Text

Rev 8 to ODCM for Comanche Peak Steam Electric Station Ubits 1 & 2
	ML20056G007
Person / Time
Site:	Comanche Peak
Issue date:	01/31/1993
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20056G003	List: ML20056G002; ML20056G005; ML20056G007; ML20056G009;
References
	PROC-930131, NUDOCS 9309010146
	Download: ML20056G007 (200)
	v • d • e

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l OFFSITE DOSE CALCULATION MANUAL FOR

. TU ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 1

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' Rev 8 9309010146 930827 I 01/93 PDR ADDCK 05000445 l-R PDR ca i

TABLE OF CONTENTS Elit :

List of Tables v List of Figures vii Cross Reference to Technical Specifications and REC viii References xi Introduction xii 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 - Applicabil'ity I 3/4-1 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 Contamination 1 3/4-15 l 3/4.11.1 -

Liquid Effluents I 3/4-17 3/4.11.1.1 - Concentration Controls I 3/4-17 3/4.11.1.2 - Dose I 3/4-21 3/4.11.1.3 - Liquid Radwaste Treatment System I 3/4-22 3/4.11.1.4 - LVW Pond Resin Inventory I 3/4-22a l

3/4.11.2 Gaseous Effluents I 3/4-23 3/4.11.2.1 - Dose Rate I 3/4-23 3/4.11.2.2 - Dose - Noble Gases I 3/4-27 3/4.11.2.3 - Dose - Iodine-131. 1 3/4-28 Iodine-133. Tritium, and Radioactive Material in Particulate Form 3/4.11.2.4 - Gaseoas Radwaste Treatment System I 3/4-29 COMANCHE PEAK - UNITS 1 AND 2 i Rev. 8 1/93

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TABLE OF CONTENTS

.P_g.gg 3/4.11.4 - Total Dose I 3/4-30 3/4.12.1 - Radiological Environmental Monitoring I 3/4-32 Program 3/4.12.2 - Land Use Censur I 3/4-44 I

3/4.12.3 - Interlaboratory Comparison Program I 3/4-45 BASES I B 3/4 0 l

SECTION 5.0 - DESIGN FEATURES I 5-0 5.1.3 - Map Defining Unrestricted Areas and I 5-1

' J Site Boundary for Radioactive Gaseous and Liquid Effluents '

SECTION 6.0 - ADMINISTRATTVE CONTROLS I 6-0 6.9.1.3 - Annual Radiological Environmental I 6-1 Operating Report

.6.9.1.4 - Semiannual Radioactive Effluent I 6-2 Release Report 6.14 - Offsite Dose Calculation Manual (ODCM) I 6-3 PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS II 1-1 1.1 10CFR20 And Radiological Effluent Control II 1-2 3/4.11.1.1 Compliance 3

1.1.1 Isotopic Concentration of the Waste II 1-3

, Tank 1.1.2 Effluent Flow Rate (f) II 1-3 1.1.3 Dilution of Liquid Effluents II 1-4 l 1.1.4 Actual Dilution Factor (ADF) II 1-5 1.1.5 Required Dilution Factor (RDF) II 1-6 ;

1.1.6 10CFR20 Compliance II 1-6 COMANCHE PEAK - UNITS 1 AND 2 11 Rev. 8 1/93 I

TABLE Of CONTENTS l P_g5Lg 1.2 Radiation Monitor Alarm Setpoints II 1-7 l 1.2.1 Primary Liquid Effluent Monitor II 1-7 (XRE-5253) 1.2.2 Turbine Building Sump Effluent II 1-8 Radiation Monitors (IRE-5100 and 2RE-5100) l 1.2.3 Service Water Effluent Radiation II 1-9 l Monitors (IRE-4269/4270 and 2RE-4269/4270) l 1.3 Dose Calculations for Liquid Effluents II 1-10 1

1.3.1 Calculation of Dose Due to II 1-11 l Liquid Releases i l

1.3.2 Calculation of Dose Due to II 1-12 l I

Radionuclide Buildup in the Lake 1.4 Dose Projections for Liquid II 1-15 l Effluents 1 1.5 Definitions of Common Liquid Effluent Parameters II 1-16 2.0 -GASEOUS EFFLUENTS II 2-1 2.1 Radiological Effluent Control 3/4.11.2.1 Compliance II 2-3 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 2.2 Gaseous Effluent Monitor Setpoints II 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 Monitors (XRE-5570A/X4E-5570B and XRE-5567A/XRE-55678) II 2-8 2.2.3 Sampler Flow Rate Monitors (X-RFT-5570A-1/X-RFT-55708-1) II 2-9 2.2.4 Auxiliary Building Ventilation Exhaust II 2-9 Monitor (XRE-5701) 2.2.5 Containment Atmosphere Gaseous Monitors II 2-10 (IRE-5503'tRE-5503)

COMANCHE PEAK - UNITS 1 AND 2 iii Rev. 8 1/93

l TABLE OF CONTENTS 1

PL91 1 2.3 Dose Calculations for Gaseous Effluents II 2-12 2.3.1 Dose Due to Noble Gases !! 2-12 2.3.2 Dose Due to Radiciodines. Tritium, and Particulates II 2-13 1 2.4 Dose Projections for Gaseous Effluents II 2-15 2.5 Dose Calculations to Support Other II 2-16 Requirements 2.6 Meteorological Model II 2-18 9

2.6.1 Dispersion Calculations II 2-18 2.6.2 Deposition Calcu1ations II 2-20 2.7 Definitions of Gaseous Effluents Parameters II 2-21 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING II 3-1 .

l 3.1 _ Sampling Locations II 3-1 l 3.2 Interlaboratory Comparison Program II 3-1 l APPENDIX A. Pathway Dose Rate Parameter A-1 B. Inhalation Pathway Dose Factor B-I C. Ground Plane Pathway Dose Factor C-1

0. Grass Cow-Milk Pathway Dose Factor D-1 E. Cow-Meat Pathway Dose Factor E-1 F. Vegetation Pathway Dose Factor F-1 G. Supplemental Guidance Statements - Deleted G-1 COMANCHE PEAK - UNITS 1 AND 2 iv Rev. 8 i 1/93

List of Tables Table No. Title ,P_gjtt PART I - RADIOLOGICAL EFFLUENT CONTROLS 1.1 Frequency Notation I 1-5 e 1.2 Operational Modes I 1-6 3.3-7 Radioactive Liquid Effluent Monitoring I 3/4-4 j Instrumentation i l

4.3-3 Radioactive Liquid Effluent Monitoring I 3/4-6 l Instrumentation Surveillance Requirements j 3.3-8 Radioactive Gaseous Effluent Monitoring I 3/4-9 Instrumentation ,

1 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 Waste 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

4.12-1 Detection Capabilities for Environmental I 3/4-41 Sample Analysis (LLDs)

PART II - CALCULATIONAL METHODOLOGIES 1.1 Summary of Liquid Release Pathways II 1-19

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1.2 Site Related Ingestion Dose Commitment II 1-20 ;

Factor (Aq )

2.1 Summary of Gaseous Release Pathways II 2-26 2.2 Dose Factors for Exposure to a Semi- II 2-27 Infinite Cloud of Noble Gases 2.3 Pathway Dose Rate Parameter (Pj) II 2-28 4

COMANCHkPEAK-UNITS 1AND2 y Rev. 8 1/93

l List of Tables Table No. Title P121 2.4 Pathway Dose Factors II 2-29 2.5 Controlling Receptor Pathways and II 2-50 Locations, and Atmospheric Dispersion !

Parameters (For Dose Calculations Required by Radiological Effluent Control 3/4.11.2.3) 3.1 Environmental Sampling Locations II 3-3 l

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List of Ficures Fioure Title Pigg PART I - RADIOLOGICAL EFFLUENT CONTROLS 5.1-3 Controlled Area. Unrestricted Area- I 5-2 and Site Boundary for Radioactive Gasecus and Liquid Effluents PART II - CALCULATIONAL METHODOLOGIES 1.1 Liquid Effluent Discharge Pathways II 1-24 1.2 Circulating Water Pump Curves II 1-26 1.3 Energy Response to Gamma Radiations II 1-27 for RD-33 Type Detector 2.1 Gaseous Waste Processing System II 2-52 2.2 Plume Depletion Effect for Ground II 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 II 2-56 3.1 Radiological Environmental Monitoring II 3-9 Locations COMANCHE PEAK - UNITS 1 AND 2 vii Rev. 8 1/93

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Cross Reference Qo Technical Soecifications and REC l Number or Document Section Recuirement ODCM Section PART I-RADIOLOGICAL EFFLUF"T CONTROLS (REC)

Tech Specs 6.8.3.e.1 Effluent monitoi a 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 Tech Specs 6.8.3.e.4 Limit doses due to liquid effluents 3/4.11.1.2 a i 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 i operability requirements 3/4.11.2.4 j

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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 the environment 4

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 REC 3/4.11.1.2 Dose due to liquid effluents 1.3 REC 3/4.11.1.3 Dose projections for liquid 1.4 releases 4

COMANCHE PEAK - UNITS 1 AND 2 viii Rev. 8 1/93

Cross Reference to Technical SDecifications and REC Number or Document Section Recuirement ODCM 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 i greater than eight days )

l 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 and particulates with half-lives greater than eight days REC 3/4.11.2.4 Dose projections for gaseous 2.4 i releases REC 3/4.11.4 Total dose due to releases of 2.5 radioactivity and direct :

radiation ;

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 Description of the Interlaboratory 3.2 Comparison Program ,

REC 3.3.3.4 Radioactive liquid effluent ,

monitoring channels alarm / trip !

setpoints 1

l l' o liquid waste monitor (XRE-5253) 1.2.1 l o turbine building sump monitors 1.2.2 (IRE-5100 and 2RE-5100) o service water monitors 1.2.3 (1RE-4269/4270 and 2RE-4269/4270) i l

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Cross Reference to Technical Soecifications and REC t

Number or Document Section Recuirement ODCM Section REC 3.3.3.5 Radioactive gaseous effluent monitoring channels alarm / trip setpoints o noble gas release rate monitors 2.2.1 XRE-5570A and XRE-5570B (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 sempler flow rate monitor 2.2.3 X' T-5570A2/B2 Tech Specs 3.3.3.1 Raliation monitoring channels alarm / trip setpoint

. . . o Containment atmosphere gaseous 2.2.5 monitors (containment vent monitors) 1RE-5503 and 2RE-5503 Tech Specs 6.9.1.4 Assessment of radiation doses due 2.5 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 1

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 I j

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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 Nuclear Power Plants." NUREG-0133 (October 1978).

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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." TV Electric. Comanche Peak Steam Electric Station.

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

5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors. U.S. NRC 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 Guide 1.111. Rev. 1 (July 1977).

7. Meteorslogy and Atomic Energy: Edited by Slade. D. H.; U. S.

Department of Commerce (July 1968).

8. " 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 Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01). 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." USNRC Regulatory Guide 1.109 (March 1976).

12. Code of Federal Regulation. Title 10. Parts 20 and 50.

COMANCHE PEAK - UNITS 1 AND 2 xi Rev. 8 1/93 w

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i INTR 000CT!ON l The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of l the CPSES Technical Specifications. Part I of the DDCM 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 i Instrumentation and Sealed Source Leakage. Part II of the ODCM describes the methodology and parameters to be used in the calculation !

of offsite doses due to radioactive liquid and gaseous effluents and i in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. Part II of the ODCH also contains a list and graphical description of the specific sample 1 locations for the radiological environmental monitoring program.

Liquid and Gaseous Radwaste Treatment System configurations are shown l in Part II. Figures 1.1 and 2.1.

l The ODCM will be maintained at the plant for use as a reference guide l I and training document on accepted methodologies and calculations. I Changes in the calculation methods or parameters will be incorporated I I

into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. TU Electric initiated changes to the ODCM will be implemented in accordance with Section 6.14 of the Technical Specifications.

l The ODCM 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 l 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 :alculations can be optionally expanded to several levels of effort. The complexity of

, the dose calculations can be expanded by several levels of effort. !

l aiming toward a full calculation in accordance with Regulatory Guide 1.109. Future changes to the ODCM may be initiated to implement more complex calculations as systems become available and are validated that can reliably, economically and properly perform these more i 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.

COMANCHE PEAK - UNITS 1 AND 2 xii Rev. 8 1/93

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l PART I RADIOLOGICAL EFFLUENT CONTROLS '

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i SECTION 1.0 i

DEFINITIONS 1

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1.0 DEFINITVONS The defined terms of this section appear in capitalized type and are applicable throughout these Controls.

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 CHANNEL OPERATIONAL 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 channel 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 step 5 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 observatior.. 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 TEST 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.

CDMANCHE PEAK UNITS 1 AND 2 PART I 1-1 1/93

l DEFINITIONS i DOSE EOUIVALENT 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-132. I-133, 1-134, and I-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.

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

l MEMBER (S) 0F THE PUBLIC l

1.18 MEMBER (S) 0F THE PUBLIC means an individual in a CONTROLLED AREA or 8 UNRESTRICTED AREA. Individuals are not MEMBERS OF THE PUBLIC if they are employees of the licensee, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE TALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) 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 effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall 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, train, 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,

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electrical power, cooling or seal water, lubrication or other auxiliary !

equipment that are required for the system, subsystem, train, component, or I device to perform its function (s) are also capable of performing their related support function (s).

I REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 1-2 1/93 1

DEFINITIONS OPERATIONAL 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.

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

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.

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RATED THERMAL ~ POWER 1.29 RATED THERMAL POWER shall be a total reactor core heat transfer rate ;

to the reactor coolant of 3411 MWt. :

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

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

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

l COMANCHE PEAK UNITS 1 AND 2 PART I 1-3 1/93

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DEFINITf0NS

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l UNRESTRICTED AREA 1.41 An UNRESTRICTED AREA means any area beyond the SITE BOUNDARY. 8 j VENTING 1.42 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, i

concentration, or other operating condition, in such a manner that i replacement air or gas is not provided or required during VENTING. Vent, a

used in system names, does not imply a VENTING process.

WASTE GAS HOLDUP SYSTEM i 1 43 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed

, to reduce radioactive gaseous effluents by collecting Reactor Coolant l

System offgases from the Reactor Coolant System and providing for delay or i holdup for the purpose of reducing the total radioactivity prior to release ,

to the environment.

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1.44 A CONTROLLED AREA means an area outside of a restricted area, as 8 1 defined in 10 CFR 20.1003, but inside the SITE BOUNDARY, access to which l can be limited by the licensee for any reason. I; b

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REY. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 1-4 1/93

TABLE 1.1 FREOUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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.

1 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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TABLE 1.2 OPERATIONAL MODES 1

AVERAGE REACTIVITY % RATED COOLANT MJ E CONDITION. Keff THERMAL POWER

TEMPERATURE'

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

2. STARTUP 1 0.99 s 5% 1 3500F ,

j 3. HOT STANDBY < 0.99 0 1 3500F

4. HOT SHUTDOWN < 0.99 0 3500F>Tavg

> 2000F

! 5. COLD SHUTDOWN < 0.99 0 1 2000F

6. REFUELING ** 5 0.95 0 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. I 4

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i 3/4 CONTROLS AND SURVEILLANCE REOUIREMENTS 3/4.0 APPLICABILITY f CONTROLS 4

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. '

l 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, completion of the ACTION requirements is l i not required. j 3.0.3 When a Control is not met, except as provided in the associated i 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 i unit in a MODE in which the specification does not apply by placing it, as I 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 permit operation under the l ACTION requirements, the action may be taken in accordance 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 shutdown 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 operation of the facility for an l 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.

. # The associated basis from the CPSES Technical Specifications applies to this section. '

1 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-1 1/93

d APPLICABfLITY SURVEILLANCE REOUIREMENTS j 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES l or other conditions specified for individual Controls unless otherwise '

stated in an individual Surveillance Requirement, i i

4.0.2 Each Surveillance Requirement shall be performed within the 7 specified time interval with a maximum allowable extension not to exceed i 25% of the surveillance interval. Exceptions to these requirements are l 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.

)

The time limits of the ACTION requirements are applicable at the time it 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 l completion of the surveillance when the allowable outage time limits of the l ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do i not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall l 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.

1 J

CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-2 1/93

INSTRUMENTATION RADIDACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION CONTRDLS I 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 accordance with the j methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABIL ITY: At all times.

ACTION: 1

a. With a radioactive liquid effluent monitoring instrumentation !

channel Alarm / Trip Setpoint less conservative than required by l 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 Re.dioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a 1 timely manner.

