, age group and organ are listed in Table 2.4.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 2-14

The methodologies used for determining 8 P

values of R j,a,c for each pathway are given in Appendices B through F.

Q't = cumulative release of radionuclide, i. B during the period of interest (uCi). Q't is based on the activities measured :q each p Ynt vent stack from the 'nalyses of the particulate and iodine san.ples required by Radiological Effluent Control 3/4.11.2.1 Table 4.11-2.

1&PT =

lodines, particulates with half-lives 8 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 8 individuals at the locations of interest as indicated in Table 2.5.

2.4 QQSL_ERQlECTIONS FOR GASEOUS EFFLUENTS 8

Radiological Effluent Control 3/4.11.2.4 requires that 8

appropriate portions of the PRIMARY PLANT VENTILATION SYSTEM and '

WASTE lAS HOLOUP SYSTEM be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent from a unit to areas at and beyond the SITE BOUNDARY would exceed, in a 31-day period, either:

0.2 mrad to air from gamma radiation; or B

0.4 mrad to air from beta radiation; or 8

0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

B The following calculational method is provided for performing 8 this dose prc.jection:

b At least once every 31 days the gamma air dose, beta air dose and 8 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 REV. B COMANCHE PEAK - UNITS 1 AND 2 PART II 2-1 L_____ _ __ _ - - - - -

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

2. 5 DOSE CALCULATIONS TO SUPPORT OTHER REQUIREMENTS 8 for the purpose of implementing the requirements of Radiological 8 Effluent Control 6.9.1.4, the Semiannual Radioactive Effluent Release Report shall include en assessment of the radiation doses due to radioactive liquid and gaseous effluents from the station during the previous 6 months 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 7.3.2 for ooses due to iodines, tritium, and particulates. This same report shall also include an assessment of the radiation doses from radioactive liquid and gasecus effluents to members of the public due to their activitics inside the SITE BOUNDARY. This assessment shall be performed in a:cordance 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 occtpancy factors.

All assumptions and factors used ir the determination shall be included in the report.

For the purpose of implementing Radiological Effluent Control 8 3/4.12.2 dose calculations for the new locati~ns identified in the land use 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 everage dispersion parameters may be used for these calculationr. If the land use censur changes, the critical location (i.e., the location where an individual would be cxposed to the highest dose) must be reevaluad for Cie nearest residence, the nearest milk animal, and the nearest REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART !! 2-16

vegetable garden. Additionally, when a location is identified 8 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 8 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 public in accordance witt 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 Semi-annual Radioactive Effluent Release Report to be submitted 60 days after January 1 of the year after the assessment was required. Otherwise, n.o assessments are 8 required.

For the evaluation of doses to real individuals from liquid S releases, 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 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 (Mj) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real 'ndividuals, the meteorological conditions, and the consumption of food. Data obtained from the latest land use census should be used to REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 2-17 !

~

1 1

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 radioneclide concentrations.

The dose component due to direct radiation my be determined by 8 calculation or actual measurement (e.g., therm 0 luminescent dosimeters, micro-R meter, etc.). The calculation or actual measurement of direct radiation shall be documented in the I Special Report that must be submitted if this determina an is required.

2.6 METEOROLOGICAL MODEL 8 2.6.1 01soersion Calculations 8 Atmospheric dispersion for gaseous releases is calculated 8 using a straight lirme flow Gaussian model similar to the Constant Mean Wind Direction model given in Regulatory C. side 1.111 Section C.1.c. The method given here is mcdified by including factors to account for plume dep etion and effects of the open terrain. The average relative concentration is given by the following equation:

[Eq.2-16]

f=2.0326K Nr E Where:

X/Q = average concentration normalized by source 8 strength (sec/m3),

2.032 = (2/ Tr )1/2 . (2 tr /16)-1 8 6 = plume depletion factor at distance r for 8 the applicable stability class (Figure 2.2). Normally, a value of 1.0 is a sumed when undepleted X/Q values are to be u,ed in dose calculations.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 2-18

K = terrain correction factor (Figure 2.5) 8 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.

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

NOTE: If hourly meteoro'ogical 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.

' = downwind distance from the release point to B the location of interest (meters) ujk = theav1ragewindspeed(midpointof 8 windspeed class, k) measured at the 10 meter level during stability class J.

(meters /sec)

Ej(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 Ej(r) is: 8 2

/ (u)2 + 0.5 b /tr)I [Eq. 2-17)

Ej(r) = the lesser of

/Tu j [Eq. 2-18]

Where:

-g j= 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 11 2-19

0.5 = the building shape factor. 8 b = the vertical height of the reactor 8 containment structure (79.4 meters) 2.6.2 Deposition Calculationi 8 The relative deposition per unit area is calculated as follows: 8 KDz q

[Eq. 2-19]

h*0.392Ir l Where:

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

Dg -

relative deposition rate for a ground level 8

,ae -I)(Figurc2.4) 2

? 's. F 4C gr* cf time the wind blows to the 8 3:.ctor of irterest.

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

0.3927 =

the width in radians of a 22.50 sector. 8 Cther 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

. - - - - . . .. . - = - . .-- - , --._ - . . . - . - . - - -.

2.7 DEFINITIONS OF GASEAMAlf1GJLENTS PARAMETfJUi 8 l I

Tgrm 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 8 vertical height of the reactor containment structure I

Cg the alarm setpoint for each plant vent stack noble gas 8 l activitymonitor(uCi/cm3) l l

Cr the alarm setpoint for each plant vent stack effluent release rate monitor (uCi/sec) caux the Auxiliary Building Ventilation Exhaust monitor alarmsetpoint(uCi/cm3) ccont the Containment Atmosphere Gaseous monitor alarm setpoint 8 (uCi/cm3)

Og relative deposition rate for a ground-level release (m-1) t.

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)

Doy 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)

Op dose to any organ of an individual from radiciodines, 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 11 2-21

Ig_r_m r DefinitioD Ds skin dose rate at the SITE BOUNDARY due to noble gases 8 from all release sources (mrem /yr)

Ogy skin dose rate at the SITE BOUNDARY due to noble gases 8 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)

Dvt total body dose rate at the SITE BOUNDARY due to noble 8 gases from release source v (mrem /yr)

Og air dose due to beta emissions from noble gases from all 8 release sources (mrad)

Dy air dose due to gamma emissions from noble gases from all 8 release sources (mrad)

D/Q the annual average relative deposition at the location of interest (m-2) 6 plume depletion factor at distance r for the appropriate 8 stability class (radiciodines and particulates)

Fy the flow rate from each re. ease source v (cm3 /sec)

, Faux the maximum Auxiliary Building Ventilation flow rate 8 (cm3/ sec) corresponding to 106,400 cfm Fcont the maximum containment release (cm3/ sec) corresponding 8 to 750 cfm for containment vents and 30,000 cfm for containment purges Fpys the maximum stack flow rate (cc/sec) corresponding to 8 115,000 cfm during normal operations and 130,000 cfm during containment purges l

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-22

Term Refinition ,

l K

terrainrecirculationfactor(Unitiess) 8 !

i Kj total body dose factor due to gamma emissions from noble 8 gasradionuclidei(mrem /yrperuCi/m3)

Lj skin dose factor due to beta emissions from noble gas 8 radionuclide 1 (mrem /yr per UCi/m3)

Mt air dose factor due to gamma emissions from noble gas 8 1 radionuclide 1 (mrem /yr per UCi/m3)

Ni air dose factor due to beta emissions from noble gas 8 radionuclidei(mrem /yrperuC1/m3) 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 Pj pathway dose rate parameter for radionuclide 1, (other 8 than noble gases) for the inhalation pathway (mrem /yr per uCi/cm3)

Qaux the limiting release rate contribution from the 8 Auxiliary Building Vent during WGOT releases (uC1/sec)

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

Qi total release rate of radionuclide i from all release 8-

, sources (uC1/sec) i l REV 8 L ' COMANCHE PEAK - UNITS 1 AND 2 PART II 2-23

Qiy the total release rate of radionuclide i from release 8 source v (uCi/sec)

Q't cumulative release of radionuclide i during the period 8 of interest from all release sources (uCi)

QNG the actual release rate of noble gases from all 8 release sources as calculated from the radionuclide concentrations determined from analyses of samples taken in accordance with Control 3/4.11.2.1, Table i 4.11-2 l QSITE the total site noble gas release rate limit corresponding S to a dose rate at the SITE BOUNDARY of 500 mrem /yr to the-

-total body or 3000 mrem /yr to the skin (uC1/sec)

RPi .a.o dose factor for radionuclide i, pathway p, and age group 8 a, and organ o (mrem /yr per uC1/m3) or (m2. mrem /yr per uC1/sec) r distance from the point of release to the location of 8 interest for dispersion calculations (meters)

SF Ssfety Factor of 0.5 applied to compnsate for 8 statistical fluctuations, errors of measurement, and non uniform distribution of release activity between the stacks Ej(r) vertical plume spread with a volumetric correction for a 8 release within the building wake cavity, at a distance, r, for stability class, j,' expressed in meters aj vertical standard deviation of the plume concentration (in 8 meters), at distance, r, for stability category j IJjk wind speed (midpoint of windspeed class k) at ground 8 level (m/sec) during atmosphere stability class j REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-24

Igrg Definit'on W' the dispersion parameter for estimating the dose to an 8 indivioual at the location where the combination of existing pathways and receptor age groups indicates the maxirrum exposures l

X/Q the annual average relative concentration at the location 8 ofinterest(sec/m3) !