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

] SURVEILLANCE REOUIREMENTS 1

4.3.3.4 Eacn radioactive liquid effluent monitoring instrumentation channel I shall be demonstrated OPERABLE by perfornance of the CHANNEL CHECK, SOURCE LHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG l CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-3.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-3 1/93

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

1 TABLE 3.3-7 RADI0 ACTIVE LIQUID EFFLUE(.f 1NITORING INSTRUMENTATJ.QM 8

MINIMUM

,E g CHANNELS OPERABLE ACTION

$ INSTRUMENT y 1. Radioactivity Monitors Providing Alarm and

^ Automatic Termination of Release e

E a. Liquid Radwaste Effluent Line (XRE-5253) 1 30 Q

" 1/ sump

b. Turbine Building (Floor Drains) Susps Effluent Lines 31 (IRE-5100 & 2RE-5100) l8 e

o 2. Radioactivity Monitors Providing Alers But Not Providing N

Automatic Termination of Release

a. Service Water System Effluent Lines 1/ train 32 (1RE-4269, 1RE-4270 & 2RE-4269. 2RE-4270) m m

l8

~4

3. Flow Rate Measurement Devices R a. Liquid Radwaste Effluent Line (XFT-5288) 1 33 u

a a a<

W OB

.- - . . _ . - _ . - - .~. _.- - - __ -.._..--....- . ___ ____ _ ___ __ __-_____ _ _ _ - - -_

TABLE 3.3-7 (Continued) 1 ACTION STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent re~ eases via this pathway mey continue provided that prior to 1.11tiating a release:

a. At least two independent samples are analyzed in accordance 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 discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

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 l

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 I microcurie / gram DOSE EQUIVALENT I-131. (Refer to Notation 3 8 :

of Table 4.11-1 for the applicability of the LLD l 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 1RE- l 4510, & 1RE-4511) OPERABLE and indicating an activity of less !

than 1X10-4 microcurie /m1, a grab sample is collected and (

analyzed for radioactivity at a lower limit of detection of ;

1 no more than 10-7 microcurie /ml 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 j analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10 ' microcurie /m1. (Refer to Notation 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 curvet generated in place may be used to estimate flow.

REV. 8 1

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-5 1/93

TABLE 4.3-3 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS n

E ANALOG DIGITAL E CHANNEL CHANNEL 9 CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL

[ INSTRUMENT CHECK CHECK CAllBRATION TEST TEST

, 1. Radioactivity Monitors Providing Alarm and i Automatic Termination of Release E

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

b. Turbine Building (Floor Drains) Sumps Effluent Lines (1RE-5100 & 2RE-5100) R(4) N.A. 0(2) g D H l8 N 2. Radioactivity Monitors Providing Alare But Not Providing Automatic Termination of Release y a. Service Water System Effluent Lines (IRE-4269. 1RE-4270. 2RE-4269 & 2RE-4270) R(4) N.A. 0(3)

D M l8

~

3. Flow Rate Measurement Devices M

P a. Liquid Radwaste Effluent Line m (XFT-5288) D(5) N.A. R 0 N.A.

TABLE 4.3-3 (Continued)

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

b. Circuit failure (Channel Out of Service - Loss of Power, Loss of 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 Low Volume Waste Treatment System to the Co-Current Waste Treatment System) and Control Room alarm annunciation occur if any of the following conditions exist:

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

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

(4) The initial CHANNEL CALIBRATION shall be performed using one or more of 8 the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards iat have been obtained from suppliers that participate in measurenent assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For 8 subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.

(5) CHANNEL CHECK shall consist of verifying indication of flow during 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, periodic, or batch releases are made.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-7 01/93

INSTRUMENTATf0N l

RADI0 ACTIVE GASEDUS 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 / Trip 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 J methodology and parameters in Part II of the ODCM.

APPLICABILITY: As shown in Table 3.3-8 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channe Alarm / Trip Setpoint less conservative than required by

, the above Control, immediately suspend the release of radioactive gaseous 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 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 REOUIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE 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 4.3-4.

l J

I a

l REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-8 1/93

'1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . - . - -,--..mm, , _ ~ . - , , ~ , . . -,...,_.,,yy . , , . _ - -

TABLE 3.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION n

EE MINIMUM CHANNELS INSTRUMENT OPERA 8LE APPLICABILITY ACTION

[ 1. WASTE GAS HOLDUP SYSTEM n, i N a. Noble Gas Release Rate

Monitor - Providing Alarm g and Automatic Termination

, :q of Release v) [XRE-5570A & XRE-55708 (effluent release rate channel)] 1/ stack ** 34 E

C3 2. PRIMARY PLANT VENTILATION

. ~

a. Noble Gas Release Rate Monitor

[XRE-5570A & XRE-55708

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

36 E

-4 b. Iodine Sampler (WRGM sample skid) 1/ stack

37 M

P c. Particulate Sampler 1/ stack

37

") (WRGH sample skid)

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

35 4 X-RFT-55708-1) 4 B

(s3

. _ - ____.________.__.__.__________.m_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ , . . _ _ _ . _ _ _ _ _ _ _ _ . . ~ . . _ - -u. - . . , , - . . . _ . . - . . , . , , , , , , , . . , , , _ _ . _..._e.,

, _ , . . . , , , , ,.,r.,,

l !

. I

! TABLE 3.3-8 (Continued) '

l

, TABLE NOTATIONS l

!

At all times.

** Du-ing Batch Radioactive Releases via this pathway. i

! i

! ACTION 34- With the number of channels OPERABLE less than required by the i 1 Minimum Channels OPERABLE requirement, the contents of the !

i tank (s) may be released to the environment provided that prior t to initiating the release: ;

, a. The auxiliary building vent duct monitor (XRE-5701) is l j confirmed OPERABLE, or.

l 1 ;

I b. At least two independent samples of the tank's contents i

are analyzed, and i

c. At least two technically qualified members of the !

, facility staff independently verify the release rate i i

calculations and discharge valve lineup.

i Otherwise, suspend release of radioactive effluents via this i 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 .

4 ACTION 36- With the number of channels OPERABLE 1ess than required by the i Minimum Channels OPERABLE requirement, effluent releases via l this pathway may continue provided that:

(a) A Plant Vent Noble Gas Activity Monitor (XRE-5570A, XRE-5570B(lowrangeactivity)orXRE-5567A,XRE-5567B) 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 N (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 4

(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 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 i 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 may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-10 1/93

TABLE 4.3-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS n

gj ANALOG DIGITAL g CHANNEL CHANNEL

[2 CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL

) "' INSTRUMENT CHECK CHECK CALIBRATION TEST TEST A

k' 1. WASTE GAS HOLDUP SYSTEM h a. Noble Gas Release Rate Monitor -

. $5 Providing Alarm and Automatic gj Termination of Release

_, [XRE-5570A, XRE-5570B(effluent release 3, rate channel)] P P R(3) N.A. 0(1) 5 n, 2. PRIMARY PLANT VENTILATION

a. Noble Gas Release Rate Monitor

[XRE-5570A, XRE-5570B(effluent release R rate channel)] D # R(3) N.A. Q(2)

, N

-, b. Iodine Sampler u, (WRGM sample skid) W(4) N.A. N.A. N.A. N.A.

D L '

c. Particulate Sampler

(WRGM Sample Skid) W(4) N.A. N.A. N.A. N.A.

d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1 D N.A. R 0 N.A. 4 4 X-RFT-55708 1) 4 a

1

. "i

TABLE a.3-4 (Continued)

TABLE NOTATIONS i Prior to any release from the WASTE GAS HOLDUP SYSTEM or containment PURGING 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 i occurs if any of the following condition exists: ,

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

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

I I

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

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 Flow, or Check Source Failure).

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of 8

the refere'nce standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For 8 subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST 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 sampling.

l l

l REV. 8 l

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-12 1/93

INSTRUMENTATTON METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in 8 Table 3.3-9 shall be OPERABLE. '

l APPLICABILI'_;. 4I all times.

l ACTION:

1

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 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 REOUIREMENTS 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 l

b. At least once per 184 days by performance of a CHANNEL CALIBRATION.

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-13 1/93

TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUMENTATION

, MINIMUM l

INSTRUMENT LOCATION OPERABLE

1. WIND SPEED 1 of 3 1

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

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

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

I .

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.

l

Mounted on backup tower.

i COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-14 01/93 I )

VNSTRUMENTATf0N SEALED SOURCE CONTAMINATION CONTROLS 4

3.7.15 Each sealed source containing radioactive material either in :

excess of 100 microCuries of beta and/or gamma emitting material l or 5 microcuries of alpha emitting material shall be free of l greater than or equal to 0.005 microcurie of removable '

contamination.

APPLICABILITY: At all times.

ACTION

With a sealed source having removable contamination in excess of the above )

i 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. l l

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

a. The licensee, or i

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

Agreement State.

l The test method shall have a detection sensitivity of at least i 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 sources containing radioactive materials:

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

and

2) In any form other than gas.

i 1

I COMANCHE PEAK UNITS 1 AND 2 P ART I 3/4-15 1/93 4

SURVEILLANCE REOUIREMENTS (Continued) ;

b. Stored sources not in usa - 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

c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested 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 i detector leakage tests reveal the presence of greater than or '

equal to 0.005 microcurie of removable contamination.

l j

l l

l CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-16 1/93 l

- - - - .=

3/4.11 RADIDACTIVE EFFLUENTS j 3/4.11.1 LIOUID EFFLUENTS

, CONCENTRATION CDNTROLS 3.11.1.1 In accordance with CPSES TS 6.8.3.e.2 and 3, the concentration of 8 radioactive material released in liquid effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 2 Column 2 for radionuclides otner 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 8 effluents to CONTROLLED AREAS and UNRESTRICTED AREAS exceeding the above limits, 'mmediately restore the concentration to within the above limits.

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

, SURVEILLANCE REOUIREMENTS l

4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according 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 methodology and parameters in Part II of the ODCM to assure that the concentrations at the point of release are maintained j within the limits of Control 3.11.1.1. '

4 i

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-17 1/93

TABLE 4.11-1 R dio:Cttve Uquid Waste Sampling and Analysis PrDgram UQUID RELEASE SAMPUNG MINIMlUM TYPE OF ACTMTY LOWER UMIT OF I

TYPE FREQUENCY ANALYSIS ANALYS!S DETECTIC' (1)

FREQUENCY (pCVmi) 1 A. Batch Weste Release (2) P P Principal Gamma 5.0E-07 Tanks to the Circulating Each Batch Each Batch Emeters (3)

Water Discharge L131 1.0E-06

a. Waste Monnor Tanks Dissolved & Entrained (3) 1.0E-05

b. Laundry Holdup I "*** * I

& Monner Tanks M H-3 1.0E-05

c. Waste Water Compostte (4)

Holoup Tanks (8) . Gross MpM 1.0E-07 7A

d. Plant Emuent O Sr-89, Sr-90 5.0E-06 Tanks Composte (4)

Fe 55 1.0E-06 7

18. Batch Waste Release (2) P P Principal Gamma 5.0E-07 Tanks to the LVW Pond Each Batch Each Batch Emtters (3)

a. Condenaste Polisher Backwash

, Recovery Tanks (6.7) l ._ L131 1.0E-06 i b. Component Cooling Water Drain l

Tanks (7)

c. Waste Water H-3 1.0E-05 Holdup Tanks (6.8) l 2A. Continuous Release (5) Deity Grab Compoelte Principal Gamma 5.0E-07 to the Circulating Sample (9) over pond Emitters (3)

Water Discharge discharge period (4) b131 1.0E-06 l a. Low Volume Weste Pond Emuents Diseotved & Entrained (3) 1.0E-05 8

Gases (Gamma Emitters) 7 l

H-3 1.0E-05 Groes Alpha 1.0E-07 O Sr-89. St-90 5.0E-08 ,

Composte (4) !

Fe-55 1.0E-06 j

28. Continuous Releases (5) W W Principal Gamma 5.0E-07 )

to the LVW Pond Grab Sample Emeters (3) l

a. Turbine Bidg. Sump !

No. 2 Emuents (6,7) b131 1.0E-06

a. Turbine Bldg. Sump ,

No. 4 Effluents (6,7) H-3 1.0E-05 ;

COMANCHE PEAK - UNIT 1 AND 2 1 3/4-18 REV. 8 01/93 !

l

I I

TABLE 4.11-1 (Continuedl 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 blank observation represents a "real" signal.

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

4.66 sb LLD =

E-V 2.22 x 100 Y exp (-Aat)

Where:

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

sh = the standard deviation of the background counting rate or ;

of the counting rate of a blank sample as appropriate (counts l per minute).

Em 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, i 1

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 g oriori (before the fact) limit representing the capability of a measurement system and not as an g nosteriori (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 II of the ODCM to assure representative sampling.

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-19 b8 01/93

TABLE 4.11-1 (Continued)

TABLE NOTATIONS

(3) The principal gamma emmiters for which the LLO specification applies 8 include the following radionuclides: Mn-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 LLD of 5 x 10-6 This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with i those of the above nuclides, 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 Guide 1.21, Appendix B.

Revision 1, June 1974 J

(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 waste streams shall be sampled and analyzed, in accordance with 8 this table, if radioactive material is detected in the LVW Pond composite samples in concentrations that exceed 10% of the limits of 10 CFR 20,-Appendix B. Table 2. Column 2. This sampling shall 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 2. Column 2.

(7) All flow from these waste streams shall be diverted to the Waste Water 8 Holdup Tanks if activity is present in the waste stream in concentrations that exceed the limits of 10 CFR 20. Appendix B, Table

2. Column 2. Sampling and analysis of the respective Tanks or sumps 1 are not required when flow is diverted to the Waste Water Holdup Tanks. 7 1

(8) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the B Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed the limits of 10 CFR 20, Appendix 8. Table 2. Column 2. Otherwise, WWHTs may be discharged to the Low Volume Waste Pond. WWHT discharges to the Circulating 7 Water Discharge Tunnel shall be sampled and analyzed per Item 1A.c of 4

this table. WWHT discharges to the LVW Pond shall be sampled and analyzed per Item 18.c of this 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 occurring. To be representative of the liquid effluent, the sample i

volume shall be proportioned to the effluent stream discharge volume.

The ratio of sample volume to effluent discharge volume shall be ;

maintained constant for all samples taken for the composite sample.

i REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-20 01/93 i

l l

RADf0ACTfVE EFFLUENTS l

QQlE CONTROLS 3.11.1.2 In accordance with CPSES TS 6.8.3.e.4 and 6.8.3.e.5 the dose or 8 dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to CONTROLLED AREAS and 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.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to tne 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 II of the ODCM J at least once per 31 days. i i

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-21 1/93

i i 1 i

1 RADf0 ACTIVE EFFLUENTS l

! i

. LIOUID RADWASTE TREATMENT SYSTEM l l

1 CONTROLS )

l I 3.11.1.3 In accordance with CPSES TS 6.8.3.e.6, the Liquid Radwaste 8

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 CONTROLLED AREAS and 1

, UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole j body or 0.2 mrem to any organ in a 31-day period.

4 APPLICABILITY: At all times.

i ACTION:

! a. With tcdioactive liquid waste being discharged without treatment i and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit ;

i to the Commission within 30 days, pursuant to Specification '

6.9.2, a 5pecial Report ' hat includes the following information: ;

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

or subsystems, and the reason for the inoperability, i a i

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

OPERABLE status, and l

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.

l SURVEILLANCE REOUIREMENTS 4

] 4.11.1.3.1 Doses due to liquid releases from each unit to CONTROLLED AREAS 8 and UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when

Liquid Radwaste Treatment Systems are not being fully utilized.

i 4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be 1 ;

l considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. l REY. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22 1/93

i RADI0 ACTIVE EFFLUENTS l l

i LVW POND RESIN INVENTORY 7 CONTROL S ,

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 :

264 . E . < 1. 0 J J l

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

l where: 7 Aj = pond inventory limit for single radionuclide "j" (Curies), 7 Cj = 10 CFR 20, Appendix B. Table 2, Column 2, concentration for 8 ;

single radionuclide "j" (microCuries/ml),

V= volume'of resins in the pond (gallons), and 7 ;

1 264 = unit conversion factor (microCuries/ Curie per 7 !

milliliter / gallon). I APPLICABILITY:, At all times. 2 ACTION:

i

a. With the quantity of radioactive material contained in resins 8 in the LVW Pond exceeding the above limit, immediately suspend all additions of resins to the pond.

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

1 SURVEILLANCE REOUIREMENTS 1

l 4.11.1.4 Prior to transferring any batch of used powdex resin to the pond, 8 the total inventory of radioactive materials in resins contained in the l pond, including the batch to be transferred, shall be determined to be within the above limit. The inventory shall be determined based on !

analysis of a representative sample of the resin batch. Decay of radionuclides k previously discharged resins may be taken into account in determining inventory levels.

t 1

1 REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22a 1/93

l RADI0 ACTIVE EFFLUENTS LW POND RESIN INVENTORY 7 SURVEILLANCE REOUIREMENTS (Continued)

Additionally, each batch of resins transferred to the pond shall be limited 8 l by the expression:

8 j C3 - 0.1 I 0 <

l 0

1 Where: Qj = Concentration of radioactive materials (microCuries/ml) 8 <

j in wet, drained slurry (used powdex resin) for l l radionuclide "j", excluding tritium,-dissolved or !

entrained noble gases, and radionuclides with less than j an B-day half-> life. The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-60. 7 Estimates of the Sr-89 and Sr-90 batch concentration ;

shall be included based on the most recent quarterly !

composite analysis, Cj = 10 CFR 20, Appendix B. Table 2. Column 2, concentration 8 for single radionuclide "j" (microCuries/ milliliter).