X/Q the hightest annual average relative concentration at the 8 ,

SITEBOUNDARY(sec/m3)(3.3x10-6sec/m3 in the hNW sector)

Xjy the measured concentration of radionuclide i present in each release source v (uCi/cm3) 2 the fraction of time the wind blows to the sector of 8 interest 1.1 conversion factor of mrem skin dose per mrad air dose 8 500 the dose rate limit to the total body of an individual at 8 the SITE BOUNDARY due to noble gases from all release sources (mrem /yr) 3000 the dose rate limit to the skin of the body of the 8 individual at the SITE B0VHDARY due to noble gases from all release sources (mrem /yr)

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-25

f Y

g TABLE 2.1 h

SUMMARY

OF GASEOUS RELEASE PATHWAYS 2

m

?

M g 1. RELEASES VIA THE PLANT VENT STACKS y 8

a REttASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfm) MONITOR (5)

N c) Stack A Continuous XRE-5570A/XRE-5567A 115.000 N Strck B Continuous 115.000 XRE-55703/XRE-5567B WGbr*s Batch 20 XRE-5570A&B/XRE-5567A&B >

U-1 Cont. Vent. Batch 750 1RE-5503 :

U-1 Cont. Purge Batch 30.000 1RE-5503 ,

U-2 Cont. Vent. Batch 750 2RE-5503 l g U-2 Cont. Purge Batch 30.000 2RE-5503 d i

~

2. RELEASES'VIA THE ILRT VENT

~

M RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfa) MONITOR (S)

ILRT Batch - - ,

8 l

) ,

[

y

{

M

TABLE 2.2 8

DOSE FACTORS FOR EXPOSURE TO A SEMI-INFI Isotope T-Bodv***(K) d-Skin ***(L) 7-Air **fM} S-Air **(N)

Kr-83m 7.5EE-02 ---

Kr-85m 1.17E+03 1.93E+01 1.46E+03 2.88E+02 Kr-85 1.61E+01 1.23E403 1.97E+03 Kr-87 1.34E+03 1.72E+01 5.92E+03 9.73E+03 1.95E+03 6.17E+03 1.03E404 Kr-88 1.47E+04 Kr-89 2.37E+03 1.52E+04 1.66E+04 1.01E+04 2.93E+03

~

Kr-90 1.56E+04 1.73E+04 1.06E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 Xe-133m 4.76E+02 1.56E+02 2.51E+02 9.94E+02 1.11E+03 Xe-133 2.94E+02 3.27E+02 3.06E+02 1.48E+03 3.53E+02 1.05E+03 Xe-135m 3.12E+03 Xe-135 7.11E+02 3.36E403 1.81E+03 1.86E+03 7.39E+02 Xe-137 1.42E+03 1.92E+03 1.22E+04 2.46E403 1.51E+03 1.27E+04 Xe-138 8.83E+03 Ar-41 4.13E+03 9.21E+03 8.84E+03 2.69E+03 4.75E+03 9.30E+03 3.28E403

Values taken from Reference 2, Table B-1 Inrad-m3 uCi-yr l

- - mrem-m3 UCi yr

\

l COMANCHE PEAK - UNITS 1 ANDPART 2 II 2-27 REV. 8

_ _ ~ " " ' ' - ' " " '

l TABLE 2.3 PATWAY DOSE RATE PARAMETER (Pi)*

BASED ON THE INHA1ATION PATWAY FOR THE CHILD AGE CROUP l ORGAN DOSE FACTORS NUCL1DE l.....................................................................

l BONE LIVER T. BODY THYROID KIDNEY LUNC CI.LLI H.3 0.00E+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 9.9PE+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 CR.51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 L08E+03 MN.54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE.55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE.59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 CO.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI 63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB 86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR.89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR.90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y.91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR 95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB.95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU.103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU 106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 AG.110X 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48F+06 1.00E+05 TE-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+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 1 131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 1 133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS.134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS.137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA.140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE 141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR.143 1.85E+04 5.55E+05 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND 147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART 112 28

TABLE 2.4 PATHWAY DOSE FACTORS AGE CROUP: ALL PATHVAY: CROUND PLANE

...t.........................................................

l ORGAN DOSE FACTORS XUCL1DE l..................... \

l T. BODY SKIN l H.3 0.00E+00 0.00E+00 l P.32 0.00E+00 0.00E+00 CR 51 4.65E+06 5.50E+06 MN 54 . 39E+09 1.62E+09 FE.55 0.00E+00 0.00E+00 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 0.00E+00 0.00E+00 ZN.65 7.47E+08 8.59E+08 RB.86 8.97E+06 1.03E+07 l hR89 h hk bb h h b bb SR.90 0.00E+00 0.00E+00 Y.91 1.07E+06 1.21E+06 ER-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.110M 3.44E+09 4.01E+09 TE.125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 TE.129M 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 8.00E+09 CS.1*6 1.51E+08 1.71E+08 CS.137 1.03E+10 1.20E+10 BA.140 1.06E+07 2.36E+07 CE.141 1.37E+07 1.54E+07 CE.144 6.96E+07 8.0$E+07 PR.143 0.00E+00 0.00E+00 ND 147 8.39E+06 1.01E+07 -

COMANCHE PEAK . UNITS 1 AND 2 REV.8 PART ll 2 29

TABLE 2.4 PATHVAY DOSE FACTORS AGE GROUP: ADULT PATHVAY: GRASS.COV MIIX l ORGAN DOSE FACTORS XUCLIDE l ---- - -- - -- - ---- *** - --- - -- - -

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 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 6.38E+08 0.00E+00 0.00E+00 0.00E+00 1.91E+09 CR.51 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN.54 0.00E+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57E+07 FE 55 2.51E+07 1.73E+07 4.04E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06 FE 59 2.97E+07 6.97E+07 2.67E+07 0.00E+00 0.00E+00 1.95E+07 2.32E+08 CO.58 0.00E+00 4.71E+06 1.0$E+07 0.00E+00 0.00E+00 0.00E+00 9.54E+07 CO.60 0.00E+00 1.64E+07 3.61E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 NI.63 6.72E+09 4.65E+08 2.25E+08 0.00E+00 0.00E+00 0.00E+00 9.71E+07 ZN.65 1.37E+09 4.36E+09 1.97E+09 0.00E+00 2.91E+09 0.00E+00 2.74E+09 RB.86 0.00E+00 2.59E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.10E+08 SR.89 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.00E+00 2.32E+0B SR-90 4.67E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1. 3 5 E -09 Y.91 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 ZR.95 9.41E+02 3.02E+02 2.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 NB.95 8.24E+04 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 RU.103 1.02E+03 0.00E+00 4.38E+02 0.00E+00 3.88E+03 0.00E+00 1.19E+05

~~ '

kh$ib6'5$b4khbdb$bbkhbbE558k+b5 b$bbk bb5$95b+b5'~b$bbk bb'~i$52 AG.110M 5.81E+07 5.38E+07 3.19E+07 0.00E+00 1.06E+08 0.00E+00 2.19E+10 TE.125M 1.63Ev07 5.89E+06 2,18E+06 4.89E+06 6.61E+07 0.00E+00 6.49E+07 TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.00E+00 1.53E+08 TE.129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 3.02E+08 I.131 2 96E+08 4.23E+08 2.42E+08 1.39E+11 7.25Ev08 0.00E+00 1.12E+08 I.133 3.87E+06 6.73E+06 2.0$E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 CS.134 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CS.136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 CS.137 7.37E+09 1.01E+10 6.60E+09 0.00E+00 3.42E+09 1.14E+09 1.95E+08 BA.140 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 CE.144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21E+0S PR-143 1.57E+02 6.32E+01 7.81E+00 0.00E+00 3.65E+01 0.00E+00 6.90E+05 ND 147 9.40E+01 1.09E+02 6.50E+00 0.00E+00 6.35E+01 0.00E+00 5.22E+05 COMANCHE PEAK . UNITS 1 AND 2 PART 112-30 REV.8

~_

TABLE 2.4 PATHVAY DOSE FACTORS ACE CROUP: TEEN PATHVAY: CRASS.COV MILX l ORCAN DOSE FACTORS NUCLIDE l -- -

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI H.3 0.00E+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 0.00E+00 0.00E+00 0.00E+00 2.65E+09 CR.51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN.54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.19E+06 0.00E+00 2.88E+07 FE.55 4.46E+07 3.16E+07 7.37E+06 0.00E+00 0.00E+00 2.01E+07 1.37E407 FE.59 5.19E+07 1.21E+08 4.68E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 Co.58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 Co.60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 NI-63 1.18E+10 8.36F+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN.65 2.11E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 RB 86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08 SR.89 2.68E+09 0.00E+00 7.67E+07 0.00E+00 0.00E+00 0.00E+00 3.19 E4 08 SR.90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.(0E+00 0.00E+00 1.86E+09 Y 91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 ZR 95 1.65E+03 5.21E+02 3.58E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 NB-95 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+0B y RU-103 1.81E+03 0,00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51E+05 RU.106 3.76E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 AG.110M 9.64E+07 9.12E+07 5.55E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 TE 125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 0.00E+00 0.00E+00 8.87E+07 TE 127M 8.45E+07 3.00E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.11E+08 TE 129M 1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 ,

1 131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 F ..............................................................................

1 133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 CS 134 9.83E+09 2.31E+10 1.07E+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 CS.136 4.49E+08 1.77E+09 1.19E+09 0.00E+00 9.63E+08 1.52E+08 1.42E+08 CS 137 1.34E+10 1.78E+10 6.21E+09 0.00E+00 6.06E+09 2.36E+09 2.54E+08 BA.140 4.87E+07 5.97E+04 3 .14 E+ 0-5 0.00E+00 2.02E+04 4.01E+04 7.51E+07 CE 141 8.89E+03 5.94E+03 6.82E+02 0.00E+00 2.80E+03 0.00E+00 1.70E+07 CE 144 6.59E+05 2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 ND 147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.12E+05 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART 112-31 L.. ... . .. .

,,,._..a

__. . . _ . . . . . . . _ .i

TABLE 2.4 PATHVAY DOSE FACTORS AGE GROUP: CHILD PATHVAY: CRASS.COV MILK l ORGAN DOSE FACTORS XUCL1DE l............. ..... .. .............. ............ ..... ............

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 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 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 CR.51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 KN.54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 FE 55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 FE.59 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.65E+07 2.03E+08 CO.58 0.00E+00 1.21E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 CO.60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+0B NI.63 2.97E+10 1.59E+09 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 EN.65 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94E+09 RB.86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E400 5.65E+08 SR.89 6.63E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E +00 2.57E+08 SR 90 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E&OO 0.00E+00 1.51E+09 Y.91 3.91E+04 0.00E+00 1.05E+03 0.00E+00 0.00E+00 0.00E+00 5.21E+06 ZR.95 3.84E+03 8.43E+02 7.51E+02 0.00E+00 1.21E+03 0.00E+00 8. 8 0E+05 NB.95 3.18E+05 1.24E+05 8.86E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+0B RU.103 4.29E+03 0.00E+00 1.65E+03 0,00E+00 1.08E+04 0.00E+00 1.11E+05 RU.106 9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 AG.110M 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0,00E+00 1.68E+10 TE.125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 TE.127M 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 TE.129M 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 I.131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 I-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 CS.134 2.27E+10 3.72E+10 7.85E+09 0,00E+00 1.15E+10 4.14E+09 2.01E+08 CS.136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21E+08 9.80E+07 CS 137 3,23E+10 3.09E+10 4.56E+09 0,00E+00 1.01E+10 3.62E+09 1.93E+08 BA.140 1.18E+08 1.03E+05 6.86E+06 0.00E+00 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.79E+03 0.00E+00 1.36E+07 CE.144 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 PR 143 7.18E+02 2,16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 ND.147 4.45E+02 3.61E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5.71E+05 x

1 COMANCHE PEAK - UNITS 1 AND 2 REV 8 i PART ll 2-32 '

c . .. .. .. .. . ..

s -- - . _ . - _ _ _ -

TABLE 2.4 PATHVAY D/.~ FACTORS AGE GROUP: INFANT PATHVAY: GRAS 3. COW.MI LX l ORCAN DOSE FACTORS gUctIDE l...... ....... ... ..................................... ............

l BONE L1/ER T. BODY THYROID KIDNEY LUNG GI LLI H.3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E403 2.38E+03 P.32 1.60E+11 9.42E+09 6.21E+09 0.00E+00 0.00E400 0.00E+00 2.17E+09

.......................................u......................................

CR.51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 KN.54 0.00E+00 3.91E+07 8.85E+06 0.00E+00 8.65E+06 0.00E+00 1.43E+07 FE.55 1.35E+08 8.74E+07 2.34E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 FE.59 2.25E+08 3.93E+08 1.55E+08 0.00E+00 0.00E+00 1.16E+08 1,88E+08 CO.58 0.00E+00 2.43E+07 6.06E+07 0.00E+00 0.00E+00 0.00E+00 6.0$E+07 C0 60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 NI 63 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1,08E+08 IN.65 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.00E+00 1.61E+10 RB.86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR.89 1.26E+10 0.00E+00 3.62E+08 0.00E+00 0.00E+00 0.00E+00 2.50E+0S SR.90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 Y.91 7.34E+04 0.00F+00 1. 9 5 E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 ZR 95 6.81E+03 1. 66 E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.27E+05 NB 95 5.94E+05 2.45E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+08 RU.103 8.68E+03 0.00E+00 2.90E+03 0.00E+00 1.81E+04 0.00E+00 1.06E+05 RU.106 1.91E+05 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 1.45E+06 AC 110M 3.86E+08 2.82E+08 1.87E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE.125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 0. 00E+00 0.00E+00 7.19E+07 TE 127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE.129M 5.58E+08 1.91E+08 8.59E+07 2.14E+0F 1.39E+09 0.00E+00 3.33E+08 I.131 2.72E+09 3.2?E+09 1.41E+09 1.05E+12 75E+09 0.00E+00 1.15E+08 I.133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.00E+00 8.96E+06 CS.134 3.65E+10 6.81E+10 6.88E+09 0.00E+00 1.75E+10 7.19E+09 1.85E+08 CS.136 1.98E+09 5.83E+09 2.18E+09 0.00E+00 2.32E+09 4.75E+08 8.85E+07

.s............................................................................

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 0.00E+00 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 0.00E+00 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08 PR 143 1.49E+03 5.56E+02 7.37E+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 ND 147 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART ll 2-33

l I

TABLE 2.4 PATHVAY DOSE FACTORS AGE CROUP: ADULT PATHVAY: GRASS COV. MEAT l ORGAN DOSE FACTORS XUCLIDE l*...-.............................. .................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI H.3 0.00E+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 0.00E+00 0.00E+00 0.00E+00 5.21E+08 CR.51 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN.54 0.00E+00 9.18E+06 1.75E+06 0.00E+v0 2.73E+06 0.00E+00 2.81E+07 FE.55 2.93E+08 2.03E+08 4.73E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 FE.59 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0 ~ E+00 1.75E+08 2.08E+09 Co.58 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.70E+08 CO.60 0.00E+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41E+09 NI 63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 ZN.65 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08 RB.86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.59E+07 SR.89 3.02E+08 0.00E+00 8.66E+06 0.00E400 0.00E+00 0.00E+00 4.84E+07 SR 90 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08 v.91 1.13E+06 0.00E+00 3.03E404 0.00E+00 0.00E+00 0.00E+00 6.24E+08 ZR.95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 NB.95 2.30E+06 1.28E+06 6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 RU.103 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00 1.23E+10 RU.106 2.80E+09 0.00E400 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG.110M 6.68E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 .2.52E+09 TE.125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE.127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE.129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 I-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 1 133 3.68E.01 6.41E.01 1.95E.01 9.42E+01 1.12E+00 0.00E+00 5.76E.01 CS.134 5.58E+08 1.57E+09 1.28E+09 0.00E+00 5.07E+08 1.68E+08 2.74E+07 CS 136 1.21E+07 4.78E+07 3.d4E+07 0.00E+00 2.66E+07 3.65E+06 5.43E+06 CS*137 8,72E+08 1.19E+09 7.82E+08 0.00E+00 4.05E+08 1.35E+08 2.31E+07 BA.140 2.90E+07 3.64E+04 1.90E+06 0.00E+00 1.04E+04 2.08E+04 5.96E407 CE.141 1.41E+04 9.51E+03 1.08E+03 0.00E+00 4.42E+03 0.00E+00 3.64E+07 CE.144 1.46E+06 6.10E+05 7.83E+04 0.00E+00 3.62E+05 0.00E+00 4.93E+08 PR.143 2.09E+04 8.40E+03 1.04E+03 0.00E+00 4.85E+03 0.00E+00 9.17E+07 ND.147 7.08E+03 8.18E+03 4.90E+02 0.00E+00 4.78E+03 0.00E+00 3.93E+07 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART ll 2 34

TABLE 2.4 PATHVAY DOSE FACTORS AGE 7UP: TEEN PATHVAY: CRASS.COV. MEAT l ORGAN DOSE FACTORS KUCLIDE l.....................................................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+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 0.00E+00 0.00E+00 0.00E+00 3.29E+08 CR-51 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 MN.54 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 FE.55 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+08 7.31E+07 FE.59 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00 1.56 +d8 % 1.17E+09 Co.58 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+08 CO.60 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 NI-63 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E+00 0.00E+00 1.71E+08 ZN.65 2.50E+08 8.68E+08 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 RB.86 0.00E+00 4.06E+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00 6.00E+07 SR 89 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 SR.90 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 Y.91 9.54E+05 0.00E+00 2.56E+04 0.00E+00 0.00E+00 0.00E+00 3.91E+08 ER.95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 NB.95 1.79E+06 4.95E+05 5.48E+05 0.00S+00 9.64E+05 0.00E+00 4.25E+09 RU-103 8.56E+07 0.00E+00 3.66E+07 0.00E+00 3.02E408 0.00E+00 7.15E+09 RU.106 2.36E+09 0.00E+00 2.97E+08 0.00E+00 4.54E+09 0.00E+00 1.13E+11 AG.110M 5.06E+06 4.78E+06 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 TE.125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 0.00E+03 0.00E+00 8.94E+08 TE-127M 9.41E+08 3.34E+0B 1.12E+08 2.24E+08 3.81E+09 0.00E+00 2.35E+09 TE.120M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 1 131 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 1 133 3.08E-01 5.22E.01 1.59E-01 7.29E+01 9.16E.01 0.00E+00 3.95E.01 CS.134 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS.136 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 CS.137 7.24E+08 9.63E+08 3.35E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07 BA.140 2.39E+07 2.93E+04 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07 CE.141 1.18E+04 7.87E+03 9.05E+02 0.00E+00 3.71E+03 0.00E+00 2.25E+07 CE-144 1.23E+06 5.08E+05 6.60E+04 0.00E+00 3.03E+05 0.00E+00 3.09E+08 PR.143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 5.79E+07 ND.147 6.23E+03 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 COMANCHE PEAK . UNITS 1 AND 2 REV.8 PART 112-35