)

i i

1 I

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-22b Rev. 8 ERRATA (6/93)

RADIQACTfVE EFFLUENTS ;

3/4.11.2 GASEOUS EFriUENTS ]

DOSE RATE l 3.11.2.1 In accordance with CPSES TS 6.8.3.e.3 and 6.8.3.e.7, the dose !

l rate due to radioactive materials released in gaseous effluents from the l

site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be j l limited to the following: l

a. For noble gases: Less than or equal to 500 mrems/yr to the wht 3 body and less than or equal to 3000 mrems/yr to the skin, l ano 1

b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mres/yr to any organ. j 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 B according 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 SITE BOUNDARY are maintained within the limits of Control 3.11.2.1.

i REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-23 1/93

O E

$ TABl,E 4.11-2 5 Radioactive Gaseous Waste Semp11ng and Analysis Program (*)

y 7e e MINIMUM LOWER LIMIT OF c- SAMPLING ANALYSIS TYPE OF DETECTION (LLD)(1)

$ GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pC1/ml) m

" 1. Weste Gas Storage P P Tank Each Tank Each Tank Principal Gamma Enitters(2) lx10 E Grab Sample C 2. Containment Purge P P N or Vent Each Release (3) Each Release (3) Principal Gamuna Emitters (2) lx10

-6 M H-3 (oxide) lx10

3. Plant Vent M(3), (4). (5) Principal Causma Emitters (2) lx10-c

> ~b

$ Grab Sample M(3) H-3 (oxide) 1x10

Continuous (6) W(7) 1-131 lx10

~I

, %s Radiolodine 7 Adoorber Continuoue(6) W(7) Principal Gaimma Emitters (2) lx10

~'

Particulate Sample Continuous (6) M Gross Alpha lx10" '

Composite Per-ticulate Sample Continuous (6) Q Sr-89, Sr-90 lx10'II Composite Par-ticulate Sample ;

O, g Continuous (6)

Noble Ga s **

Bet a or Gama Noble Cas lx10 lI (a3

Table notations next page

- This sample is continuously analyzed by a radiation monitor l1 ,

TABLE 4.11-2 (Continued 1 l

TABLE NOTATIONS l

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

For a particular measurement system, which may include radiochemical ,

separation:

4.66 s b I LLD =

l E . y . 2.22 x 10 6 . y . exp (-AAt) ;

l Where-l LLD = the "a priori" lower limit of detection (microcurie per '

unit mass or volume),

S b = the standard devi ablanksampeksappropriate rate or ofthecountingrateoftionoftheblckroundcounting(counts j per minute),

l E'=~ the counting efficiency (counts per disintegration),

f 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

.it= the clapsed 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.

1 It should be recognized that the LLD is defined as an a criori 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.

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-25 01/93

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(2) The principal gasum 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 Co-60, Zn-65, I-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 nuclides, 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 Guide 1.21, Appendix 8. Revision 1 June 1974.

(3) Sampling and analysis shall also be performed following shutdown,

startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. This requirement does not apply if: (1) 8 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) noble gas monitoring shows that effluent activity has not increased 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)Tritiumirabsamplesshallbetakenatleastonceper7daysfromthe ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with 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-hour 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) 8 analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor cocitnt has not increased more than a factor of 3; and (2) noble gas monitoring shows that effluent activity has not increased more than a factor of 3.

t REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-26 01/93

RAD 10 ACTIVE 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: '

a. 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 gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION

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 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 REOUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter 8 and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Part II of the 00CM at least once per 31 days.

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-27 1/93

RADf0ACTfVE EFFLUENTS DOSE - 10 DINE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM 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.

3PPLICABILITY: At all times.

l ACTION:

a. With the calculated dose from the release of Iodine-131 Iodine- 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 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the l corrective actions that have to be taken to assure that I subsequent releases will be in compliance with the above limits. l l

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

SURVEILLANCE REOUIREMENTS 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.

l l

l i

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-28 1/93

RADf0 ACTIVE 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, to 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 Lata radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. l APPLICABILITY: At all times. l

}

ACTION:

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

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

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

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

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

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 00CM when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed PRIMARY PLANT VENTILATION 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.

l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-29 1/93

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

i

! RADI0 ACTIVE EFFLUEMTS j TOTAL DOSE i

CONTROLS l

i l 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 I radioactivity and to radiation from uranium fuel cycle sources shall be I 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.

l APPLICABILITY: At all times.

1 I i ACTION: I l l With the calculated doses from thc release of radioactive l a.

I materials in liquid or gaseous effluents exceeding twice the

! limits of Controls 3.11.1.2a., 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, j

3.11.2.3a., or 3.11.2.3b., calculations shall be made including !

direct radiation contributions from the units and from outside i

! storage tanks to determine whether the above limits of Control l j 3.11.4 have been exceeded. If such is the case, prepare and 8 1 submit to the NRC within 30 days, pursuant to Specification :

1 6.9.2, a Special Report that defines the corrective action to be l i taken to reduce subsequent releases to prevent recurrence of i j exceeding the above limits and includes the schedule for ;

j achieving conformance with the above limits. This Special 8 l 1 Report, as defined in 10 CFR 20.2203(a)(4) and 20.2203(b), shall '

include an analysis that estimates the radiation exposure (dose) i to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, '

including all effluent pathways and direct radiation, for the i calendar year that includes the release (s) covered by this ;

j report. It shall also describe levels of radiation and j j concentration of radioactive material involved, and the cause of i the exposure levels or concentrations. If the estimated dose (s)

{ exceeds the above limits, and if the release condition resulting l in violation of 40 CFR Part 190 has not already been corrected, j the Special Report shall include a request for a variance 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.

l b. lne provisions of Controls 3.0.3 and 3.0.4 are not applicable. l l

SURVEILLANCE REOUIREMENTS l

! 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents 8 i shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and i 4.11.2.3, and in accordance witn the methodology and parameters in Part II

of the ODCM.

I l

4 l

COMANCHE oEAK UNITS 1 AND 2 PART I 3/4-30 :

i i A

{

l RAD 10 ACTIVE EFFLUENTS (Continued) i

! 3/4.11.4 TOTAL DOSE i l

SURVEILLANCE REOUIREMENTS 4.11.4.2 Cumulative dose contributions from direct radiation from the 8 i units and from radwaste storage tanks shall be determined in accordance !

with the methodology and parameters in Part II of the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4. l l

r l

i l

l l

l REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-31 1/93

.- -. - - - . _ . , . . _- _ _ _ _ _ _ .__ _ _ _,. .. ___ . _ _ _ _a

i l 3/4.12 RADIOLOGICAL ENVfRONMENTAL MONITORING j 3/4.12.1 MONITORING PROGRAM l I

i 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 j the Commission, in the Annual Radiological Environmental 4

Operating Report required by Control 6.9.1.3, a description of the reason (s) for not conducting the program as required and the plan 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 ine reporting levels of Table 3.12-2 when averaged l over any calendar quarter, prepare and submit to the NRC l within 30 days, pursuant to Specification 6.9.2, a Special j 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 j

$ MEMBER OF THE PUBLIC is less than the calendar year limits of i Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than one of i 2

the radionuclides in Table 3.12-2 are detected in the sampling l medium, this report shall be submitted if: l 3 concentration (1) . concentration (2)

reporting level (1) reporting level (2) ...> 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. i 3 This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in i

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.

l 1

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-32 1/93

RADf0LOGTCAL ENVIRONMENTAL MONITORING CONTROLS ACTION (Continued)

c. With milk or fresh leafy vegetable samples 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 ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Control 6.14, submit as a part of or concurrent with the Semiannual Radioactive Effluent l

Release Report, a complete, legible copy of-the entire ODCM, including a revised figure (s) and table for the ODCM reflecting the new location (s).

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

SURVEILLANCE REOUIREMENTS 4.12.1 The radiological environmental monitoring 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 ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

j i

i i

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-33 1/93 f

_ _-__. _ - - - _ , . , _ . . - - . _ , . . , , . __ , m,. , , . , , . _

TABLE 3.12-1 Radiological Environmental Monitoring Program o

y NUMBER OF is REPRESENTATIVE Ri EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY y AND/0R SAMPLE SAMPLE LOCATIONS (I) COLLECTION FREQUENCY OF ANALYSIS i

92

~ 0uarterly.

1. Direct Radiation (2) Forty routine monitoring stations Gamma dose quarterly either with two or more dosimeters EE or with one instrument for measur-

1 ing and recording dose rate continuously, placed as follows:

[]

$? 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 m each meteorological sector in 4

the 6- to 8-km range from the h site: and 10 The balance of the stations to be f placed in special interest areas SE 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 Radioiodine Cannister:

Particulates operation with sample I-131 analysis weekly

!! collection weekly, 15 Three samples from close to or more frequently 68 the three SITE BOUNDARY if required by dust Particulate Samoler:

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) or composite (by location quarterly.

1

TABLE 3.12-1 (Continued) e, Radiological Environmental Monitoring Program O

y NUMBER OF

[]

REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY

?' AND/OR SAMPLE SAMPLE LOCATIONS (1) . COLLECTION FREQUENCY OF ANALYSIS R '

, One sample from the c: vicinity of a community 25 having the highest calcu-G1 lated annual average ground-

_. level D/Q: and h! One sample from a control n3 location, as for example 15 to 30 km distant and in the least prevalent wind direction. (3)

}

-4

3. Waterborne

-. a. Surface Squaw Creek Reservoir (6) Monthly composite of Gamma isotopic anal-u, weekly grab samples. ysis(5) monthly.

ls Composite for tritium la v, analysis quarterly.

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

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

from SCR. Otherwise, monthly grab sample.(7) o 0 Control-Brazos River Monthly Gamma isotopic anal-ll upstream of Lake Granbury ysis(5) monthly.

Composite for tritium analysis quarterly.

b. Ground Samples from two sources Quarterly Gamma isotopic (S) if likely to be affected(8) . and tritium analysis quarterly.

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

ce

. . 'LA a L. .A. .4--. a; -- 1 -. c 4 - - -hi4h am. ,c= - >_u--.- - - it -_ L-h*2mmws 4 6w+i_i TABLE 3.12-1 (Continued) c, Radiological Environmental Monitoring Program S

E NUMBER OF 9

REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY

?? AND/0R SAMPLE SAMPLE LOCATIONS (l) .i COLLECTION FREQUENCY OF ANALYSIS N

. 3. Waterborne (Continued)

! c. Drinking One sample from Squaw Creek Composite of weekly I-131 analysis of Di Reservoir. grab samples over each composite sample 2-week period when

_. when the dose calcu-3 I-131 analysis is lated for the con-

@5 performed: monthly sumption of the water no composite of weekly is greater than 1 mrem grab samples other- per year (9) . Gross wise. beta and gamma iso-topic analyses (5)

$ monthly. Composite

$ for tritium analysis

-- quarterly.

w 3s d. Sediment One sample from downstream area Semiannually. Gamma isotopic analy-Es 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 dose pasture; monthly semimonthly when potential. If there are none. at other times, animals are on pas- ,

sample from milking animals in ture; monthly at 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 lo from milking animals at a control 20 location. 15 to 30 km distant and ll in the least direction.(3) prevalent wind

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

g NUMBER OF g REPRESENTATIVE

"' EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY A AND/0R SAMPLE SAMPLE LOCATIONS (I) ,, COLLECTION FREQUENCY OF ANALYSIS R

, 4. Ingestion (Continued) k b. Fish and One sample of at least two Sample semiannually. Gamma isotopic d Invertebrates recreationally important species analysis (5) on m in vicinity of plant discharge area. edible portions.

h One sample of same species in areas ce 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 s that is irrigated by water in which edible portion.

4

$ liquid plant wastes have been

,_. discharged.

1 w 1 A sample of broad leaf vegetation Monthly, when Gamma isotopic (5)

L, grown 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.

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

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

Reports from 3 additional airborne radiolodine sample locations may be supplemented for broad leaf vegetation samples.

i

i I

i 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 ODCM. 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 i 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 l 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 provide 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 M bw for radon and thoron daughter decay. If gross beta activity in a k particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

I 1

Rev 8 ,

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-38 01/93

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

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

l (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 this 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 00CM. l

.- j (10) If harvest occurs more than once a year, sampling shall be performed l during each discrete harvest. If harvest occurs continuously, l sampling shall be monthly. Attention shall be paid to including ,

samples of tuberous and root food products. '

l 1

i l

REV. 8 COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-39 1/93 l

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COMANCHE PEAK - UNITS 1 AND 2 PART I 3/4-41 01/93

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i l TABLE 4.12-1 (Continued) i TABLE NOTATIONS l

4

(1) The list does not mean that only these nuclides are to be considered.

! Other peaks that are identifiable, together with those of the above '

i nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

l (2) Required detection capabilities for thermoluminescent dosimeters used

for environmental measurements shall be in accordance with the.

recommendations of Regulatory Guide 4.13.

i (3) The 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 1 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 L Where

' LLD = thi~"a priori" lower limit of detection (picocurie per unit mass !

or volume), "

i S = the standard deviation of the backaround countino rate or of the h i ccunting rate of a blank sample as appfopriate (counts per minute), '

E = the counting efficiency (counts per disintegration), ,

] r j V=thesamplesize(unitsofmassorvolume),

2.22 = the number of disintegrations per minute per picocurie, j Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide

] (sec-1),and a

At = the elapsed time between the midpoint of sample collection and the time of counting (s).

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

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-42 1/93 l

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TABLE 4.12-1 (Continued)

TABLE NOTATIONS (Continued)

(3) Continued It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a measurement system and not as an g oosteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD'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.

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-43 1/93 J

,, --v-- -c-- , , - - , , - - m. - - .,v,-

i RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 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

of greater than 50 m2 (500 ft2 ) producing broad leaf vegetation.

l APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location (s) that yields a i calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, pursuant to l Control 6.9.1.4, identify the new location (s) in the next l 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 exoosure 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 Eqvironmental Monitoring Program given in Part II of the ODCH.

I The sampling locations having the lowest calculated dose or dose connitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the I year in which this Land Use Census was conducted. Pursuant to I l 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 ODCM 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 REOUIREMENTS l 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 i results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

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

COMANCHE PEAK UNITS 1 AND 2 PART I 3/4-44 1/93

RADIOLOGTCAL 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 i on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1. ;

APPLICABILITY: At all times.

ACTION:

I

a. With analyses not being performed as required above, report the L corrective actions taken to prevent a recurrence to the l 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. i SURVEILLANCE REOUIREMENTS l

4.12.3 The Interlaboratory Comparison Program shall be described in Part 8

II of the ODCH. 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.

l 1

REV. 8 CDMANCHE PEAK UNITS 1 AND 2 PART I 3/4-45 1/93

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l COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-0 01/93 1

1 i

i

INSTRUMENTATION BASES 3/4.3.3.4 RADIQACTIVE 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 ODCM 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 64 of Appendix A to 10CFR 50.

3/4.3.3.5 RADIOACTIVE GASEOUS 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.

i The Alarm / Trip Setpoints for these instruments shall be calculated and 8 adjusted in acccrdance with the methocology and parameters in Part II of the ODCM to ensure that the alarm / trip will occur prior to exceeding the dose rate limits of Control 3.11.2.1. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design 4

Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.6 METEORDLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures tnat 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.

e REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-1 01/93

_ - ~ _ .

! INSTRUMENTATf0N j BASES ;

l i 3/4.7.15 SEALED SOURCE CONTAMINATION !

The limitations on removable contamination for sources requiring leak !

testing, including alpha emitters, are based on 10CFR70.39(c) limits for j 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 i j to a source in that group. Those sources which are frequently handled are l required to be tested more often than those which are not. Sealed sources

! which are continuously enclosed within a shielded mechanism (i.e., sealed

, sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from i

the shielded mechanism.

i 1 i i 1 l

i l .-

I i

i a

1 4

4 1

Y CDMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-2 01/93

3/4.11 RADf0 ACTIVE EFFLUENTS BASES i

3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS This control is provided to ensure that the concentration of 8 4 radioactive materials released in liquid waste effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in CONTROLLED AREAS and 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 20.1301(a) and (b) to individual MEMBERS OF THE PUBLIC. 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) Publication 2.