TABLE 2.4 PATHVAY DOSE FACTORS AGE CROUP: CHILD PATHWAY: CRASS COW. MEAT j ORGAN DOSE FACTORS NUCL1DE l.- - - *. -- - --* - -. - . - --...-- .. -

l BONE LIVER T. BODY THYROID KIDNEY LUNG CI LLI H.3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 P.32 7.38E+09 3.45L+08 2.85E+08 0.00E+00 0.00E+00 0.00E+00 2.04E+08 CR.51 0.00E+00 0.03E+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 KN.54 0.00E+00 8.01E+06 2.13E+06 0.00E+00 2.25E+06 0.00E+00 6.73E+06 FE.55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07

..............~ ..............................................................

FE.59 3.77E+08 6.10E+08 3.04E+08 0.00E+00 0.00E+00 1.77E+08 6.35E+08 CO 58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 CO 60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI.63 2.91E+10 1.56E+09 9.91E+08 0.00E+00 0.00E+00 0.00E+00 1.05E+08 ZN.65 3.76E+08 1.00E+09 6.22E+08 0.0CE+00 6.31E+08 0.00E+00 1.76E+08 RB.86 0.00E+00 5.76E+08 3.54E+08 0.00E+00 0.00E+00 0.00E+00 3.71E+07 SR.89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 SR.90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E*00 1.40E+08 Y.91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR.95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+0B NB.95 3.10E+06 1.21E+06 8.63E+05 0.00E+00 1.13E+06 0.00E+00 2.23E+09 RU.103 1.55E+08 0.00E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01E+09 RU.106 4.44E+09 0.00E+00 5.54E+08 0.00E+00 6.00E+09 0.00c+00 6.91E+10 AG.110M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+08 TE 125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5.49E+08 TE.127M 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 0.00E+00 1.44E+09 TE 129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 0.00E+00 2.18E+09 I.131 1.66E+07 1.67E+07 9.48E+06 5,52E+09 2.74E+07 0.00E+00 1.48E+06 I.133 5.72E.01 7.08E.01 2.68E.01 1.31E+02 1.18E+00 0.00E+00 2.85E.01 CS.134 9.23E+08 1.51E+09 3.19E+08 0.00E+00* 4.69E+08 1.68E+08 8.16E+0e CS.136 1.63E+07 4.48E+07 2.90E+07 0.00E+00 2.39E+07 3.56E+06 1.57E+06 CS.137 1.33E+09 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 BA 140 4.42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 CE-141 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE 144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1.89E+08 PR 143 3.33E+04 1.00E+04 1.65E&O3 0.00E+00 5.42E+03 0.00E+00 3.60E+07 ND.147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 l COMANCHE PEAK . UNITS 1 AND 2 PART ll 2-36 REE 8

a 1

i TABLE 2.4 PATHVAY DOSE FACT 0kS AGE GROUP: INFANT PATHVAY: GRASS.COV. MEAT

....s.........................................................................

] ORCAN DOSE FACTORS NUCLIDE l.....................................................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P.32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

.............................................................................. j CR.51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .

NN.54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

FE.55- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE.59 0.00E+00 0.00E+00 0.00E+00 0.00E+00_ 0.00E+00 0.00E+00 0.00E+00 Co.58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO.60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI 63 0.00E+00 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 ZN.65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

RB.86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 hR895 b$bbk bb b$bbk bb b$bbk bb b$bbk bb b$bbk bb 0$bbk bb b$bbb bb '

SR.90 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y.91: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ER.95 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB.95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU.106' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AG.110M -0.00E+00' O.00E+00 0.00E+00' O.00E+00 0.00E+00 0.00E+00 0.00E+00 ;

TE.125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

TE.127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.129M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L I 131: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

j. 1 133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.134 0.00E+00 .0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 ,

l L CS.136 0.00E+00 0.00EA00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 O.00E+00 L ....................................................................'..........

CS.137 0.00E+00 _0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA 140' O.00E+00 LO.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 CE.141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE.144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L PR 143 0.00E+00: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l' ND 147 0.00E+00. 0.00E+00 0.00EF00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 COMANCHE PEAK . UNITS 1_ AND 2 PART 112-37 REV.8

TABLE 2.4 PATHk'AY DOSE FACIORS AGE GROUP: ADULT PATHk'AY: GRASS. COAT. MILK l ORGAN DOSE FACTORS NUCLIDE l.................... .............................. .................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI H.3 0.00E+00 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 0.00E+00 0.00E+0) 0.00E+00 2.30E+09 CR.51 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN.54 0.00E+00 1.01E+06 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06 FE.55 3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 FE 59 3.87E+05 9.09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 Co.58 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 CO.60 0.00E+00 1.97E+06 4.35E+06 0.00E+00 0.00E+00 0.00E+00 3.70E+07 NI.63 8.08E+08 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E+07 EN.65 1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.51E+08 0.00E+00 3.30E+08 RB.86 0.00E+00 3.12E+08 1.45E408 0.00E+00 0.00E+00 0.00E+00 6.14E+07 SR.89 3.05E+09 0.00E+00 8.76E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 SR 90 9.84E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09 Y.91 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0.00E+00 5.68E+05 ZR.95 1.13E+02 3.63E+01 2.46E+01 0.00E+00 5.70E+01 0.0CE+00 1.15E+05 NB.95 9.92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.35E+07 RU.103 1.22E+02 0.00E+00 5.27E+01 0.00E+00 4.67E+02 0.00E+00 1.43E+04 RU.106 2.45E+03 0.000-00 3.10E+02 0.00E+00 i.73E+03 0.00E+00 1.59E+05 AG.110M 6.99E+06 6.47es 06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE.125M 1.96E+06 7.09E+05 2.62E+05 5.8>E+05 7.96E+06 0.00E+00 7.81E+06 TE.127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 2.23E+07 0.00E+00 1.84E+07 TE.129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.00E+00 3.64E+07 I. s 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 0.00E+00 1.34E+08 1-133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41E+07 0.00Ev00 7.28E+06 CS.134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.07E+08 CS.136 7.92E+08 3.13E+09 2.25E+09 0.00E+00 1.74E+09 2.38E+08 3.55E+08 CS.137 2.22E+10 3.03E+10 1.99E+10 0.00E+00 1.03E+10 3.42E+09 5.87E+08 BA.140 3.24E+06 4.07E+03 2.12E+05 0.00E+00 1.38E+03 2.33E+03 6.672+06 CE.141 5.82E+02 3.94E+02 4.47E+01 0.00E+00 1.83E+02 0.00E+00 1.51E+06 CE.144 4.30E+04 1.dGE+04 2.31E+03 0.00E+00 1.07E+04 0.00E+00 1.45E+07 PR.143 1.90E+01 7.60E+00 9.40E 01 0.00E+00 4.39E+00 0.00E+00 8. 30E+0/

ND 147 1.13E+01 1.31E+01 7.82E.01 0.00E+00 7.65E+00 0.00E+00 6.28E+04 COMANCHE PEAK . UNITS 1 AND 2 REV.8 PART 112-38

l TABLE 2.4 PATHVAY DOSE FACTORS AGE CROUP: TEEN PATHVAY: CRASS. COAT. MILK 1 ORGAN DOSE FACTORS NUCLIDE l..................-..... ............................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG CI.uLI H.3 0.00E+00 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 0.00E+00 0.00E+00 0.00E+00 3.18E+09

........ y....................................................................