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

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

(LLDs). Detailed discussion of the LLD and other detection limits can be '

found in Currie, L.A., " Lower Limit of Detection Definition and Elaboration i i

of a Proposed Position for Radiological Effluent and Environmental Measurements." NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual. HASL-300. l 3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections 4

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 8 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

Also, for fresh utter sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose 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 Appendix I be shown by '

calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part II of 8 the the ODCM for calculating the doses due to the actual release rates of 4

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-3 01/93

RAD 10 ACTIVE EFFLUENTS BASES QQE (Continued) radioactive 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 1," 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.

l 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 1 ,

and Unit 2. '

3/4.11.1.3 LIOUID RADWASTE 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 CFR 50.36a, General Design Criterion.60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the 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 liquio 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. 8 3/4.11.1.4 LVW POND RESIN INVENTORY The inventory limits of the LVW Pond are based on limiting the 8 consequences of an uncontrolled release of the pond resin inventory. The expression in Control 3.11.1.4 assumes the pond inventory is uniformly mixed, and that the pond is located in a CONTROLLED AREA as defined in 10 CFR Part 20, an+ that the concentration limit in Note 4 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 Effluent Concentration Limits specified in 10 CFR 20, Appendix B. Table 2, Column 2. Because Control 3.11.1.1 limits the concentration of liquid effluents from other pathways to the LVW Pond to the 10 CFR 20 Effluent Concentration values, also limiting the average concentration in resins to the Effluent Concentration values will assure that the average concentration in the pond from all sources, calculated over the total volume of the pond (liquid and resins), will not exceed the 10 CFR 20 Effluent Concentration values.

REY. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-4 01/93

I RADI0 ACTIVE EFFLUENTS l

BASES (Continued) 3 /a .11.1. 4 LVW POND RESIN INVENTORY (Continued) l7 The batch limits for resins transferred to the LVW Pond assure tnat 8 radicactive 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 8 transferred to the Pond unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than 10%

of the limits established in 10 CFR 20, Appendix B.

The catch limit is arbitrarily established at 10% of the 10 CFR 20, 8 Appendix B limits to minimize input of radioactive materials to the LVW Pond consistent with detection limits for the resin analysis. The batch limit also provides assurance that the radioactive material released is within the inventory limitation of Control 3.11.1.4.

I i 1

l COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-5 Rev. 8 ERRATA (6/93)

l RADfGACTIVE EFFLUENTS j BASES i

l 3/4.11.2 GASEQUS EFFLUENT $

a j 3/4.11.2.1 DOSE RATE

! This control, in conjunction with Controls 3.11.2.2 and 3.11.2.3, is 8 provided to ensure that the dose 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 CONTROLLED AREAS and UNRESTRICTED AREAS. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEPEER OF THE PUBLIC at or i beyond the SITE BOUNDARY to less than or equal to 500 mress/ year to the l whole body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid i dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year. Because these dose rate limits are 8 applied on an instantaneous basis and because of the overriding 10 CFR 50, Appendix I, cummulative dose limitations, established in Control 3.11.2.2

and 3.11.2.3, 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 a CONTROLLED AREA or an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations that

, would result in extceding the annual total effective dose equivalent limit 4 specified in 1.0 CFR 20.1301. . For MEMBERS OF THE PUBLIC who may at times

be in CONTROLLED AREAS within the SITE BOUNDARY, the occupancy factors for 1

those MEMBERS OF THE PUBLIC will usually be sufficiently low to compensate 4

for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The methodology for calculating doses for such MEMBERS OF

THE PUBLIC is provided in PART II of the 00CM.

3

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

l The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection j (LLDs). Detailed discussion of the LLDs and other detection limits caa be 4

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 4 Manual, HASL-300 J

l 4

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i l REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-6 01/93 1

I RADf0ACTfVE EFFLUENTS i

l BASES l

3/4.11.2.2 DOSE - NOBLE GASES l

This control is provided to implement the requirements of Sections l II.B III.A and IV.A of 10CFR50, Appendix I. The control implements the guides set forth in Section I.B of Appendix I. The ACTION statements 8 l provide the required operating flexibility and at the same time implement I

the guides set forth in Section IV.A of Appendix I to assure that the ,

releases of radioactive material in gaseous effluents to CONTROLLED AREAS I and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by I calculational procedures based on models and data such that the actual l i

exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely l to be substantially underestimated. The dose calculation methodology and '

parameters established in Part II of the ODCM for calculating the doses due to the actual release rates of the radioactive noble gases in gaseous 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 I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in i Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977. l The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

i 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.

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I REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-7 01/93

RADIDACTfVE EFFLUENTS BASES 3/4.11.2.3 DOSE - IODINE-131. 10 DINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM This control is provided to implement the requirements of Sections II.C, III.A. and IV.A of 10CFR50, Appendix I. The Controls are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the 8 required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assyre that the releases of radioactive materials in gaseous effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The calculational methodology and parameters specified in Part II of the ODCM 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 I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion o PGaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1. July 1977. These equations also provide for determining the actual doses based upon the 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 Qf the calculations were: (1) individual inhalation of airborne radionucludes, (2) deposition cf radionuclides onto green leafy l vegetation with subsequent consumption by man, (3) deposition onto grassy I areas where milk animals ind meat-producing animals graze with consumption )

of the milk and meat by man, and (4) depo:ition on the ground with j subsequent exposure of man.

l This control applies to the release cf 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 3/4-8 01/93

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RADf0ACTfvE EFFLUENTS 1

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3/4.11.2.4 GAsEduS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the PRIMARY PLANT l SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The !

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 i 4

achievable." This control implements the requirements of 10 CFR 50.36a, <

l General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design l

. objectives given in Section II.D of Appendix I to 10 CFR Part 50. The ;

specified limits governing the use of appropriate portions of the systems l were specified as a suitable fraction of the dose design objectives set '

forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous j 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. ;

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I REV. 8 COMANCHE PEAK - UNITS 1 AND 2. PART I B 3/4-9' 01/93

RADIOACTIVE EFFLUENTS j BASES (Continued) 3/4.11.4 TOTAL DOSE !

This control is provided to meet the dose limitations of 40 CFR Part ;

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 f uranium 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 containing 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 I, and if direct radiation doses from the units (including outside storage tanks, etc.) are kept small. The -

Special Report will describe a course of action that should result in the .

limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 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 8 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

20.2203(a)(4) and 20.2203(b), 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 ot*3r requirements for dose limitation >

of 10 CFR Part 20, as addressed in Conu ais 3.11.1.1 and 3.11.2.1. An individual is not consiaered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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COMANCHE PEAK UNITS 1 AND 2 PART I B 3/4-10 Rev. 8 ERRATA (6/93)

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONIT(RING 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 MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessmert Branch Tcchnical 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 environmental 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 environmental '

measurements-in industrial laboratories. It should be recognized that the )

LLO is defined as an a oriori (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.

Detailed discussion of the LLD, and other detection limits, can be found in Currie L. A., " Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300.

31.4d2.2 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 nodifications 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 I to 10 CFR Part 50.

Restricting the census to garden; 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 garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m'.

COMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-11 01/93

R3[1DLOGICAL ENVIRONMENTAL MONITORING BASES _,_

l 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM l

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in j environmental sample matrices are performed as part of the quality !

assurance program for environmental monitoring in order to d-monstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to .

10 CFR Part 50. I I

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CDMANCHE PEAK - UNITS 1 AND 2 PART I B 3/4-12 01/93 l .-. _ . .

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SECTION 5.0 DESIGN FEATURES COMANCHE PEAK - UNITS 1 AND 2 PART I 5-0 01/93

5.0 DESIGN FEATURES MAP DEFINING CONTROLLED AREAS. UNRESTRICTED AREAS AND SITE BOUNDARY 8 FOR RADIDACTIVE GASEOUS AND LIOUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, 8 which allows identification of structures and release points as well l as definition of CONTROLLED AREAS, UNRESTRICTED AREAS and the SITE l BOUNDARY are shown in Figure 5.1-3.

l The UNRESTRICTED AREA, as show in Figure 5.1-3, is that area

~

8 beyond the SITE BOUNDARY. Access to this area is not limited or controlled by the licensee. This is consistent with the definition of UNRESTRICTED AREA given in 10 CFR 20.1003. The SITE BOUNDARY coincides with the Exclusion (fenced) Area Boundary, as defined in 10 CFR 100.3(a). 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.

The CONTROLLED AREA, as shown in Figure 5.1-3, is that area that 8 is inside the SITE BOUNDARY but is outside of any plant areas defined by the licensee as restricted areas, per the definition of restricted area in 10 CFR 20.1003. Access to the CONTROLLED AREA is limited or ;

controlled by the licensee. This is consistent with the definition l of CONTROLLED AREA given in 10 CFR 20.1003. '

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CDMANCHE PEAK UNITS 1 AND 2 PART I 5-1 Rev. 8 ERRATA (6/93)

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- l SECTION 6.0 ;

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COMANCHE PEAK - UNITS 1 AND 2 PART I 6-0 01/93

ADMINISTRATfvE CONTROLS I

ANNUAL RADIOLOGICAL ENVIRDNMENTAL OPERATING REPORT * .)

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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. )

l The Annual Radiological Environmental Operating Reports shall include i summaries, interpretations, and an analysis of trends of the results of the l

j radiological environmental surveillance activities for the report period, j including a comparison with preoperational studies and with operational J controls, as appropriate, and with previous environmental surveillance i 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 j

, all environmental radiation measurements taken during the period pursuant to the locations specified in Table 3.1 and Figure 3.1 in Part II of the j Offsite Dose Calculation Manual, as well as susuarized and tabulated 1 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 l

inclusion with the report, the report shall be submitted noting and l l explaining the reasons for the missing results. The missing data shall be '

submitted as soon as possible in a supplementary report.

The reports 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 t 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 j Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Progras'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.

i

A single submittal may be made for both units. 8

- One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

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

01/93 !

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ADMINISTRATIVE CONTROLS SEMIANNUAL RADIQACTIVE 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 after January 1 and July 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 summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21

" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof.

For solid wastes, the format for Table 3 in Appendix 8 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, Type B.

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 sumary of hourly meteorological data collected over the previous year. This annual summapy 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 stability.**

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station 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 PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period. 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, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses 8 shall be performed in accordance with the methodology and parameters in Part II of the WFSITE DOSE CALCULATION MANUAL (ODCM).

i A single submittal may be made for both units. The submittal should 8 j combine those sections that are cosenon to both units at the station. J In lieu of submission with the Semiannual Radioactive Effluent Release 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.

COMANCHE PEAK 'JNITS 1 AND 2 PART I 6-2

-- , . - - . - - _ _ _ . .--.-.-----.-.__--..____.L

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT I 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 MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, i I

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 Operation."

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

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

The Semiannual Radioactive Effluent Release Reports shall include a !

listing of new locations for dose calculations and/or environmental l monitoring identified by the Land Use Census pursuant to Control 3.12.2. 1 The Semiannual Radioactive Effluent Release Reports shall also include 1 the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the l time specifidd in Controls 3.3.3.4 or 3.3.3.5, respectively; and a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the Technical Specification limits.

6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)

)

Changes to the ODCH: l l

a. Shall be documented and records of reviews performed shall be l retained as required by Specification 6.10.3.o. This documentation shall contain:

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

2) A determination that the change will maintain the level of 8 radioactive effluent control required by 10 CFR 20.1302, 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 after review and acceptance by the SORC 1 and the approval of the Vice President, Nuclear Operations.

COMANCHE PEAK - UNITS 1 AND 2 PART I 6-3 REV. 8 01/93

ADMINISTRATTVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM] (continued)

c. Shall be submitted to the Commission in the form of a complete. l 1egible copy of the entire ODCM 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 markings 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.

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

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SECTION 1.0 4

, LIQUID EFFLUENTS ;

The Comanche Peak Steam Electric Station (CPSES) is a 2 unit naclear 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 radwaste processing system are batch type releases, from the Plant Effluent 7A Tanks (PET), Laundry Holdup & Monitor Tanks (LHMT) and Waste Monitor Tanks (WMT), discharged to SCR via the Circulating Water Discharge Tunnel. Potentially radioactive liquid effluent releases from 8 secondary systems include a continuous 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 Waste (LVW) Pond 7 for chemical treatment. The LVW Pond normally discharges to SCR via 8 the circulating Water Discharge Tunnel. Alternatively, secondary waste streams may be routed to the common Waste Water Holdup Tanks (WWHT). The WWHTs may be released on a batch basis to the LVW Pond or to SCR via the Circulating Water Discharge Tunnel, depending on the 7 l 1evels of radioactivity present. Table 4.11-1 of Part I of this 8 document requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentrations that exceed the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Also, releases from the Station Service Water (SSW)

System are monitored for radioactivity, although no significant releases of radioactivity are expected from this pathway. Sampling and aatlysis requirements for all release sources are given in Part I, Table.4.11-1. All batch release sources are isolated and thoroughly mixed by mechanical mixing or recirculating the tank contents, prior

]

to sampling, to assure representative sampling. The recirculation or mixing times necessary to assure representative sampling shall be specified in station procedures.

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

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

! The liquid effluent radiation monitors shown in Figure 1.1 are part of 7 the plant Digital Radiation Monitoring System (DRMS) supplied by l

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 j j factor for detector output from counts'per minute to uC1/ml is determined in the calibration process and input into the database for i the monitor microprocessor.

1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL 3/4.11.1.1 8 !

COMPLIANCE ,

To demonstrate compliance with 10 CFR 20.1301, 00CM 8 Radiological Effluent Control 3/4.11.1.1 requires that the ;

concentration of radioactive material released in liquid i effluents to CONTROLLED AREAS and UNRESTRICTED AREAS be limited to the concentrations specified in 10 CFR 20, Appendix ]

B Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases, and to 2E-4 uC1/ml for dissolved or ,

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

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

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

ICi= ICg + (Ca + Cs + Ct + C Fe) i g [Eq 1-1]

Where: IC1= Sum of the concentrations of each radionuclide, in the i release (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 analyzed for gross alpha only) 7 Cs = Concentration of 89S r and 90S r as measured in the 7 most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

Ct= Concentration of 3H as measured in the most recent 7 composite sample (uC1/ml) required by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1.

Cre= Concentration of 55F e as measured in the most recent 7 composite sample (uC1/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

1.1.2 Effluent Flow Rate (f)

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

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

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

i 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, j respectively. l 1.1.3 Dilution of Liouid Effluents _

a. Discharges to SCR via Circulating Water Discharge Tunnel 7 Since liquid effluents from the radwaste treatment system, 7 l Waste Water Holdup Tanks and the LVW Pond are mixed with Circulating water prior to being discharged to Squaw Creek

Reservoir, complir.nce with 10 CFR 20_is a function of the Circulating water flow rate. The maximum Circulating water i flow rate per plant is 1.1 million gps. This is determined l from the Ingersoll-Rand pump curves (Fig. 1.2) which indicate 7 !

a flow rate per pump of 275,000 gpm. The actual Circulating l water dilution flow is given by- I

... F(diluting flow) = (275,000 gps / pump) x (f of' pumps) x 0.9 7

[Eq. 1-2]

]

Where: 0.9 = Safety Factor to compensate for flow' 7 fluctuations from the rate predicted by the i Circulating water pump curves (Fig. 1.2). !

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

available dilution flow for any release is reduced by the required dilution flow for any other concurrent releases.

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

1 F' = F (1 - 1 (C'j/ECLj)) [Eq 1-3] 8 Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-4 01/93

i Where: F'= Adjusted Circulating Water Flow Rate 7

C'i = Concentration of radionuclide i in the Reservoir 7 (uC1/ml) as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Control 3/4.12.1 Table 3.12.1. This sample is taken at the Circulating water intake structure as indicated by location SW6 on Table 3.1 and Figure 3-1 of this manual.

ECL1= Effluent Concentration Limit of radionuclide 8 i, from 10CFR20, Appendix B, Table 2, Column 2 F= (275,000 gpm/ pump) x (i of pumps) x 0.9 7 j NOTE:

If C'j is less than LLD then F' = F and no adjusted flow 7 l

rate need be considered in the calculation of ADF. The LLD i values used for this determination shall be the LLD valves for l l

water given in Radiological Effluent Control 3/4.12.1. Table. !

4.12-1.

i i

b. Discharges to the LVW Pond 7

i Secondary release sources are discharged directly to the LVW 7 Pondwithnodilution(i.e.,F=0).

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.

ADF = (f + F)/f [Eq. 1-41 7 Where: f = effluent flow rate (gpm)

. F = dilution flow rate (gpm) 7 NOTE:

l If radioactivity is. detected in the Reservoir, an adjusted 7 Circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See section 1.1.3 for the calculation of F' (Eq. 1-3). Also, if simultaneous releases 1 are occurring, the available dilution flow shall be reduced by l

the required dilution flow for any other concurrent release.

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

1.1.5 Reauired Dilution Factor (RDF)

The required dilution factor ensures that the effluent 8 concentrations expressed in 10CFR20, Appendix B. Table 2, Column 2, and a total concentration of dissolved or entrained noble gases of 2 x 10-4 uCi/ml are not exceeded during a discharge. The required dilution factor includes a safety factor of 2 to provide a margin of assurance that the 1 j instantaneous concentration limits are not exceeded.

RDF = (Ij (C /ECLj))

1 x SF 8 ,

=

(Ig (C /ECL g g) + (Ca/ECL'a + Cs/ECLs + 8 Ct /ECLt+CFe/ECLpe)) x SF [Eq 1-5) 8 ;

1 Where: ECLj = Effluent Concentration Limit of 8 radionuclide 1, from 10 CFR20, Appendix l B, Table 2. Column 2 l

SF = Safety Factor of 2. 7 l

J All other variables and subscripts are previously defined. l l

NOTE: If RDF is less than 1, the release meets discharge limits 7 without dilution. For conservatism, set RDF equal to 1.0. l The maximum value for the high alarm setpoint for detector 7 XRE-5253 would then be calculated in accordance with the equation for C1 w in Section 1.2.1.

1.1.6 10 CFR 20 Como11ance l

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:

EDE 5 1.0 [Eq 1-6] 7 ADF 1

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

1.2 RADIATION MONITOR ALARM SETPOINTS 7 1.2.1 Primary Liouid Effluent Monitor XRE-5253 7 To ensure that releases from the primary radwaste processing 8 system do not exceed 10 CFR 20, Appendix B. Table 2. Column 2 limits at the point of release to the CONTROLLED AREA or UNRESTRICTED AREA, a radiation detector (XRE-5253) monitors discharges to the Circulating Water Discharge Tunnel. XRV-5253 is the discharge isolation valve controlled by XRE-5253.

The isolation valve shuts automatically if the detector 7 alarms on high radiation or a detector operation failure occurs. The 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, setpoints may be established at values lower than the calculated values, if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.

C1 w = (ADF/RDF) x I C g [Eq 1-7] 7 9

Where: Cw=

1 The liquid waste effluent monitor alarm setpoint. This corresponds to the gamma 8 concentration in the undiluted waste stream which after dilution would result in Effluent Concentration Limit level releases (uCi/ml).

All other variables are as previously defined.

When considering the mixture of nuclides in the liquid 7 effluent stream in terms of detector sensitivity, the most probable nuclides present would be those referenced in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. Table Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-7 01/93

l Notation 2. Figure 1.3 is a representative energy sp:ctrum 7 response for the RD-33 type detector used in XRE-5253. This l curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant. In fact between 137Cs and 60C o, the total change in sensitivity is approximately 7%. Because this is well within the accuracy l l of measurement, there is no need to change the software sensitivity for given varied effluent concentrations.

l However, should the concentration of previously unexpected l nuclides become significant, further evaluation would be required.

1.2.2 Turbine Buidlina Sumo Effluent Radiation Monitor 1RE-5100 and 8 2RE-5100

~~

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 Turbine Building Sumps, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm, should an inadvertent radioactive release occur. To this end, the setpoint will be ;

initially established at three (3) times background until 7 further data can be collected. Then, if this setpoint is 8 exceeded, the monitor will direct control valves to divert the turbine building sumps discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be l

sampled and released in a batch 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 detected in the Turbine Building Sumps, a setpoint then may be Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1 8 01/93

)

~

I I l

established for 1RE-5100 or 2RE-5100 using the methodology in 8 l Section 1.2.1 to ensure that 10 CFR 20 Effluent Concentration )

limits are not exceeded in discharges to the LVW Pond.

l 1.2.3 Service Water Effluent Radiation Monitors 1RE-4269/4270 and 8 l 2RE-4269/4270 i

j The concentration of radioactive material in the service water 7 1 effluent line normally is expected to be insignificant.

Therefore, the monitor alert alarm setpoint should 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 4

can be collected. If this effluent stream should become i contaminated, radionuclide concentrations should be determined

from grab samples and a radiation monitor alarm setpoint determined as follows

1 Csw " (I g Cg ) + DF [Eq 1-8) 7 Where: Csw = the Service Water effluent monitor alarm 7 setpoint Cg = the concentration of each measured gamma 7 emitter g, observied in the effluent (uCi/ml)

DF = Ii(C 1/ECLj) = the dilution factor 8 required to ensure effluent concentration limits are not exceeded.

1 1

For this release pathway no additional dilution is available.

Therefore, if the calculated DF is greater than 1.0, any 7 releases occurring via this pathway will result in a violation of Radiological Effluent Control 3/4.11.1.1. If radioactivity is detected in this release stream, doses due to releases from this stream shall be calculated in accordance with the methodology given in Section 1.3, with the near field average dilution factor, Fk , equal to 1.0.

Rev. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-9 01/93

4

i

! i i 1.3 DOSE CALCULATION FOR LIOUID EFFLUENTS l

l

! For implementation of Radiological Effluent Control 7 ,

3/4.11.1.2, the dose comitment from the release of liquid '

effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose comitments will be maintained for each calendar quarter and each calendar year. Dose calculations will be performed for J l releases from the Plant Effluent Tanks, Waste Monitor Tanks, 7A Laundry Holdup & Monitor Tanks, Waste Water Holdup Tanks, and 7 the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir. Although the LVW Pond is 8 located in a CONTROLLED AREA, dose calculations for discharges to the LVW Pond will not be performed because there are no '

real pathways for exposure to members of the public. Doses for these pathways will be calculated when the LVW Pond is 7 discharged to Squaw Creek Reservoir. The cumulative dose over the desired time period (e.g., the sum of all doses due to releases during a 31 day period, calendar quarter, or a l calendar year) will be calculated using the following equation: ,

DT= IDk+ ID(lake)m [Eq 1-9]

k m Where DT= the dose comitment to the total body or any organ due B to all releases during the desired time interval from )

all release sources (arem).

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

D(lake)m= the dose comitment received by the total body or any 7 organ during the desired time period, m, (normally m =

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

1-12). 7 Rev. 8 C0KANCHE PEAK - UNITS 1 AND 2 PART II 1-10 01/93

~

3 To demonstrate compliance eith 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 l 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 l release will be calculated using the following equation.

Dk* Ti Aj tk Cik Fk [Eq. 1-10] 7 l

Where: tk =

the time duration of the release k (hrs) 7 l l )

Cik = The isotopic concentration (uC1/ml) of 7 radionuclide i found in the release sample for- :

release k. Concentrations are determined i primarily from gama isotopic analysis of the [

liquid effluent sample. For Sr-89, SR-90, H-3, Fe-55 and alpha emitters, the last measured value will be used in the dose calculation.

i Fk

=

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

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

l

I Air = the site related ingestion dose commitment 7 factor for the toal body or any organ, r , for j each identified gamma or beta emitter (mrem /hr !

I per uC1/ml) . Ari is calculated as follows- l l

. Ari = 1.14x105 (Uw/Dw + UrBFj) DFj l

[Eq. 1-11] 7 !

l

)

Where: 1.14x105 = unit conversion factor, 7 I

l Uw = adult water consumption from Squaw Creek 8 i Reservior. 0 liters /yr for CPSES.

, Uf = adult fish consumption, 21 kg/yr 7 i BFj = bicaccumulation factor for radionuclide i, in 7 i fish from Table A-1, Ref. 2 (pCi/kg per pCi/1) 7 l DFi =

adult dose conversion factor for radionuclide 7 i, from Table E-11 Ref. 2 (mrem /pci ingested)

Dw

=

Dilution factor from the near field area 7 within one-quarter mile of the release 1 point to the potable water intake for the adult water consumption; 1.0 for CPSES.

(unitiess)

Calculated values for Ai r are given in Table 1.2.

1.3.2 Calculation of Dose Due to Radionuclide Builduo in the Lake 7 1 i

I The dose contribution from significant pathways, due to 8 buildup of previously discharged radionuclides in the lake, must be considered in the committed dose calculation only if Rev. 8 COMANCHE PEAK - UNITS 1 AND 2- PART II 1-12 0 1/93 ___ _ _ . _

radioactivity is detected in the water of-Squaw Creek 8 Reservoir or in fish from Squaw Creek Reservoir. Based on the design calculations presented in the CPSES FSAR, Appendix 11A and documented in CPSES Engineering Calculation No. ME-l CA-0000-3161, the significant pathways included in this I

calculation are fish consumption from Squaw Creek Reservoir and consumption of meat from cows drinking water from Squaw Creek. Additionally, consumption of milk from cows drinking water from Squaw Creek is included, but a CPSES site-specific consumption factor of 0 is normally used since there are no identified animals milked for human consumption along Squaw Creek. If animals milked for consumption are identified along Squaw Creek during the annual land use census, this pathway should be included in the dose calculation. Also, water from Squaw Creek Reservoir or Squaw Creek is not used as a source of drinking water, so the drinking water pathway is not included in dose calculations.

To further simplify the calculation, the dose due to 8 l consumption of meat and milk from cows drinking water from Squaw Creek is only calculated for tritium. CPSES Engineering Calculation No. ME-CA-0000-3161 shows that tritium is the only isotope routinely released from CPSES that j significantly contributes to the dose from these pathways (i.e., >95% of the total dose). The calculation does show a significant dose contribution from Ru-106 for the cow-meat pathway, but this isotope has not historically been observed in actual CPSES liquid effluent samples. The dose from the fish consumption pathway will be calculated for all measured 4

isotopes.

l The contribution to the total dose due to the buildup of 8 radionuclides in the reservo'ir is determined as follows: '

D(lake), = 1.Mxi d @ g M gC 4f U)+

8 f

DFt C tw Qaw IU milk Imt + UmeatFftU

[Eq. 1-12) 1 l COMANCHE PEAK UNITS 1 AND 2 PART II 1-13 Rev 8 ERRATA (6/93)

Where: 1.14 x 10-4 = units conversion factor (yr/hr) >

C'jr =

concentration of radionuclide i in fish 7 sampled from Squaw Creek Reservoir from i

! location F1 or Table 3.1 and Figure 3.1 of this manual (pCi/kg)

DFt

= adult ingestion dose conversion factor for #

8 l

tritium for the organ of interest form Table E-11, Ref. 2 (mrem /pCi).

C'tw = concentration of tritium in the reservoir. 8 l

This value shall correspond to the highest concentration measured at any Squaw Creek ,

Reservoir sample location (pCi/1).

Qaw

= the consumption rate of contaminated water by 8 a cow, 60 1/ day from Table E-3, Ref. 2.

Umilk = adult milk consumption rate. A CPSES site 8

! specific useage factor of 0 is normally used l unless milk cows are identifed along Squaw Creek during the annual Land Use Census. If i

milk cows are identifed, a value of 310 1/yr from Table E-5, Ref. 2, should be used. ,

t Fat =

the stable element transfer coefficient for 8 tritium that relates the daily intake rate of tritium by a cow to the concentration in milk, 1.0E-2 pC1/1 per pCi/ day from Table E-1, Rev.

2.

Umeat

= adult meat consumption rate, 110Kg/yr from 8 Table E-5, Ref. 2.

Fft =

the stable element transfer coefficient for 8 tritium that relates the daily intake rate of tritium by a cow to the concentration in meat, 1.2E-2 pC1/kg per pC1/ day.

l Rev. 8

, COMANCHE PEAK - UNITS 1 AND 2 PART II 1-14 01/93

i j All oth;r variables are previously defin;d. 7 i

NOTE: This calculation is only required if activity is detected in 7 water and/or fish in excess of the appropriate LLD values !

given in Radiological Effluent Control 3/4.12.1, Table 4.12-1.

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

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

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 l estimated dose for a unit due to any anticipated unusual releases during the period for which the projection is made.

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

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

1.5 DEFINITIONS OF COMMON LIOUID EFFLUENT PARAMETERS 7 IEBM DEFINITION ADF Actual Dilution Factor (unitiess). This is defined as the 7 ratio of the effluent flow rate plos the circulating water ,

flow rate divided by the effluent flow rate.

Ajr The site related ingestion dose connitment factor to the 7 :'

total body or any organ, 7 , for each identified gamma or

{ beta emitter, 1. (mrem /hrperuC1/ml)

BFj Biaccumulation factor for radionuclide, i, in fish from 7 Reg. Guide 1.109. (pC1/kg per pC1/1)

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) i Cre The concentration of 55F e in liquid waste as measured 7 in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3 3/4.11.1.1, Table 4.11-1. (uC1/ml) ;

cg The concentration of each measured gannia 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 (uC1/ml)

C1 The concentrations of radionuclide, 1, in the waste tank. 7 (uCi/ml) l

' C'j 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 l 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'g The concentration of radionuclide i in fish sampled from 7 the reservoir from location F1 on Table 3.1 and Figure 3-1 of this manual (pC1/kg).

Cik The isotopic concentration of radionuclide i found in 7 the pre-release sample for batch release k.

Concentrations are determined primarily from gaiana 1

8'10 topic analysis of the liquid effluent sample. For JSr, 90S r, 3g, 55 Fe and alpha emitters, the last measured value will be used. (uC1/ml)

COMANCHE PEAK - UNITS 1 AND 2 PART II 1-16 01/93

i 1

l 1

C'jw The concentration of radionuclide i in the reservoir as 7 l

< measured at the Circulating water intake structure shown ,

as location SW6 on Table 3.1 and Figure 3-1 of this !

manual (pCi/1).

Cw1 The liquid waste effluent monitor alarm setpoint. This 8 l corresponds to the gamma concentration in'the cadiluted 1 waste stream which after dilution would result in ECL- l level releases. (uCi/ml) ;

Cs The concentration of 89S 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 (uC1/ml)

Csw The Service Water effluent monitor alarm setpoint. 7 (uCi/ml)

Ct The concentration of 3H in liquid waste as measured in the 7 )

analysis of the most recent monthly composite sample required ,

by Radiological Effluent Control 3/4.11.1.1. Table 4.11-1 '

(uC1/ml)

DFj Adult dose conversion factor for radionuclide, 1, from 7 Reg. Guide 1.109 (mrem /pCi ingested) :

Dk The dose commitment received by the total body or any organ 7 i during the duration of batch release k of liquid effluents. !

(mrem)

D(lake)m The dose comitment received by the total body or 7 1 any organ during a desired time period, m, due to the buildup in the lake of previously discharged radionuclides. (mrem)

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

Dw Dilution factor, from the near field area within 1/4 mile of 7 the release point to the potable water intake for adult water ;

consumption, 1.0 for CPSES (unitiess) '

f Effluent flow rate. (gpm) 7 ;

1 F Circulating water flow rate (or dilution flow rate). (gpm) 7 4

F' Adjusted Circulating water flow rate to account for buildup 7 of radionuclides in the Circulating water due to previous i releases. (gpm) :

REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-17 01/93

_ - 1

l 1

l 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. ;

ECla Effluent Concentration Limit

of a mixture of 8 unidentified alpha emitters. (uCi/ml)

ECLF e Effluent Concentration Limit

of 55F e. (uci/ml) 8 l l

ECLg Effluent Concentration Limit

of each identified gama 8 emitter, g. (uCi/ml) !

ECLj Effluent Concentration Limit

of radionuclide, 1. 8 (uC1/ml)

ECLs Effluent Concentration Limit

of a mixture of 895 r and 8 90S r. (uC1/ml)

ECL Effluent Concentration Limit

of tritium (3H) 8 l

t (uCi/ml)

SF Safety Factor of 2. Used in the calculation of the Required 7

^_ Dilution Factor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are not exceeded.

RDF Required Dilution Factor (unitiess). This is defined as the 8 dilution factor that ensures that the effluent concentrations expressed in 10CFR20, Appendix B, Table 2, 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

Effluent Concentration limits (ECL) for liquids are given in 8 10CFR20, Appendix B. Table 2 Column 2. A value of 2x10-4 uC1/al for dissolved or entrained noble gas shall be used.

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

,- y ,'..+s.-

- e e. v. -.y + y a y %.--w.-ew..,

l i

i l

TABLE 1.1 J

SUMMARY

OF LIOUID RELEASE PATHWAYS 1

i 1. RELEASES TO .CCR VIA THE CIRC WATER DISCHARGE 1

l Release Source Release Type Max Flow Max Vol Monitor Rate (acm) (cal) _

j PET-1 Batch 100 30000 XRE-5253 7A l 4

PET-2 Batch 100 30000 XRE-5253 7A .

l WMT-1 Batch 100 5340 XRE-5253 ,

j WMT-2 Batch 100 5340 XRE-5253 '

j LHMT-1 Batch 100 5875 XRE-5253 l

! LHMT-2 Batch 100 5875 XRE-5253 l WWHT-1 Batch 200 25000 None l 4

WWHT-2 Batch 200 25000 None !