CR.51 J.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 MN.54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 FE.55 5.79E+05 4.11E+05 9.56E+04 0.00E+00 0.00E+00 2.61E+05 1.78E+05 FE.59 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 CO.58 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 CO.60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 4.35E+07 N1 63 1.42E+09 1.00E+08 4.81E*07 0.00E+00 0.00E+00 0.00E+00 1.60E+07 ZN.65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+08 RB.86 0.00E+00 5.67E+08 2.67E+03 0.00E+00 0.00E+00 0.00E+00 8.40E+07 SR.89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 SR.90 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 Y.91 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0.00E+00 0.00E+00 7.78E+05 ZR.95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05 NB.95 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+07 RU 103 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02 0.00E+00 1.82E+04 RU.106 4.50E+03 0.00E+00 3.68E+02 0.00E+00 8.69E+03 0.00E+00 2.16E+05 AG.110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3.07E+09 TE.125M 3.61E+06 1.30E+06 4. 82 E+05 1.01E+06 0.00E+00 0.00E+00 1.06E+07 TE.127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2.52E+07 TE.129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 1 131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 1.79E+08 I.133 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 CS-134 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 CS.136 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2.89E+09 4.55E+08 4.27E+08 CS.137 4.02E+10 5.34E+10 1.86E+10 0.00E400 1.82E+10 7.07E+09 7.60E+08 BA.140 5.84E+06 7.16E+03 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+06 CE 141 1.07E+03 7.12E+02 8.13f+01 0.00E+00 3.3?i+02 0.00E+00 2.04E+06 CE.144 7.90E+04 3.27E+04 4.25E+S3 0.00E+00 1.95E+04 0.00E+00 1.99E+07 PR.143 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.06E+00 0.00E+00 1.15E+05 ND.147 2.18E+01 2.37E+01 1.42E+00 0.06E+09 1.39E+01 0.00E+00 8.54E404 COMANCHE PEAK - UNITS 1 AND 2 REV.8 l PART 112-39 4

_ _ -_. ._ _ m _ _ _ _ ._ _ _ _ . . .m _

TABLE 2.4 PA11NAY DOSE FACTORS AGE GROUP: CHILD PATHAY : CRASS GOAI .

l ORCAN DOSE FACTORS NUCLIDE l - ---- - -- - . - - . - -

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI H-3 0.00E+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 0.00E+00 0.00E+00 0.00E+00 2.5bE+09

........................... .................................................. \

CR 51 0.00E+00 0.00E+0- 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 l MN.54 0.00E+00 2.52Ed0 6.71E+05 0.00E400 7.06E+05 0.00E+00 2.11E+06 FE.55 1.45E+06 7.71E+d 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.43E+05 FE.59 1.56E+06 2.53E+06 1.26E+06 0.00E+00 0.00E+00 7.34E+05 2.64E+0/

CO.58 0.00E+00 1.46E+06 4.46E+06 0.00E+00 0.00E+00 0.00E+00 8.49E+06 CO.60 0.00E+00 5.18E+06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07 N1 63 3.56E+09 1.91E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 EN.65 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E+08 RB 86 0.00E+00 1.0$E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77E+07 SR.89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.39E+08 SR 90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.'6E+A9 .

Y 91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0,00E+00 6.24r+05 ZR 95 4.60E+02 1.01E+02 9.00E+01 0.00E+00 1.45E+02 0.00E+00 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 RU.103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29r+03 0.00E+00 1.33E+04 RU.106 1.11E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.73E+05 AG.110M 2.51E+07 1.69E+07 1.35E+07- 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE 125M 8.86E+06 2.40E+06 1.18E+06 2. 4 9 E+06 0.00E+00 0.00E+00 8.55E+06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07 TE 129M 3.26E+07 9.10E+06 5.06E+06 1.05E+07 9.56E+07 0.00E+00 3.97E+07 l 1-131 1.57E+09 1.57E+09 C.95E+08 5.21E+11 2.58E+09 0.00E+00 1.40E+08 l

l I-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07 l CS 134 6.80E+10 1.12E+11 2.35E+10 0.00E+00 3.46E+10 1.24E+10 6.01E+08 i CS.136 3.04E+09 8.36E+09 5.41E+09 0.00E+00 4.45E+09 6.64E+08 2,94E+08 i

CS-137 9.68E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 l BA.140 1.41E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 7.15E+06 l

CE 141 2.63E+03 1.31E+03 1.95E+02 0.00E+00 5.74E+02 0.00E+00 1,63E+06 CE.144 1.95E+05 6.11E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 PR.143 8.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 0.00E+00 9.29E+04 ND 147 5.34E+01 4.33E+01 3.35E400 0.00E+00 2.37E+01 0.00E+00 6.85F+04 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART 112-40

l i

l TABLE 2.4 PATHWAY DOSE FACTORS AGE CROUP: INFANT PATHVAY: CRASS. COAT. MILK l ORGAN DOSE FACTORS NUCLIOE I.......................................~ ........-................... ;

l BONE LIVER T. BODY THYROID KIDNEY LUNG C1.LLI l

.............................................................................. l H.3 0.00E+00 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 0.00E+00 0.00E+00 0.00E+00 7. 60E+09 i CR.51 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03- 2.46E+04 5.64E+05 MN.54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.7?E+06 -

FE-55 1.76E+06 1.14E+06 3.03E+05 0.00E+00 0.00E+00- 5.55E+05 1.44E+05 FE 59 2.92F+06 5.10E+06 -2,01E+06 0.00E+00 0.00E+00 1.51E+06 2.44E+06 Co.58 0.00E+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 CO.60 0.00E+00 1.06E+07 2.50E+07 0.00E+00 0.00E+00 0.00E+00 2,52E+07 NI.63 4;19E+09 2.59E+08 1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN 65 6.67E+08 2;29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+00 1.93E+09 RB.86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6 . 8 3 E+0 ~,

SR.89 2.65E+10 0.00E+00 7.59Ev08 0.00E+00 0.00E+00 0.00E+00 5.44E+08 SR.90 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 Y.91 8.80E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0 00E+00 6.31E+05 ZR.95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 NB.95 7.13E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 .0.00E+00 2.48E+07 RU 103- 1.04E+03. 0.00E+00' 3.48E+02 0.00E+00 2.17E+03 0.00E+00 1.27E+04 RU.106 2.28E+04 0.00E+00 -2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG 110M 4.63E+07 3.38E+07. 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1.75E+09 TE.125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06

-TE.127M 5.06E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 '

TE.129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3,99E+07 I.131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 -1.37E408 I.133 f4.36E+07 6.35E+07. 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 CS.134 1.09E+11 2.04E+11 '2.06E,10 0.00E+00 5.26E+10 2.15E+10 5.55E+08 -

CS.136 5.94E+09 1.75E+10 6.52E+09 0.00E+00- 6.96E+09 1.42E+09 2.65E+08 L ..............................................................................

CS.137 1.54E+11 1.81E+11 1.28E+10 0.00F+00 4.85E+10 1.96E+10 5.65E+08

'BA 140- 2.90E+07 1~.90E+04 1.50E+06- 0.00E+00 6.89E+03 1.78E+04 '7.13E+06 CE.141 5.21E+03 3.18E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64E+06 CE.144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4'.62E+04 0.00L+00 1.60E+07 L PR 143 1,78E+02 6.66E+01- 8.83E+00 0.00E+00 2.48E+01 0.00E+00 9 40E+04

ND.14'/ - 1.06E+02 1.09E+02 6.66E+00 -0.00E+00L 4.19E+01 0.00E+00 6.89E+04 P

COMANCHE PEAK UMYS 1 AND 2 REV.8 PART B 2-41

4 TABLE 2.4 PATHVAY DOSE FACTORS AGE CROUP: ADULT PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCL1DE l....*..... ....... ........... . ............... ...................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI .LLI H.3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 P.32 1.40E+09 8.69E+07 5.40E+07 0.00E+00 0.00E+00 0.00E+00 1.57E+08 CR.51 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN.54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 _9.58E+08 ,

FE.55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 FE.59 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+03 Coc58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+C8 CO.60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 3.14E+09 NI-63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 1.50E+08 ZN.65 3.17E+08 1.01E+09 4.56E+08 0.00E+00 5.75E+08 0.00E+00 6.36E+0B RB.86 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 SR.89 9.98E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 SR.90 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 Y.91 5.12E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.82E+09 ZR.95 1.17E+06 3.77E+05 2.55E+05 0.00E&OO .5.91E+05 0.00E+00 1.19E+09 NB 95 1.42E+05 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 RU.103 4.77E+06 0.00E+00 2.06E+06 0.?OE+00 1.82E+07 0.00E+00 5.57E+08 RU.106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 '3.72E+08 0.00E+00 1.2fE+10 AG.110M 1.05E+07 9.75E+06 5.79E+06 0.00E F00 1.92E+07 0,00E+C0 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 TF.127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.00E+00 1.17E+09 TE.129M 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 I.131 8.08F+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0,00E+00 3.05E+07 I.133 2.09E+06 .3.6?E+06 1.11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 CS.134 4.67E&O9 J'C0 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1_94E+08-CS.136 4.28E+0 i+08 1.22E+08 0.00E+00- 9.41E+07 1,29E+07 1.92E+07 CS.137 6.36E+vc 8,70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 BA.140 1.29E+08 1.62E+05' 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.66E+08 CE.141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 0.00E+00 5.10E+08 L ..............................................................................

l_ CE 144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0,00E+00 1.11E+10 L PR.143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08 l

ND.147 -3.34E+04 -3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 COMANCHE PEAK - LNTS 1 AND 2 FFV. 8 PART 112 42

TABLE 2.4 PATHWAY DOSE FACTORS ACE CROUP: TEEN PATHWAY: VEGETATION l ORGAN DOSE FAETORS NUC1.IDE }...... .. . ..... . ....--... ................................ ......