3 LVW Pond Continuous 1600 -

None

{ 2. RELEASES TO THE LVW POND I

, l Release Source Release Type Max Flow Max Vol Monitor )

Rate (com) (aal) )

._ 1 i 'CPBRT Batch 25 8500 None

, CCWDT (Unit 1) Batch 40 2300 Mone 8 J

CCWOT (Unit 2) Batch 40 2300 None 8 WWHT-1 Batch 200 25000 None WWHT-2 Baten 703 25000 None I TBSump2 (Uniti) Continuous 300 -

1RE-5100 i TBSump4 (Unit 2) Continuous 300 -

2RE-5100 8

3. )IRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT) 4 !

l Release Source Release Type Max Flow Max Vol Monitor Rate (com) (cal) 1 l Unit 1 SSW Train A Continuoas 17,000 -

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

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

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

2RE-4270 8 i

i 1

l t

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

i l

, TABLE 1.2 7

} PAGE il of 4) !

l SITE RELATED INGESTION SOSE COMMITMENT FACTOR Aj7

{ (mrem /hr per uC1/ml) i i

ISOTOPE SQ.NE Llylg T-BODY TB'RQH KIDNEY LQNfa GI-LLI l f H-3 0.00E+00 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 '8 3 I

C-14 3.13E+04 6.25E+03 6.25E+03 6.25E+03 6.25E+03 6.25E+03 6.25E+03 8 j NA-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.n7E+02 .4.07E+02 4.07E+02 8 )

l P-32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 C._DE+00 0.00E+00 5.20E+06 8 i

] CR-51 0.00E+00 0.00E+00 1.27E+00 7.62E-01 2.80E-01 1.69E+00 3.20E+02 8

MN-54 0.00E+00 4.38E+03 8.35E+02 0.00E+00 1.31E+03 0.00E+00 1.34E+04 8 l

MN-56 0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.40E+02 0.00E40 3.51E+03 8 j FE-55 6.58E+02 4.55E+02 1.06E+02 0.00E+00 0.00E+00 2.54E+02 2.61E+02 8 I FE-59 1.04E+03 2.44E+03 9.35E+02 0.00E+00 0.00E+00 6.82E+02 8.16E+03 8 CO-58 0.00E+00 8.91E+01 2.00E+02 0.00E+00 0.00E+00 0.00E+00 1.81E+03 8 j CD-60 0.00E+00 2.56E+02 5.65E+02 0.00E+00 0.00E+00 0.00E+00 4.81E+03 8 NI-63 3.11E+04 2.16E+03 1.05E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02

{ 8 i WI-65 1.26E+02 1.64E+01 7.49E+00 L.00E+00 0.00E+00 0.00E+00 4.16E+02 8 CU-64 0.00E40 9.97E+00 4.68E+00 0.00E+00 2.51E+01 0.00E+00 8.49E+02

{ 8

{ ZN-65 2.32E+04 7.37E+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.65E+04 8 l ZN-69 4.93E+01 9.44E+01 6.56E+00 0.00E+00 6.13E401 0.00E+00 1.42E+01 8 BR-83 0.00E+00 0.00E40 4.05E+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 8

., BR-84 0.00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00E+00 4.11E-04 8 1

? BR-t ';

0.0(E+00 0.00E+00 2.15E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-15 8 l R8-86 0.00E+00 1.01E+05 4.71E+04 0.00E+00 0.00E+00 0.00E+00 2.00E+04 8 j RB-88 0.00E40 2.94E+02 1.56E+02 0.00E+00 0.00E+00 0.00E+00 3.93E-09 8 RB-89 0.00E+00 1.95E+02 1.37E+02 0.00E+00 0.00E+00 0.00E+00 1.13E-11 8 l

SR-89 2.21E404 0.00E+00 6.35E+02 0.00E+00 0.00E+00 0.00E+00 3.55E+03 8

. SR-90 5.47E405 0.00E+00 1.33E+05 0.00E+00 0.00E+00 0.00E+00 1.58E+04 8 a SR-91 4.07E+02 0.00E+00 1.64E+01 0.00E+00 0.00E+00 0.00E+00 1.94E+03 8 q SR-92 1.54E+02 0.00E+00 6.67E+00 0.00E+00 0.00E+00 0.00E+00 3.06E+03 8 j Y-90 5.77E-01 0.00E+00 1.54E-02 0.00E+00 0.00E 40 0.00E+00 6.11E+03 8 4 Y-91M 5.44E-03 0.00E+00 2.11E-04 0.00E+00 0.00E+00 0.00E+00 1.60E-02 8 l Y-91 8.45E+00 0.00E+00 2.25E-01 0.00E40 0.00E+00 0.00E+00 4.64E+03 8 Y-92 5.06E-02 0.00E+00 1.48E-03 0.00E+00 0.00E+00 0.00E+00 8.87E+02 l 8 REV. 8

] COMANCHE PEAK - UNITS 1 AND 2 PART II 1-20 01/93 d

. , , , , - - _ . , ~ - , . . , , . , . -.,.......__._,,,.,,,._..,,,,,,...,c._, ,_,,,...,m. , . , . . . . . -

1 l

l TA8LE 1.2 7 PAGE (2 of 4) i SITE RELATED INGESTION DOSE COMMITMENT FACTOR A17 (mrem /hr per uCi/ml) !

ISOTOPE EE LIVER T-BODY THYROID KIDNEY LlLNG GI-LLI Y-93 1.60E-01 0.00E+00 4.43E-03 0.00E+00 0.00E+00 0.00E+00 5.10E 4 3 8 ZR-95 2.40E-01 7.70E-02 5.21E-02 0.00E40 1.21E-01 0.00E+00 2.44E+02 8 l ZR-97 1.33E-02 2.68E-03 1.22E-03 0.00E+00 4.05E-03 0.00E40 8.30E+02 8 N8-95 4.46E+02 2.49E42 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 8 ;

MD-99 0.00E+00 1.03E+02 1.96E+01 0.00E+00 2.35E+02 0.00E+00 2.39E+02 8 l

TC-99M 8.86E-03 2.51E-02 3.20E-01 0.00E+00 3.80E-01 1.23E-02 1.4BE+01 8 TC-101 9.13E-03 1.31E-02 1.29E-01 0.00E+00 2.37E-01 6.72E-03 3.95E-14 8 RU-103 4.42E+00 0.00E+00 1.91E+00 0.00E+00 1.69E+01 0.00E+00 5.16E+02 8 RU-105 3.69E-01 0.00E+00 1.45E-01 0.00E+00 4.76E+00 0.00E+00 2.26E42 8 RU-106 6,5SE+01 0.00E40 8.33E+00 0.00E+00 1.27E+02 0.00E+00 4.27E+03 8 AG-110M 8.81E-01 8.13E-01 4.84E-01 0.00E+00 1.60E+00 0.00E40 3.33E+02 8 i TE-125M 2.57E+03 9.29E+02 3.44E+02 7.72E+02 1.04E+04 0.00E40 1.02E+04 8 TE-127M 6.49E+03 2.32E+03 7.90E+02 1.66E+03 2.63E 44 0.00E+00 2.17E+04 8 ,

TE-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.00E+00 8.31E+03 8 TE-129M 1.10E44 4.11E+03 1.74E43 3.78E+03 4.60E+04 0.00E+00 5.55E+01 8 TE-129 3.01E+01 1.13E+01 7.32E+00 2.31E+01 1.26E+02 0.00E+00 2.27E41 8 TE-131M 1.066+03 8.11E+02 6.75E+02 1.28E+03 8.21E+03 0.00E+00 8.04E+04 8 TE-131 1.89E+01 7.88E+00 5.95E+00 1.55E+01 8.26E+01 0.00E+00 2.67E+00 8 I l

TE-132 2.41E43 1.56E+C3 1.46E+03 1.72E+03 1.50E+04 0.00E+00 7.38E+04 8 I-130 2.72E+01 8.02E+01 3.17E+01 6.78E+03 1.25E+02 0.00E40 6.90E+01 8 I-131 1.5 2.14E+02 1.22E+02 6.99E+04 3.68E+02 0.00E+00 5.64E+01 8 l I-132 7. 1.95E+01 6.81E+00 6.81E+02 3.10E+01 0.00E+00 3.687 *0 8 I-133 5. 8.86E+01 2.70E+01 1.30E+04 1.55E+02 0.00E+00 7.96 N 1 8 I-134 3.80E+00 1.03E+01 3.71E+00 1.79E+02 1.65E+01 0.00E+00 9.01E-03 8 I-135 1.59E+01 4.16E+01 1.54E+01 2.75E+03 6.69E+01 0.00E400 4.70E+01 8 CS-134 2.98E+05 7.09E45 5.79E+05 0.00E+00 2.29E+05 7.62E+04 1.24E+04 8 CS-136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 9.39E403 1.40E+04 8 CS-137 3.81E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.89E+04 1.01E+04 8 CS-138 2.64E+02 5.22E+02 2.59E+02 0.00E+00 3.83E+02 3.78E+01 2.23E-03 8 8A-139 9.29E-01 6.61E-04 2.72E-02 0.00E+00 6.18E-04 3.76E-04 1.65E+00 ,8 REV. 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 1-21 01/93

l TABLE 1.2 7 PAGE (3 of 4)

SITE RELATE 0 INGESTION 00SE COMMITMENT FACTOR Aj, (mrem /hr per uC1/ml)

ISOTOPE Rft1 N LlyR T-BODY THYROID KIDNEY QNfa GI-LLI I

BA-140 1.94E+02 2.45E-01 1.27E+01 0.00E+00 8.31E+00 1.39E-01 4.00E+02 8 BA-141 4.51E-01 3.41E-04 1.53E-02 0.00E40 3.17E-04 1.93E-04 2.06E-10 8 BA-142 2.04E-01 2.09E-04 1.28E-02 0.00E+00 1.77E-04 1.19E-04 2.87E-19 8 LA-140 1.50E-01 7.53E-02 1.99E-02 0.00E40 0.00E+00 0.00E+00' 5.52E+03 8 3 LA-142 7.66E-03 3.16E-03 8.66E-04 0.00E+00 0.00E+00 0.00E+00 2.54E+01 8 l CE-141. 2.24E-02 1.51E-02 1.72E-03 0.00E+00 7.05E-03 0.00E+00 5.79E+01 8 f

CE-143 3.94E-03 2.91E+00 3.24E-04 0.00E+00 1.29E-03 0.00E+00 1.09E+02 8 l CE-144 1.17E+00 4.89E-01 6.26E-02 0.00E+00 2.91E-01 0.00E+00 3.94E+02 8 l

PR-143 5.52E-01 2.21E-01 2.73E-02 0.00E+00 1.28E-01 0.00E+00 2.41E+03 8 :

PR-144 1.A0E-03 7.49E-04 9.16E-05 0.00E+00 4.23E-04 0.00E+00 2.59E-10 8 i ND-147 3.76E-01 4.35E-01 2.60E-02 0.00E+00 -2.54E-01 0.00E+00 2.09E+03 8 !

W-187 2.95E+02 2.48E+02 8.65E41 0.00E40 0.00E+00 0.00E40 8.11E+04 8 !

NP-239 2.86E-02 2.79E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 5.74E+02 8 !

SB-122 4.42E+00 8.71E-02 1.29E+00 6.01E-02 0.00E+00 2.30E+00 1.27E+03 8 l

- SB-124 S.38E+01 1.01E+00 2.12E+01 1.30E-01 0.00E+00 4.18E+01 1.52E+03 8 I

- BR-82 l 0.00E+00 0.00E+00 1.78E+02 0.00E+00 0.00E+00 0.00E+00 2.05E+02 8 1

- S8-125 4.27E+01 4.58E-01 8.58E+00 3.80E-02 0.00E+00 4.45E+03 3.78E+02 8 l

- SB-126 2.20E+01 4.47E-01 7.93E+00 1.35E-01 0.00E40 1.35E+01 1.80E+03 8

- SB-127 4.94E40 1.80E-01 1.90E+00 5.94E-02 0.00E+00 2.93E+00 1.13E+03 8

- LA-141 1.14E-02 3.55E-03 5.81E-04 0.00E+00 0.00E+00 0.00E+00 4.23E+02 8 i

REV. 8 j l

COMANCHE PEAK - UNITS 1 ANO 2 PART.II 1-22 01/93

l 1

2

The adult dose conversion factors, DFj, for Sb-122 are not published 5 l 1

4 2

in Reference 2. The calculation of dose conversion factors and site- !

! related ingestion dose commitment factors for Sb-122 is documented in l Reference 10. ;

i I

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

],

I l

i i

l 1 i

4 S

T i

4 l

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

f _Urut i SSW _Itavi A <.,f+,,,4 t- .

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LIQUID EFFLUENT DISCHARGE PATHWAYS o NOTES:

dg4 (1) Spared in place hop (2) Descharge valve closes on morW t lie rad, loss of flow, or channel out of service alarms.

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COMANCHE PEAK - UNITS 1 AND 2 i

! PART II 1-26 01/93 i

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, FOR RD-33 TYPE DETECTOR 1

Figure 1.3 !

tra. era asem w e. er. g,w..e com .er emoe wer. u.,ng en mo.c or um. g.omery ;

COMANCHE PEAK - UNITS 1 AND 2 01M3 PART II 1-27

SECTION 2.0 GASEOUS EFFLUENTS 1

8 At CPSES, normal radioactive gaseous effluents are collected in a 8 common exhaust air intake plenum, processed through charcoal and HEPA filters, and discharged to the atmosphere through the two common Plant Vent Stacks designated as Stack A and Stack B. Due to the fact that these release points are below the height of the nearest adjacent structure (i.e., containment building), all gaseous releases from these stacks are conservatively assumed to

~

be entrained into the building wake and cavity regions, which results in a conservative ground-level release.

4 Routine gaseous effluent releases may occur from the Unit 1 and 8 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 l

pressure relief and WGDT discharges are treated as batch releases. Because Containment Building purges are only allowed during MODES 5 and 6 and because radioactivity is discharged rapidly from the containment atmosphere 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 j to the continuous release already occurring through the plant vent stacks.

l 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) vents during maintenance on the Waste Gas Processing System, from the Containment Buildings during Intergrated Leak Rate Test (ILRT), and from secondary steam releases (potentially radioactive during periods of primary-to-secondary leaks).

These releases occur infrequently and are treated as batch releases.

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

l A summary of all gaseous effluent release points, release 8 sources,flowrates(ifapplicable)andassociatedradiation monitors is shown in Table 2.1. A flow diagram of all gaseous effluent discharge pathways is shown in Figure 2.1. '

t Each Plant Vent Stack is equipped with a Wide Range Gas Monitor 8 l (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 l Atomics). Since all DRMS monitors provide a digital output, l they may be calibrated to read out'in the appropriate engineering units (i.e., uC1/ml). The conversion factor for detector output l from counts per minute to uCi/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 !

t

~

Stacks A and B, respectively. Each WRGM consists of a low range (10-7 to 10-1 uC1/cc), mid range (10-4 to 102 uC1/cc), i and high range (10-1 to 103 uCi/cc) noble gas activity '

i detector. The WRGMs also have an effluent. release rate channel I4 which uses inputs from the appropriate WRGM noble gas activity

(

detectors and the plant vent stack flow rate detectors (X-FT- i 5570A-1/B-1) to provide an indication of noble gas release rate )

in uC1/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. Execeeding the WRGM effluent release rate channel high alarm setpoint also initiates i

automatic termination of Waste Gas Decay Tank releases.

The stack PIGS are designated as particulate channels XRE-5568A and XRE-55688, iodine channels XRE-5575A and XRE-55758, and noble gas channels XRE-5567A and XRE-55678 for Stacks A and B, respectively. The stack PIG noble gas channels may be used as a back-up to the WRGM when no automatic control functions are

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

l l

required. Therefore, a methodology is provid:;d for calculating l the PIG noble gas monitor setpoints. i4ethodologies are not 8 ,

provided for calculating setpoints for the PIG particulate and j iodine channels, since these channels are not required by the Radiological Effluent Controls Program, and because it is not l

practical to establish instaneous setpoints for integrating type

! monitors (reference 1).

l 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 by monitoring the Auxiliary B;ilding Ventilation Duct.

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

for termination of Containment vents or purges.

2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 COMPLIANCE 8 2.1.1 Dose Rates Due to Noble Gases For implementation of Radiological Effluent Control 8 l 3/4.11.2.1.a. the dose rate to the total body and skin of l an individual at the SITE BOUNDARY due to noble gases ,

released from the site shall be calculated as follows:

l A. Total body dose rate due to noble cases 8 D=IDtv t

v

= I(X/Q) v I K Oy [Eq. 2-1]

(noble gases)

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

Dv=

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

Rev 8

, COMANCHE PEAK - UNITS 1 AND 2 PART II 2-3 01/93 I -. _ __

l

! (X/Q) = the highest annual average relative concentration at the SITE BOUNDARY (3.3 x 10-6 sec/m3 in the NNW sector at a distance of 1,29 miles from the plant *.)

NOTE: The annual average X3 is also used in 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 pCi/m3)

Qjy = the total release rate of noble gas 8 radionuclide i from the release source v (pCi/sec) (See C below for calculation of Qiv) y = index over all release sources 8

,_ B. Skin dose rate due to noble cases I

l D=ID3y 3 = I(X/Q) 1 (Lj + 1.1 Mj) Ojy v v (noble gases) 8 Where: Ds = the skin dose rate at the SITE BOUNDARY due 8 to noble gases from all release sources.

(des /yr)

Dsy= the skin dose rate at the SITE BOUNDARY due 8 l

, to noble gases from release source v.

l (mrem /yr) l

Reference 4, Section 2.3.5.2. 8 Rev 8 COMANCHE PEAK ~- UNITS 1 AND 2 PART II 2-4 01/93 ;

Lj = 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 8 noble gas radionuclide i from Table 2.2 (mrad /yr per pC1/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. Qj is given by:

Q$= 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 (pC1/cm3)

Fy =

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

Qiy = the release rate of radionuclide i from 8 release source v (pCi/sec) y = index over all release sources 8 I

2.1.2 Dose Rates Due to Radiciodines. Tritium. and Particulates 8 l

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

Do=IDay = 3 (X/Q) I Pj Oj v v IP&T [Eq. 2-4]

Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-5 01/93

Where: Do

= 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 due to iodine-131, 8

)

iodine-133, particulates with half-lives i 1

greater than eight days, and tritium from l

release source v (mrem /yr) l 4 Pj = pathway dose rate parameter factor for 8 I

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.

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

All other variable are previously defined.

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

If a calculated setpoint is less than the measured concentration 3 associated with the particular release pathway, no release may 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 01/93 ;

2.2.1 Plant Vent Effluent Release Rate Monitors 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 WRGH low range noble gas activity channel (uC1/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 WRGH effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases. The setpoint for each plant vent effluent release rate monitor will be calculated using the following methodology:

500 X SF = 125 QNG

,Q NG D D

[Eq.2.5]

t t

/

O site = the lesser of Q

" [Eq. 2.6]

NG D s s ;

Where: Qsite = the total site noble gas release rate limit 8 corresponding to a dose rate at the SITE BOUNDARY of 500 mrem /yr to the total body '

or 3000 mres/yr to the skin (uCi/sec)

I QNG = (noble gases) Qt 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)

Rev8 COMAMCHE PEAK - UNITS 1 AND 2 PART II 2-7 OW

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

l (mrem /yr)

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

Then the release rate setpoint for each stack monitor, 8 i

Cf . in uCi/sec is determined as follows:

Cr = Qsite AF [Eq. 2-7]

Where: AF = Allocation Factor of 0.5 applied 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 (WRGM low rance noble cas activity 8 channel) and XRE-5567A/XRE-5567B (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-55678) as a backup for an inoperable WRGM effluent Rev 8 CDMANCHE PEAK - UNITS 1 AND 2 PART 11 2-8 01/93

relcase rato channel whcn no automatic control function is 8 required. The alarm sotpoint for th::se channels, CG in uti/cm3, is determined using the following methodology:

Cf

[Eq. 2-8) ;

8

" 1 CG FPVS i

Where: Fpys = the maximum stack flow rate 8 ;

(cc/sec) correspc. ding to 115,000 !

cfm during normal operations and 130,000 cfm during containment i purges. !

l 4

2.2.3 Samoler Flow Rate Monitors (X-RFT-5570A-1/B-11 8 l l

The WRGMs are designed to sample .isokinetically from the plant vent stacks. Isokinetic sample flow is maintained 8 l automatically by the monitor microprocessor. The sampler !

flow rate monitors are designed such that if there is a ;

loss of sample flow, the stack monitor automatic control i

functions are initiated. The loss of sample flow alarm !

setpoints are established permanently in accordance with '

vendor specifications.

I 2.2.4 Auxiliary Buildino Ventilation Exhaust Monitor (XRE-57011 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 (WGOT) 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. l 1

The alarm setpoint calculation is based on the following i assumption: !

(1) a waste gas decay tank release is the agih batch 8 l release occurring (i.e., a containment purge or vent 1 is not occurring at the same time).

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-9 01M {

i

Based on assumption (1) above, th:re are a maximu] of 8 three release sources that may contribute to the total release rate from the site during a WGDT release. These are the WGDT batch release, the continuous release from Stack A, and the continuous release from Stack B.

Therefore, a release factor of 1/3 will be used for the ABV monitor setpoint determination. The total release rate from the site at the alarm setpoint release rate from each stack would correspond to a value of 2Cf 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 [Eq. 2-9]

2Cf= 2/3 C f Where: Qaux = The limiting release rate 8 contribucion from the Auxiliary Building Vent during WGDT releases

,, (uC1/sec)

Other terms have been previously defined. 8 J

To determine the setpoint, Caux, for the ABV monitor in uCi/cc, the limiting ABV release rate is divided by the 8 maximum ABV flow rate:

Q 2C Caux " F " 3F aux [Eq.2-10]

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

f 2.5 Containment Atmosobere Gaseous Monitors (1RE-5503 and

~

2RE-55031 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 01/93

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

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

These are a Unit 1 Containment release, a Unit 2 Containment release the continuous release from Stack A, and the continuous release from Stack B. Therefore, a release factor of 1/4 will be used for the the containment monitor setpoint determination. The total release rate from the site at the alarm setpoint release rate from each stack would correspond to a value of 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 = 2C f=fC f bW 1 l

Where: Qcont = the limiting release rate 8 contribution from a containment release (uC1/sec) !

Other terms have been previously defined. 8 i

, To determine the setpoint, Ccont, for the containment 8 l monitor in uCi/cc, the limiting containment release rate l 1s divided by the maximum containment release flow rate: j C

cont 2F cont b9'2~12 cont ,

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

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

01/93

i i

i 8 l 1

2.3 DOSE CALCULATIONS FOR GASEOUS EFFLUENTS 8 The methodologies for calculating doses from gaseous effluents 8 l

are given in Sections 2.3.1 and 2.3.2 below. For purposes of demonstrating compliance with the dose limits of Radiological Effluent Controls 3.11.2.2 and 3.11.2.3, the calculated cumulative doses (i.e., the total dose for both units) will be l 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.

l 2.3.1 Dese Due to Noble Gases 8 For implementation of Radiological Effluent Control 8 l 3/4.11.2.2, the cumulative air dose due to noble gases l to areas at and beyond the SITE BOUNDARY will be I calculated at least once per 31 days and a cumulative .

~"

sunnation of the air doses will be maintained for each i calendar quarter and each calendar year. The air dose '

l over the desired time period will be calculated-as '

follows:

A. Air Dose Due to Gamma Emissions 8 I

I Dy = air dose due to ganna emissions from noble gas 8 radionuclides from all release sources (mrad)

D.y = 3.17 x 10-8 (X/Q) (noble gases) N 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 j (uC1)

(Q'i = Qi (uCi/sec) x release duration (sec)) 8 >

. 4 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-12 01/93 l

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

All other variables are previously defined.

B. Air Dose Due to Beta Emissiona 8 Og = air dose due to beta emissions from noble gas 8 l radionuclides (mrad) l D = 3.17 x 10-8 (X/0) (noble gases) Ng Q', [Eq.2-14] 8 3

i Where: Nj = the air dose factor due to beta emissions from 8 noble gas radionuclide i from Table 2.2 l (mrad /yr per uC1/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 K1 for j Mj, (Lj + 1.1 M 1) for N ,t 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 to 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 j individual due to iodine-131, iodine-133, tritium, and particulates with half-lives greater than 8 days will be calculated at least once per 31 days and a cumulative summation of these doses will be maintained for each calendar quarter and each calendar year. The dose over !

the desired period will be calculated as follows:

Dp = pgyss3 17

10' "' IP T R i,a.o i Q'$ [Eq.2-15]

nov s COMANCHE PEAK - UNITS 1 AND 2 PART II 2-13 - -.

l

Wh;re: Dp a dose due to all real pathrays to organ, 0, 8 of an individual in age group, a from iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days from all

release sources (mrem).

W' = the dispersion parameter for estimating the 8 dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum i potential exposures. Locations of interest are listed in Table 2.5, W' = X/Q for the inhalation pathway in sec/m3, X/Q is the annual average relative 8

)

concentration at the location of interest. I Values for X/Q are listed in Table 2.5.

If desired, the highest individual receptor X/Q or X/Q valve may be used, or W' = D/Q for the food and ground plane pathways 8 4

in m-2 0/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/Q or D/Q value may be used. j NOTE: For tritium, the dispersion parameter, W' 8 l

is taken as the annual average X/Q values from Table 2.5 for inhalation, food and ground plane pathways. I RPi ,a.o = dose factor for radionuclide i, 8 pathway p, age group a and organ o, in mrem /yr per UCi/m3 for the inhalation pathway and I m2(mrem /yr) per uC1/sec for food and ground plane pathways, except for tritium which is in mrem /yr per uC1/m3 for all pathways. The I values for RP1 .a o for each pathway, radionuclide, age group and organ are listed in Table 2.4 Rev 8 C0KANCHE PEAK - UNITS 1 AND 2 PART II 2-14 01/93

l The methodologies usGd for determining 8 values of RP 1,a,o for each pathway are given in Appendices B through F.

Q'j = cumulative release of radionuclide, i, 8 during the period of interest (uC1). Q'j is based on the activities measured in each plant vent stack from the analyses of the particulate and iodine samples required by l Radiological Effluent Control 3/4.11.2.1,

! Table 4.11-2.

I !

I&PT = Iodines, particulates with half-lives 8 greater than eight days, and tritium.

These are the isotopes over which the l summation function is to be performed.

. PATHS = The real pathways of exposure to 8 l

l I

individuals at the locations of interest as !

indicated in Tabic 2.5. l 2.4~ DOSE PROJECTIONS 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 GAS HOLDUP SYSTEM be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent from a unit to areas at and beyond the SITE BOUNDARY :

would exceed, in a 31-day period, either:

0.2 mrad to air from gamma radiation; or 8 0.4 mrad to air from beta radiation; or 8 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. 8 The following calculational method is provided for performing 8 this dose projection:

At least once every 31 days the gasuna 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 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-15 01/93 i

i j include the estimated dose due to any anticipated unusual 8 ;

j releases during the period for which the projection is made. such j as Waste Gas Decay Tank release. If the projected doses for a unit exceed any of the values listed above, appropriate portions j of the PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP '

j SYSTEM shall be used to reduce radioactivity levels prior to release. i

! 2.5 DOSE CALCULATIONS TO SUPPORT OTHER REOUIREMENTS 8 i i

5 For the purpose of implementing the requirements of Radiological 8 !

! Effluent Control 6.9.1.4, the Semiannual Radioactive Effluent j Release Report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents from the station i during the previous 6 months of operation. This assessment ,

shall be a summary of the doses determined in accordance with l Section 1.3 for doses due to liquid effluents, Section 2.3.1 for .

j _ air doses due to noble gases, and Section 2.3.2 for doses due to

] iodines, tritium, and particulates. This same report shall also j

) include an assessment of the radiation doses from radioactive '

h liquid and gaseous effluents to members of the public due to r their activities inside the SITE BOUNDARY. This assessment shall be performed in accordance with the methodologies in

] Sections 1.3, 2.3.1, and 2.3.2, using either historical average i or concurrent dispersion and deposition parameters for the locations of interest, and taking into account occupancy factors.

, All assumptions and factors used in the determination shall be included in the report.

i For the purpose of implementing Radiological Effluent Control 8 k 3/4.12.2 dose calculations for the new locations 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 average dispersion parameters may be used for these calculations. If the land use census changes, the

critical location (i.e., the location where an individual would be exposed to the highest dose) must be reevaluated for the

nearest residence, the nearest milk animal, and the nearest Rev 8 2

COMANCHE PEAK - UNITS 1 AND 2 PART II 2-16 01/93

vegetable gard:n. Additionally, wh:n a location is identified 8 that yields a calculated dose 20% greater than at a location l 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.

l For the purpose of implementing Radiological Effluent Control 8 l 3/4.11.4, the total annual dose to any member of the public due l

to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by suming the annual doses l determined for a member of the public in accordance with the methodology of Sections 1.3, 2.3.1, and 2.3.2 and the direct !

l l

radiation dose contributions from the units and from outside l l 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 '

l

. to be submitted 60 days after January 1 of the year after the j assessment was required. Otherwise, no assessments are 8 i required.

For the evaluation of doses to real individuals from liquid 8 releases, the same calculation methods as employed in section 1.3 l 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 (Hj) l to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will i

be made concerning the actual location of real individuals, the meteorological conditions, and the consumption of food. Data '

obtained from the latest land use census should be used to Rev8 l COMANCHE PEAK - UNITS 1 AND 2 PART II 2-17 01/93 .

i f

I determine locations for evaluating doses. The results of the 8

Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations. ,

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

required.

l 2.6 METEOROLOGICAL MODEL 8 2.6.1 Discersion Calculations 8 :

l j _

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

[Eq. 2-16]

f=2.0326K Nr r 3(r)

)

Where- I X/Q = average concentration normalized by source 8 strength (sec/m3),

2.032 = (2/ w )1/2 . (2 w /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 assumed when undepleted X/Q values are to be used in dose calculations.

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

K = terrain correction factor (Figure 2.5) 8 njk = the number of hours meteorological ;

} conditions are observed to be in a given j

, wind direction, wind speed class, k, and atmospheric stability class, j.

j N = total hours of valid meteorological data !

throughout the period of release.

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

r = downwind distance from the release point to 8 :

the location of interest (meters) .

ujk = the average windspeed (midpoint of 8 l windspeed class, k) measured at the 10 ;

meter level during stability class J. l (meters /sec)

Ij(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 calculatin9 Ij(r) is: 8 l

2

'(a j2 + 0.5 b fy)) [Eq.2-17) l (r) j = the lesser of

, /3 a j [Eq. 2-13]

Where:

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

Rev8 COMANCHE PEAK - UNITS 1 AND 2 _

PART II 2-19 __ _

01/93 .

I

I i

0.5 = the building shape factor. 8 b = the vertical height of the reactor 8 4

containment structure (79.4 meters)

}

l 2.6.2 Decosition Calculations 8 .

I l l The relative deposition per unit area is calculated as follows: 8 I l

KDz l

0.392 r [Eq.2-19]

4

{ Where:

! D/Q = deposition per unit area normalized by 8 I

a source strength (m-2) !

Og = relative deposition rate for a ground level 8 !

I release (m-1) (Figure 2.4) !

i z = the fraction of time the wind blows to the 8 i I

i sector of interest.

I

' ~

) NOTE: If hourly meteorological data are used, z is set equal to 8 );

i, one. ,

f 0.3927 = the width in radians of a 22.50 sector. 8 i

Other variables are as previously defined. 8 l

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

i i

l i

)

Rev 8

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

i i

2.7 DEF1 NIT 10NS OF GASEOUS EFFLUENTS PARAMETERS 8 i

l Tgr5 Definition 3

! AF Allocation factor of 0.5 applied to account for releases 8 1

from both stacks simultaneously. This factor will limit

! the release rate contribution from each stack to 1/2 the l limit for the site i i i

i B vertical height of the reactor containment structure i

! l l Cg the alarm setpoint for each plant vent stack noble gas 8 !

l, activity monitor (uC1/cm3) 2

]

i' the alarm setpoint for each plant vent stack effluent f Cf j release rate monitor (uC1/sec) i

) <

1 caux the Auxiliary Building Ventilation Exhaust monitor I

.. alarmsetpoint(uC1/cm3) 4

{ ccont the Containment Atmosphere Gaseous monitor alarm setpoint 8 ,

! (uC1/cm3) ;

Dg relative deposition rate for a ground-level release

}4 (m-1) 1

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

from gaseous release source v (mrem /yr) i Op dose to any organ of an individual from radioiodines, 8

tritium and radionuclides in particulate form with half-i lives greater than eight days from all release sources j (mrem)

Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II_2-21 01/93

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

I Dsy Skin dose rate at the SITE BOUNDARY due to noble 8 l gases from release source v. (mrem /yr) l Dt Total body dose rate at the SITE BOUNDARY due to noble 8 l

gases from all release sources. (mrem /yr) j l

Oyt Total body dose rate at the SITE BOUNDARY due to 8 ;

noble gases from release source v. (mrem /yr) j Dg Air dose due to beta emissions from noble gases from all 8 release sources. (mrad) j l

i D7 Air dose due to gamma emissions f rom noble gases from all 8 I release sources. (mrad) i D/Q Annual average relative deposition at the location of interest. (m-2) 6 Plume depletion factor at distance r for the appropriate stability class (radiciodines and particulates).

8 Fy Flow rate from each release source v. (cm3sec)/ 8 Faux Maximum Auxiliary Building Ventilation flow rate 8 (cm3/ sec) corresponding to 106,400 cfm.

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

Fpys Maximum stack flow rate (cc/sec) corresponding to 8 115,000 cfm during normal operations and 130,000 cfm !

during containment purges.

COMANCriE PEAK UNITS 1 AND 2 PART II 2-22 Rev. 8 .