! BONE LIVER T. BODY THYROID KIDNEY LUNG LLI H.3 0.00E+00 2.59E+03 2.19E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 P.32 1.60E+09 9.91E+07 6.20E+07 0.00E+00 0.00E+00 0.00E+00 1,34E+0B CR.51 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 KN 54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 ...

FE.55 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+0B CO.58 0.00E+00 4.36E+07 1.01E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 CO.60 0,00E+00 2.49E+08 5.60E+38 0.00E+00 0.00E+00 0.00E+00 3.24E+09 NI-63 1,61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 ZN.65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9,42E+08 0.00E+00 6 P &OS RB.86 0.00E+00 2.73E+08 1.28E+08 0.00E+00 L 7JE+00 0.00E+00 4, r . -07 SR.89 1.52E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00t+00 1.80E+09 SR-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2,11E+10 #

Y.91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 ZR.95 1.72E+06 5.43E405 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NB 95 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 RU.103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 RU.106 3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10

AG.110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE-125M 1.4BE+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08

{

TE.127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E*09 j TE.129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 I.131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I.13? 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS.1;e 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 S-136 4.39E+07 1.722r08 1.16E+08 0.00E+00 9.41E+07 1.48E+07 1.39E+07 CS.131 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.39E+08 1.71E+05 8.97E+06 0.00E+00 5.782+04 1.15E+05 2.15E+08 CE.141 2.83E+05 1.89E+0! 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 CE.144 5,28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 PR.143 6.99E*04 2.79C+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 ND.147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08

. COMANCHE PEAK . UNITS 1 AND 2 REV.8 PART 112-43

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: VEGETATION l ORCAN DOSE FACTORS XUCLIDE }-- --..- --- - - ---- --- -- *- ------ -- - - -- - -

l BONE LIVER T. BODY YFYROID KID 11 LUNG CI.LLI H.3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+0? 4.02E+03 4.02E+03 P.32 3.35E+09 1.57E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 9.25E+07 CR.51 0.00E+00 0.00E+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN.54 0.00E+00 6.65E+08 1.77E408 0.00E+00 1.86E+08 0.00E+00 5.58E+0c FE.55 8.01E+08 4.2SE+08 1.32E&O8 0.00E+00 0.00E+00 2.40E+08 7.87E+07 FE 59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+08 CO-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 CO.60 0.00E+00 3.78E+08 1.12E+09 0,00E+00 0.00E+00 0.00E+00 2.10E+09 NI-63 3,95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+0' ZN-65 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+C LRB 86 0.00E+00 4.51E+08 2.77E+08 0.00E+00 0.00E+00 0.00E+00 2.90E+07 SR.89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 SR 90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y.91 1.F'E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 ER.95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+0B NB.95 4.11E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 RU.103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 AG-110M 3.21E+07 2.1'E+07 l'.73E+07 0.00E+00 4.04E+07 0.00E+00= 2.58E+09 TE.125M 3.51E+0B 7 50E407 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00E+00 1.07E+09 TE.129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 0.00E+00 1.02E+09 I.131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2,36E+08 0.00E+00 1.28E+07 I-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 CS.134 1.60E+10 2.53E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 CS.136 ,3.28E+07 2.28F.+08 1.47EF08 0.00E+00 1.21E+08 1.81E+07 8.00E+06

- CS.137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 BA.140 2.79E+08 2.44E+05 1.63E+07 0.00E+00 7.96E+04 1.46E+05 1.41E+08 CE-141 6.57E+05 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 4.09E+08 CE-144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10 PR.143 1.45E+05 4.36E+04 7.21E+03 0.00E+00 2.36E+04 0.00E+00 1.57E+08 ND 147 7.15E+04 5.79E+04 4.49E+03 0.00E+00 3.18E+04 0.00E+00 9.18E+07 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART ll 2-44

i TABLE 2.4 PATHVAY DOSE FACTORS AGE GROUP: INFANT PATHVAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE I..- .--.-.-.--- ---- ---- --- - --.. .--...--- ----.--.------. ---.

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P.32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 bk.51 b.bbb$bb N 5bk$bb b.bb $bb b.bb +bb b.bbk$bb b.bbk$bb b.bbk$bb MN.54 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00t+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE.59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co.58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

CO-60 0.00E+00 0.00E+00 0.00E+00 0.00F+00 0.00E+00 0.00E+00 0.00E+00 NI.63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN.65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR.89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR.90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y.91 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 ZR-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e NB.95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU 103 0.00E+00 0.00E+00 0.006 90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RU-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AG.110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE.125M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 TE-127M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E.00 TE-129M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 05 134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS.137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BA-149 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

CE-l'.1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ND.147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 COMANCHE PEAK - UNITS 1 AND 2 REV.8 PART 112-45

.. - - . - - ~ ~ _ - - - . -- . - - - - . - _ - - - .

TABLE 2.4 PATHWAY DOSE FACTORS-AGE GROUP: ADULT PATHWAY: INHA1ATION l ORGAN DOSE EACTORS NUCLIDE l..*. . -.. . .-..-- - -. . -- -- - - -.--- - -- -.--* - -- -- .

l BONE LIVER T. BODY THYROID KIDNEY LUNC GI.LLI H.3 0.00E+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 0.00E+00 0.00E+00 0.00E+00 8.64E+04 CR.51 0.00E+00 _0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 KN.54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04

-FE.55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 FE.59 1.18E+04 2.78E+04 1.16E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 Co.58 0.00E+00- 1.58E+03 2.07E+03. 0.00E+00 0.00E+00 9.28E+05 1.06E+05 >

CO.60 0.00E+00 1 15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 hkS65 b$bbk bb b$k b bb k$bbk b5 b$bbk bb b$bbb bb k$78h bb k b b bb ZN.65- 3.24E+04' 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 RB.86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 L .E+04 SR.89- 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05

-SR.90- .9.92E+07 0.00E+ ) 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 Y.91 4.62E+05 0,00E+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 0.00E+00 5.42E+04 1.77E+06 1.50E+05 NB.95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 RU.103 1.53E+03- 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 RU.106 6,91E+04 0.00E+00 8.72E+03 0.00E+00' 1.34E+05 9.36E+06 9.12E+05 AG.110M 1.08E+04- 1.00E+04 5.94E+03' O.00E+00 1.97E+04 4.63E+06 3.02E+05 TE.125M- 3.42Et03 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 1.57Et03 3.29E+03 4.58E+04 9.60E+05 1.50E+0; TE.129M 9.76E+03 4.67E+03 1.58E+01 3.44E+0*> 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 0.00E+00 6.28E+03 I.133 8.64E+03 1.48E+04 4,52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03

.CS.134 3.73E+05. 8.48E+05 7.28E+05. 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS.136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS.137- 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03

. BA.140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE-141 -1.99E+04 1.~35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 -1.20E+05 CE.144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 PR.143' 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05

COMANCHE PEAK - UNITS 1 AND 2 PART 112-46 REV.8

.- - . . - - - - - - . - - - - - - . . -.- .~,

m TABLE 2.4 PATWAY DOSE FACTORS AGE GROUP: TEEN PATWAY: INHA1ATION

' [ . ORGAN DOSE FACTORS NUCL1DE- l.....-- ..-- -- .-.--.- - ~ -.-- --*.-..--.... ...-- . - .-..

'l BONE 1 LIVER T BODY THYROID KIDNEY LUNG GI-LLI H.3 'O.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P 32 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.28E+04 CR 51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03

.MN.54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE.55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 FE.59 1,59E+04 3.70E+04 -1.43E+04 -0.00E+00 0.00E+00 1.53E+06: 1.78E+05-

-CO.58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 CO.60 'O.00E+00 1.51E+04 1.98E+04- 0.00E+00 7,30E+00 8.72E+06' 2.59E+05

, NI.63 5.80E+05~ 4.34E+04. 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04-ZN-65 3.86E+04l1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 RB.86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 SR.89' '4.34E+05 0.00E+1 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 LSR.90 1.08E+08- 0.00E+49 6 68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y.91 6.61E+03- 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 ZR.95 1-. 46 E+05 4.58E+04 3.15E+04- 0.00E+00 6.74E+04 2.69E+06 1.49E+05 NB.95 1,86E+04 '1.03E+04 '5.66E+03- 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU 103 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05

-RU.106 9,84E+04 0.00E+00 -1.24E+04 0.00E+00 1.90E+05- 1.61E+07 9.60E+05 AG 110M 1.38E+04 1.31E+04 7.99E+03 0.00E+00 -2.50E+04 6.75E+06 2.73E+05 TE.125M 4.88E+03 2.24E+03 - 6.67E+02 1.40E+03 0.00E+00 5 '. 36 E+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 JTE.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+04L~4.91E+04 2.64E+04 -1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-133- .1.22E+04 .2.05E+04- 6.22E+03- 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS.134 5.02E+05 1.13E+06 .5.49E+05 0.00E+00- 3.75E+05 1.46E+05 9.76E+03 CS.136- 5.1SE+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 '1.09E+04 CS.137 6.70E+05 8.48E+03 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA.140 5.47E+04 6.70E+01- 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 CE.141- 2.84E+04 1.90E+04 2.17E+03 ~ 0.00E+00 8.38E+03 6.14E+05 1.26E+05 CE.144 4;89E+06 2,02E+06. 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 PR 143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03' 4.83E+05' 2.14E+05 ND.147 7.86E+03 S.56E+03 5.13E+02 0.00FF00 5.02E+03 3 . 7'iE+0 5 1.82E+05

- COMANCHE PEAK . UNITS 1 AND 2 REV.8 PART Il 2-47

= = -- . . .-

TABLE 2.4 PATWAY DOSE FACTORS AGE GROUP: CHILD PATHVAY: INHALATION l ORGAN DOSE FACTORS XUCLIDE l...................................................-.................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+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 0.00E+00 0.00E+00 0.00E+00 4.22E+04 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.0dE+03 KN.54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE.55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE-59 2.07E+04. 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1 27E+06 7.07E+04 CO-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB.86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR.89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR.90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y-91 9 -.14 E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 7.R.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB.95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU.103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E*05 4.48E+04 RU 106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1,84E+05 1.43E+07 4.29E+05 AG-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 T 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 0.00E+00 2.84E+03 I-133 1.66E+04 2.03E+04 '

.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS.134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03-CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+0a BA.140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 '1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.557+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND-147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 COMANCHE PEAK - LNTS 1 AND 2 pp.4T ll 2-48 REV.8

TABLE 2.4 PATHVAY DOSE FACTORS AGE GROUP: INTANT PATHVAY: INHALATION l ORCAN DOSE FACTORS NUCLIDE l - ---- - - - - - .- - - - - - - - -- - - -

l BONE 11VER T. BODY THYROID KIDNEY LUNG CI-LLI H.3 0.00E+00 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 0.00E+00 0.00E+00 0.00E+00 1.61E+04 CR.51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN.54 0.00E+00 2.53E+04 4.98E+03 0.00F+00 4.98E+03 1.00E+06 7.06E+03 FE.55 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 FE.59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 CO.58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CO.60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 Nkhh h h9k bh h bkk bb k k6k hk b bbk bb b bbk bb h b9k bh h khh b3 ZN.65 1.93E+04 6,26E+04 3.11E+04 0,00E+00 3.25E+04 6.47E+05 5.14E+04 RB 86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03 SR.89 3.98E+05 0.00E+00 -1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR.90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Y.91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 IR.95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 NB.95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 RU.103 2,02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU.106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 AG.110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+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 3.18E+04 1.68E+06 6.90E+04 I.131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I.133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS.134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS.136 4.S3E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03

...............s...............................................................

C5 137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA.140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 CE 144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 PR.143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND.147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 COMANCHE PEAK - UNITS 1 AND 2 PART ll 2-49 REV.8

TABLE 2.5 8 IIE (Sheet 1of2)

CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1), AND 5 ATHOSPHERIC OISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3)

Pathway Distance X/Q D/Q 5 Sector (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6_1 Resident 2.20 9.28E-07 5.32E-09 5 N Garden. 3.3 --

2.10E-09 7 Milk Cow 4.4 --

1.06E-09 7 Resident 2.30 5.126-07 2.60E-09 5 NNE Garden 2.40 --

2.30E-09 5 Milk Cow None -- --

5 Resident 2.30 3.58E-07 1.28E-09 5 NE Garden 2.70 --

8.92E-10 5 Milk Cow 4.9 --

2.38E-10 7 Resident 2.40 2.58E-07 7.08E-10 5 ENE Garden 2.5 --

6.10E-10 7 Milk Cow None -- --

5 Resident 2.40 3.02E-07 6.62E-10 5 E Garden 3.3 --

3.32E-10 7 Milk Cow Ncne -- --

5 Resident 2.0 4.7E-07 1.20E-09 7 ESE Garden 2.30 --

9.00E-10 5 Milk Cow Hone -- --

5 Resident 2.00 7.10E-07 2.80E-09 5 SE Garden 2.50 --

1.60E-09 5 Milk Cow None -- --

5

, Resident 1.60 9.96E-07 5.92E-09 5 SSE Garden 1.7 --

5.24E-09 7 Milk Cow 2.20 --

1.80E-09 5 Resident 1.60 7.74E-07 4.66E-09 5 S Garden 1.8 --

5.38E-09 7 Milk Cow None -- --

7 Resident ~' 1.90 4.42E-07 2.06E-09 5 SSW Garden 4.3 --

2.92E-10 7 Milk Cow None -- --

5 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 2-50

TABLE 2.5 8 (Sheet 2of2)

CONTROLLING RECEPT 0R PATHWAYS AND LOCATIONS (NOTE 1), AND S ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3)

Pathway Distance X/Q D/Q 5 Sector (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6)

Resident 1.00 1.60E-06 7.50E-09 7 SW Garden 1.7 --

1.98E-09 5 Milk Cow None -- --

5 Resident 1.00 1.80E-06 6.50E-09 5 WSW Garden 1.5 --

2.20E-09 7 Milk Cow None -- --

5 Resident 1.50 8.40E-07 2.80E-09 5 W Garden 1.50 --

2.80E-09 5 Milk Cow None -- --

5 Resident 4.0 2.00E-07 5.00E-10 7 WNW Garden 3.00 --

1.04E-09 5 Milk Cow None -- --

5 Resident 2.70 6.98E-07 2.24E-09 5 NW Garden None -- --

5 Milk Cow None -- --

5 Resident 2.70 7.62E-07 3.22E-09 5 NNW Garden 3.6 --

1.60E-09 7 Milk Cow None - - - --

7 NOTES:

(1) Receptor locations are taken from the nearest receptor 5 locations identified in the CPSES 1991 land use census.

(2) In addition to the pathways shown, the inhalation and ground 5 plane pathways are present at the nearest resident.

(3) The units for X/Q are Sec/ Cubic Meter. 5 (4) X/Q Values at distances 1.0, 1.5, 2.0, 2.5, 3.5, 4.0, 4.5, 5 and 6.0 miles were taken from-Table 2.3-16. " Average Annual Relative Concentration at CPSES," of the CPSES Environment Report, Operating Licensing Stage (Reference 3). The X/Q values at other distances were determined by linear interpolation.

(5) The units for D/Q are inverse square meters. 5 (6) D/Q values at distances 1.0, 1.5, 2.0, 2.5, 3.5, 4.0, 4.5, 5 and 6.0 miles were taken from Table 2.3-17. " Average Annual Relative Deposition Rate," of the CPSES Environmental Report, Operating License Stage (Reference 3). The D/Q values at other distances were determined by linear. interpolation.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-51

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1 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 described in Table 3.1 and shown on the map in Figure 3.1.

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 8 be performed as specified in Section 2.5.

The sampling locations shown on Table 3.1 are the minimum locations required for compliance with Radiological Effluent Control 3/4.12.1. If desired, additional locati:ns may be monitored as-special studies to evaluate potential pathways of exposure without adding such locations to the monitoring program given in Table 3.1.

3.2 INTERLABORATORY COMPARISON PROGRAM for the purpose of implementing Radiological Effluent Control 3/4.12.3, TU Electric has contracted Teledyne Isotopes Midwest Laboratory to perform the Interlaboratory Comparison Program.

The program is operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to the participant laboratories. The purpose of the program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the REV. 8 CDMANCHE PEAK - UNITS 1 AND 2 PART II 3-1

participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control- limits i. iicate a need to check the instruments or procedures used. Teledyne participates in the environmental sample crosscheck program for milk and water samples conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. The results of the program are included in the Annual Radiological Environmental Operating Report, as required by CPSES Technical Specification 6.9.1.3.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-2

Table 3.1 Environmental Sampling Locations -

Sampling Location Sample Point (Sector - Miles) h(1)

Al N-1.45 (Squaw Creek Park) A A2 N-9.4 (Granbury) A A3 E-3.5 (Children's Home) A A4 SSE-4.5 (Glen Rose) A A5 S/SSW-1.2 A A6- SW-12.3(Control) A i

A7 SW/WSW-0.95 A A8 NW-1.0 A R1 N-1.45 (Squaw Creek Park) R R2 N-4.4 R R3 N-6.5 R R4 N-9.4 (Granbury) R R5 NNE-1.1 R R6 NNE-5.65 R _

NE-1.7 R7 R R8 NE-4.8 R R9 ENE-2.5 R R10 ENE-5.0 R R11 E-0.5 R REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 3-3

Table 3.1 (Continued)

~

Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Tyng(l)

R12 E-1.9 R R13 E-3.5 (Children's Home) R R14 E-4.2 R R15 ESE-1.4 R o

Rio ESE-4.7 R R17 SE-1.3 R R18 SE-3.85 R R19 SE-4.6 R R20 SSE-1.3 R R21 SSE-4.4 (Glen Rose) R R22 SSE-4.5 (Glen Rose) R R23 5-1.5 R R24 S-4.2 R R25 SSW-1.1 R R26 SSW-4.4 (State Park) R R27 SW-0.9 R R28 SW-4.8 (Girl Scout Camp) R R29 SW-12.3 (Control) R R30 WSW-1.0 R R31 WSW-5.35 R REV. 8 '

COMANCHE PEAK - UNITS 1 AND 2 PART 11 3-4

.u Table 3.1 (Continued)

Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Tyag(l)

R32 WSW-7.0(Control) R R33 W-1.0 R R34 W-2.0 R R35 W-5.5 R R36 WNW-1.0 R R37 WNW-5.0 R R38 WNW-6.7 R R39 NW-1.0 R R40 NW-5.7 R R41 NW-9.9 (Tolar) R R42 NNW-1.35 R R43 N P-4.6 R SW1 N-1.5 (Squaw Creek Reservoir Marina) SW SW2 N-9.9 (Lake Granbury) SW/0W(2)

SW3 N-19.3(Control-BrazosRiver) W SW4 NE-7.4 (Lake Granbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW(3)

SW6 NNW-0.1 (Squaw Creek Reservoir) SW/DW(4)

GW1 W-1.2 (NOSF potable water) GW GW2 WSW-0.1 (Plant potable water) GW(4),(5) l-REV. 8 COMANCHE PEAK - UNITS 1 ANO 2 PART 11 3-5

Thble 3.1 (Continued)

Environmental Sampling Locations Sampling Location Sample _

Point (Sector - Miles) J_yp_q(1)

GW3 SSE-4.6 (Glen Rose) GW(5)

GW4 N-9.8(Granbury) GW(2),(5)

GW5 N-1.45 (Squaw Creek Park) GW(5)

SS1 NNE-1,0(SquawCreekReservoir) SS SS2 N-9.9 (Lake Granbury) SS SS3 NE-7.4 (Lake Granbury) SS M1 SSE-2.2 M M2 not used (6) g H3 not used (6) g M4 SW-13.5(Control) M F1 ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F FP1 ENE-9.0 (Leonard Bros. Pecan Farm) FP FP2 E-4.2 (truck farm) FP FP3 Deleted FP 6 FP4 SW-12.2(Control) FP 6 BL1 N-1.45 BL BL2 SW-1.0(7) BL BL3 BL SW-13.5 (Control)(7)

(1) Types:

A - Air Sample; R - Direct Radiation; SW - surface Water; GW - Ground Water; SS - Shoreline Sediment; M- Milk; j F - Fish; FP - Food Products; BL - Broad Leaf Vegetation.

l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-6

(2) The municipal water system for the City of Granbury is supplied by surface water from Lake Granbury (location SW2) and ground well water (location GW4). Each of these input supplies for the Granbury municipal water system is sampled. These samples are not required for compliance with Radiologica Effluent Control 3/4.12.1, Table 3.12-1, because they are not affected by plant discharges.

(3) This sample (location SWS) is representative of discharges from Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury.

(4) . The plant potable water is supplied by surface water from Squaw Creek Reservoir (location SW6) and ground well water (location GW2). Each of these input supplies for plant potable water is sampled.

(5) Grour.d water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 and are therefore not required to be monitored for radioactivity to meet the requirements of the Radiological Environmental Monitoring Program specified in Radiological Effluent Control 3/4.12.1, Table 3.12-1. Although not required for compliance with the Radiological Environmental Monitoring Program groundwater sampling locations are included in the monitoring program to provide confirmation that ground water is not affected by plant discharges.

(6) Due to the current availability of milk sampling locations, milk samples are taken at only two locations (i.e., one sample and one control). If additional milk sampling locations are identified in future land use census, this table will be revised to include up to a maximum of 3 samples and one control, as indicated in the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1. Table 3.12-1.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-7

(7) Per the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1, Table 3.12-1, broad leaf vegetation is required to be sampled only when milk sampling is not performed at all required locations. Broad leaf sampling will be performed at the specified locations if milk samples are unavailable from any location.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-8

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Rev.6 113-9 7/91 Q OSl]oz31-o'

APPENDIX A PATHWAY DOSE RATE PARAMETER Pj (inhalation) = K'=(BR) DFAi [Eq. A-1]

where:

Pj = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem /yr per microcurie /m3 The dose factors are based on the critical individua. 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) 0FAj = 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 0FAj (mrem /yr per uCi/m3)

(Eq. A-2)

The latest NRC Guidance has deleted the requirement to determine Pj

-(ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II A-1

APPENDIX B I

INHALATIONPATHWAY00SEFACTOR(R i.a.o) 3 Rf,a,o = k' (BR) (DFAi,a,o) (mrem /yr per microcurie /m ) [Eq. B-1]

where:

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)

DFA i ,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 0FAi ,a,o. Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Ref.2) l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II B-1 i

I 1

APPENDIX C GROUND PLANE PATHWAY DOSE FACFR (R G) 4 R = k' k" (SF) DFG 4 ['l-e'A i t)/Aj ] [Eq. C-1]

where:

k' = conversion factor, 106 pC1/ microcurie k" = conversion factor, 8760 hr/yr Aj = decay constant for the ith radionuclide, sec -1 t = the exposure time (this calculation assumes that decay is the only operating remova i mechanism) 4,73 x 108 sec.

(15 yrs)

DFGi =the ground pla^e dose conversion factor for the ith radionuclide (mrem /hr per pCi/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Ref. 2). These values apply 1 to all age groups, ilose 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)

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II C-1

i APPENDIX 0 C

GRASS C0W-MILK PATHWAY DOSE FACTOR (R 1,a,o)

Rf,a,o = k' [(Qp xUAP) / (A l ^A w)] x (Fm ) x (r) x (DFLi,a,o) *

[((f px f )/ Y ) + ((1-f p x f,) e'Aih t )/Y 3] e~^i f t

[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/m2 (NUREG-0133)

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

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

1.109).

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

DFL i .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) '

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

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 0-1

}

APPENDIX D (CONTINUED) th = 7.78 x 106 sec, the transport time from pasture to harve',t to cow to milk to receptor (Table E-15. R.G.

1.109) fp = t.0, the fraction of the year that the cow is on pasture, f

s = 1.0, the f/ action of the cow feed that is pesture grass while the cow is on pasture.

The concentrction of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, R C 33 _

basedon(X/Q):

t,a.o = k ' k "' F 07UAP U t,a,o (.75 (.5/H)) [Eq.D-2]

where:

k = 103 grams /kg H = 8 grams /m3, absolute humidity of the atmospnere 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. (NilREG-0152)

l.t.a.o the ingestion dose f actor for tritium ano 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.

C NOTE: Goat-milk pathway factor, R i,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 for goats is 6 kg/ day from Table E-3, R. G. 1.109 8 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II D-2

APPENDIX E COW-MEAT PATHWAY DOSE FACTOR (RMi a.o)

R"i.a.o

k' (OFxUAP)/I^i

A w) x (F f) x (r) x (DFL 4 ,g) x

-Aif t

[((f x f )/Y ) + ((1 - f f ) g p 3 p ps At)/q)xe 4h

[Eq.E-1]

where: -

k' = conversion factor, 106 picocurie / microcurie (pCi/uC1)

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

VAP = 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 transfc? coefficients, days /kg.

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

DFL1 ,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)

Aj = decay constant for radionuclide i, sec-1 Aw

= decay constant for weathering, 5.73 x 10-7 sec -1 (NUREG-0133) tr = 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 recep;ur (NUREG-0133)

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 E-1 1

l t

. - . - - - ..-=- ..

APPENDIXE(CONTINUED) ,

Yp = agricultural productivity by unit area of pasture feed !

grass 0.7 kg/m2 (NUREG-0133) ,

Ys = agriw 'tural productivity by unit area of stored .

2.0 kg/m2, (NUREG 0133) 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 tritisim in meat is based on its airborne concentration rather thc,: the deposition. Therefore RM 1 4, based on (X/Q):

R

,g [Eq.E-E]

= k ' k "' Ff QUAP p (DFLt.a.o) x 0.75 x {0.5/M) where:

All terms are as defined above and in Apperidix 0, REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II E-2

APPENDIX F V

VEGETATION PATHWAY DOSE FACTOR (R )

R k' x [r/ (Y y (A 4 + Ag ))] x (DFL$g,g)x[(Uk)fL e-A tit

+Uff g e ^^ih]

t

[Eq.F-1]

where:

k' = 106 picocurie / microcurie (pCi/uti)

UL A = the consumption rate cf fresh leafy vegetation, O, 26, 42, 64kg/yr for inf ant, child, teenager, or adult age groups respectively. (R.G. 1.109)

US A = the consumption rate of stored vegetation, O, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G.1.109) ft = the fraction of the annual intake of fresh leafy _

vegetatiori grown locally,1.0 (NUREG-0133) fg = the fraction of the stored vegetation grown locally .76 (NUREG-0133) t l

= 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))

t h ' 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))

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 F-1

i APPEND'XF(CONTINUED) yy = the vegetation areal density, 2.0 kg/m2 (Table E-15, 8 i R.G. 1.109)

All other parameters are as previously defined.

The concentration of tritium in vegetation is based on the airborne '

Y concentration rather than the deposition. Therefore, R j is basedon(X/Q)

Rf,a.o = k ' k '"

[Ukft+Uf() (DFLt.a,0) (.75(.5/H)) [Eq. F-2]

where:

All terms-are as defined above and in Appendix 0.

t REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 c-2 e

_,..__..;_....~..._....___.._...._._...._...-.-...._..__..___.._..._.._........._....c.__..,.._.,.....,_.. , _ . . . . . _ , , _ , _ . . . . _ ,

I APPENDIX G 8 SUPPLEMENTAL GUIDANCE STATEMENTS HAVE BEEN DELETED sc REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART 11 G-1

_ - ___ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _

ML20096H457

Text

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