ERRATA (6/93) 1 ... -. . . . - .. -. ._ . -_ ---

l h Definition l

K terrain recirculation factor (Unitiess) 8 Kj total body dose factor due to gaisna emissions from noble 8 gas radienuclide 1 ( d en/yr per uC1/m3)

Lj skir dose factor due to beta emissions from noble gas 8 l

radionuclide 1 ( d em/yr per uC1/m3)

Mj air dose factor due to gamma emissions from noble gas 8 radionuclide 1 (d em/yr per uC1/m3) l Nj air dose factor due to beta emissions from noble gas 8 radionuclide 1 (d em/yr per uC1/m3) l l l number of hours meteorological conditions are observed l njk 8 l to be in a given wind direction, wind speed c16ss k, and atmospheric stability class j N total hours of valid meteorological data 8 l l Pi pathway dose rate parameter for radionuclide 1 (other 8 than noble gases) for the inhalation pathway (d em/yr per uC1/cm3)

Qaux the limiting release rate contribution from the 8 l l Auxiliary Building Vent during WGDT releases (uC1/sec)

)

Qcont the limiting release rate contribution from a containment 8 release (uC1/sec)

Qj total release rate of radionuclide i from all release 8 sources (uC1/sec) i Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-23 W93 l

l IEE Definition Qjy the total releaso rate of radionuclide i from.relcase 8 source v (uC1/sec)

Q'i cumulative release of radionuclide i during the period 8 of interest from all release sources (uC1)

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 4.11-2 l QSITE the total site noble gas release rate limit corresponding 8 to a dose rate et the SITE BOUNDARY of 500 mrem /yr to the total body or 3000 mrem /yr to the skin (uC1/sec) l I

Rpi,a.o dose factor for radionuclide 1, pathway p, and age group 8 a, and organ o (mrem /yr per uC1/m3) or (m2. mrem /yr per I

,. uC1/sec) r distance from the point of release to the location of 8 ;

interest for dispersion calculations (meters)

SF Safety Factor of 0.5 applied to compensate 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 dev ation of the plume concentration (in 8 meters), at distance, r, for stability category j ujk wind speed (midpoint of windspeed class k) at ground 8 level (m/sec) during atmosphere stability class j Rev8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-24 01/93

Igr3 Definition W' the dispersion parameter for estimating the dose to an 8 individual at the location where the combination of existing pathways and receptor age groups indicates the

! maximum exposures X/Q the annual average relative concentration at the location 8 of interest (sec/m3) 1 -

l X/Q the hightest annual average relative concentration at the 8 SITE BOUNDARY (sec/m3) (3.3 x 10-6 sec/m3 in the NNW sector) j Xiy the measured concentration of radionuclide i present ,

i in each release source v (uC1/cm3) i l z the fraction of time the wind blows to the sector of 8 !

interest ;

i l 1.1 conversion factor of mRes 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 l l sources (mrem /yr)

, 3000 the dose rate limit to the skin of the body of the 8 1

) 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 2-25 01/93 ;

l

n h TABLE 2.1 l8 m

SUMMARY

OF GASEOUS RELEASE PATHWAYS l8 A

^ 1. RELEASES VIA THE PLANT VENT STACKS 8 E

~

--4

" RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfa) MONITOR (S) 8 E Stack A Continuous 115.000 XRE-5570A/XRE-5567A 8 Stack B Continuous 115.000 XRE-55708/XRE-5567B 8

^2 WGDT's Batch 20 XRE-5570A48/XRE-5701 8 U-1 Cont. Vent. Batch 750 1RE-5503 8 U-2 Cont. Purge Batch 30.000 1RE-5503 8 U-2 Cont. Vent. Batch 750 2RE-5503 8 U-2 Cont. Purge Batch 30.000 2RE-5503 8 5

5

2. RELEASES VIA THE ILRT VENT

, 8

'?

$ RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfs) MONITOR (S) l8 ILRT Batch - -

8 EE g .<

W.

3 3

3

i i

I f i i j TABLE 2.2 8

{

F

] DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES

i l Isotone T-Bod v***( K ) S-Skin ***(L) Y-Air **(M) B-Air **(N) l i Kr-83m 7.56E-02 ---

1.93E+01 2.88E+02 :

l Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03

Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 j Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04

! Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 !

Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 !

i Kr-90 1.56E+04 7.29E+03 1.63E+04 7.03E+03 j Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 j Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 i Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 i Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 l Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 i

a Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 ;

i Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 I 1

I l

Values taken from Reference 2. Table B-1 i

i ** 1 mrad-m3 j uti-yr

. \

j *** g 4 uti-yr l

l 4

4 Rev 8 COMANCHE PEAK - UNITS 1 AND 2 PART II 2-27 01/93 e

+ - - ,, - - ,.-w-~y-,.,-.c - , , , ca . . - -, . - - - , , . , - - , . . _ ,, , - . , + , , . . , , , , ,+.se,,, . , , - , ,

4 J

j 4

TABLE 2.3 PATHVAY DOSE RATE PARAMETER (Pi)*

BASED ON THE INHAIATION PATHWAY

, FOR THE CHILD AGE CROUP i ................................................................................ ,

l ORGAN DOSE FACTORS !

NUCLIDE l.----------.----...-.....-.-....-.-------..... ..--.-..-........-.... ;

, l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI I

................................................................................ l 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 H.3 0.00E+00 1.12E+03 i

l P-32 2.60E+06 1.14E+05 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04

................................................................................ i 5 CR.51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 2 MN.54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 I FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03

, ................................................................................ l FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 l

, CO.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 l 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 0.00E40 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 !

I RB.86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 i ................................................................................

5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 i SR-89 SR.90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 j Y.01 9.14E+05 0.00E40 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 2 ................................................................................

ZR.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 l NB.95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 l RU.103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 j ................................................................................

RU.106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 4 AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1,00E+05 l TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 l ................................................................................

l TE.127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04

TE.129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 i 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 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 1.28E4 5 0.00E40 2.82E+05 1.04E+05 3.62E+03 5A.140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E41 1.74E+06 1.02E+05 i CE.141 3.92E+04 1.95E+04 2.90E43 0.00E+00 8.55E+03 5.44E+05 5.66E+04 j ................................................................................

i CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 ;

l PR-143 1.85E+04 5.55E+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

.............................................................m.-..=..........-.-

COMANCFE PEAK - t.NTS 1 APO 2 PART I 2 28 Rev 8

) 01/93

_ _ _ _ _ _ . _ .-= _ ,

I i

TABLE 2.4 PATH' JAY DOSE FACTORS AGE CROUP: ALL PATH' JAY: GROUND PLANE l ORGAN DOSE FACTORS j NUCL1DE l--------------------- l' l T. BODY SKIN H-3 0.00E+00 0.00E+00 P-32 0.00'E+00 0.00E+00 CR-51 4.65E+06 5.50E+06 i MN.54 1.39E+09 1.62E+09 I FE-55 0.00E+00 0.00E+00 l

............................... I FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 i CO-60 2.15E+10 2.53E+10 l NI-63 0.00E+00 0.00E+00 l ZN-65 7.47E+08 8.59E+08 RB-86 8.97E+06 1.03E+07 l

i SR 89 2.16E+04 2.51E+04 !

SR-90 0.00E+00 0.00E+00 Y-91 1.07E+06 1.21E+06 ZR-95 2.45E+08 2.84E+08 NB-95 1.37E+08 1.61E+08 KU.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 i

CS-136 1.51E+08 1.71E+08 CS-137 1.03E+10 1.20E+10 BA-140 2.06E+07 2.36E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07 8.05E+07 PR-143 0.00E+00 0.00E+00 ND-147 8.39E+06 1.01E+07 1

Rev 8 1 COMANCE PEAK - UMTS 1 APO 2 01/93 PART I 2-29

i l

TABLE 2.4 PATHVAY DOSE FACTORS AGE GROUP: ADULT PATHVAY: GRASS-COV-MI1X l ORGAN DOSE FACTORS NUCLIDE 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 6.58E+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. 66 E406 9. 93 E446 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 1.05E+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 I 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+08 SR-90 4.67E+10 0.00E+00 1.15E<10 0.00E+00 0.00E+00 0.00E+00 1.35E-09 Y.91 8.57E+03 0.00E+00 2.29E+02 0.00E+00 0.00E+00 0.00E+00 4.72E+06 l ZR-95 9.41E+02 3.02E+02 5.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 NB.95 8.24E+04 4.58E+04 4 . .,6 E+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 RU-106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.93E+04 0.00E+00 1.32E+06 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 1.63E+07 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+0B l TE.129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 3.02E+08 I I.131 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.00E+00 1.12E+08 l

.............................................................................. l l 1 133 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 l 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 l 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 l CE.144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21E+08 l 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 1 ..............................................................................

1 COMANCE PEAK - UMTS 1 APO 2 Rev 8 PART I 2-30 01/93

)

TABilE 2.4 !

PATHWAY DOSE FACTORS I 1

AGE GROUP: TEEN PATHVAY: GRASS-COV-MIII

[ ORGAN DOSE FACTORS

NUCLIDE l---------------------------------------------------------------------

1 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 a ..............................................................................

! CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 l' 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 1.37E+07 j ..............................................................................

! 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 )

0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08

~

CO.60 j ..............................................................................

NI-63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 i ZN.65. 2.11E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 ,

1 RS-86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08 '

1

! SR-89 2.68E+09 0.00E+00 7.67E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 SR-90 6.62E+10 0. 00E+' ' 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 l i Y.91 1.58E+04 0. 00 E+ 0^s 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 I l

j ZR-95 1.65E+03 5.21E+02 3.58E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+06 l

] NB.95 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 )

j RU.103 1.81E+03 0.00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51E+05 l 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 1 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

I-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 i 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&O8 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 3.14E+06 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 bhkkb h b9k hh 2$7hk hh h$h hIhk h hhk hh [ hhk hh h$hhk hh k khb+b8 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 Rev 8 COMANCE PEAK - UMTS 1 APO 2 PART I 2 31 01/93 i

i i

4 1

I i

i TABLE 2.4 PATHWAY DOSE FACTORS ;

AGE CROUP: CHILD PATHWAY: CRASS-COV-MI1X

] l ORGAN DOSE FACTORS NUCLIDE l---------------------------------------------------------------------

i a l BONE LIVER T. BODY THYROID KIDNEY LUNG CI-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

~ ~~ ~~ " '

Ck55 b$bbk$bb'~b$bbkIbb"i$b2kSb5 5$55kI65"i$5dkE65"~i$b35Ab5 5$Ebi MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E40 5.89E+06 0.00E+00 1.76E+07 TE-55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 4 ..............................................................................

FE-59 1.20E+08 1.95E+08 9.70E+07 0.00E40 0.00E40 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+08 '

NI.63 2.97E+10 1.59E+09 1.01E+09 0.00E40 0.00E+00 0.00E+00 1.07E+08 .

ZN.65 . 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94E+09 j RB.86 0.00E+00 8.78E+09 5.40E+09 0.00E+00 0.00E+00 0.00E+00 5.65E+08 SR.89 6.63E+09 0.00E+00 1.89E+08 0.00E40 0.00E+00 0.00E@0 2.57E+08 SR-90 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E+00 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 8.80E+05 NB-95 3.18E+05 1.24E+05 8.86E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+0B 4

RU-103 4.29E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 0.00E+00 1.11E*05

.............................................................................. l

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+0B I.131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 l

.............................................................................. I I-133 1.72E47 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 I'

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 bh$kkh b$5bk kb b$bhk [b $bhk bh b$bbk Ob k$bik kb b$hhk bh k$hbb bh BA.140 1.18E44 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 44 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 3.56E4 1 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 w

COMANCE PEAK - UMTS 1 AfC 2 Rev 8 PART I 2-32 01/93 i

I TABLE 2.4 PATHWAY DOSE FACTORS i

AGE GROUP: INFANT PATHWAY: GRASS. COW-MILK l j ORGAN DOSE FACTORS NuCLIDE l------------------------------------------------ ----------~~---- --

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 P-32 1.60E+11 9.42E+09 6.21E+09 0.00E+00 0.00E+00 0.00E+00 2.17E+09 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 6.05E+07 CO.60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 !

.............................................................................. l NI-63 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.08E+08 ZN-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 2.59E+08 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 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 ZR.95 6.81E+03 1.66E+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 AG.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+08 1.39E+09 0.00E+00 3.33E+08 I-131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+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 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 COMANCE PEAK - UMTS 1 APO 2 Rev 8 PART I 2-33 01/93

J I

?

1 i TABLE 2.4 I l PATHWAY DOSE EACTORS I AGE CROUP: ADULT PATHWAY: GRASS. COW. MEAT I 1

I ORGAN DOSE FACTORS I

NUCLIDE l............--........-..-.........-...........................-.....

l l l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI 1 .............................................................................. ;

i H.3 0.00E+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 <

i l

} P-32 4.63E+09 2.88E+08 1.79E+08 0.00E+00 0.00E+00 0.00E+00 5.21E+08 I

.............................................................................. l t CR.51 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 I I MN.54 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 I i FE.55 2.93E+08 2.03E+08 4.73E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 l

, .............................................................................. l FE-59 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 4

CO.58 0.00E+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.70E+08 i 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 i ZN.65:- 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08

! R3 86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.59E+07 4, ..............................................................................

SR.89 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 l SR-90 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08 Y.91 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 1

IR.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 l l 9.U.106 2.80E+09 0.00E+00 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11

AC.110M 6.68E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09

TE-125M 3.592+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

1 131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 I.133 3.68E.01 6.41E.01 1.95E.01 9.42E+01 1.12E+00 0.00E+00 5.76E.01 CS.134 6.58E+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 3.44E+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 1.24E+04 2.08E+04 5.96E+07

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 COMANCE PEAK - UNITS 1 APO 2 Rev8 PWJTT I 2-34 01 93

i !

i i

l 1

i i

TABLE 2L4 '

PATHWAY DOSE FACTORS 4

ACE GROUP: TEEN PATHEAY: CRASS-COW-MEAT !

. t 3

1 l ORGAN DOSE FACTORS l NUCLIDE l.----.----.------------.-.--- l l BONE LIVER T. BODY THYROID KIDNEY LUNG CI-LLI l i

H-3 ;

0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02

~

l i

f P-32 3.91E+09 2.^2E+08 1.52E+08 0.00E+00 0.00E+00 0.00E+00 3.29E+08 l 4

CR.51

MN-54 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 i

FE.55 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 i 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+08 7.31E+07 i

{

i FE.59 l CO-58 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00. 1.56E+08 1.17E+09 .j 1

CO-60 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+08 1 4

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 4

RB.86 2.50E+08 8.68E+08 4.05E+08 .0.00E+00 5.56E+08 0.00E+00 3.68E+08 O.00E+00 4.06E+08 1.91E+08 0.00E+00 'O.00E+00 0.00E+00 6.00E+07 j

i ..............................................................................

SR.89 SR-90 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07

! Y.91 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 9.54E+05 0.00E+00 2.56E+04 0.00E+00 0.00E+00 0.00E+00 3.91E+08 l

ZR.95 j NS-95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 i RU.103 1.79E+06 9.95E+05 5.48E+05 0.00E+00 9.64E+05 0.00E+00 4.25E+09 8.56E+07 0.00E+00 3.66E+07 0.00E+00 3.02E+08 0.00E+00 7.15E+09 j ..............................................................................

KU.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+00 0.00E+00 8.94E+08 3

3 TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 0.00E+00 2.35E+09 i TE-129M I.131 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 8.93E+46 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 I ,

i I.133 3.04E.01 5.22E.01 1.59E.01 7.29E+01 9.16E-01 0.00E+00 3.95E.01 1 CS.134 CS.136 5.23E+48 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 j CS-137 7.24E+08 9.63E+08 3.35E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07

) &A.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+45 0.00E+00 3.09E+08 j PR-143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 5.79E+07 4 ND-147 6.23E+03 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 4 .......................................................................---.---

j -

1 2 Rev8 4 PART I 2-35 01/93 3

I

i i

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS. COW-MEAT l ORGAN DOSE FACTORS 1 NUCLIDE l.---- ---------------------------- ------------ --- ----------...--- 1 l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.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 3.45E+08 2.85E+08 0.00E+00 0.00E+00 0.00E+00 2.04E+08 l CR.51 0.00E+00 0.00E+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 .

MN.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 l CO.58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 i 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 i ZN.65 - 3.76E+08 1.00E+09 6.22E+08 0.00E+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 :

...................................................... 4......................

i SR-89 4.82E+08 0.00E+00 1.38E+07 -0.00E+00 0.00E+00 0.00E+00 1.87E+07 l 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+08 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 5.96dM7 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 0.00E+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 i 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 l CS-134 9.23E+08 1.51Ed9 3.19E+08 0.00E+00* 4.69E+08 1.68E+08 8.16E+06 CS.136 1.63EM7 4.48E+07 2.90E+07 0.00E+00 2.39E+07 3.56E+06 1.UUO6 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 1.00E44 1.65E+03 0.00E+00 5.42E43 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 Rev 8 COMANCW PEAK . UMTS 1 APO 2 PART I 2-36 01/93 J

I i

l l

l i

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT l ORGAN 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 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-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 l NI-63 0.00E+00 0.00E+00 0.00E+00 0. 00E+00 0.00E+00 0.00E+00 0.00E+00 l ZN. 6 5 . . 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l RB-86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t

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 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 0.00E+00 0.00E+00 0.00E+00 0.00E40 0.00E+00 0.00E+00 0.00E+00 AC-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 0.00E40 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 0.00E40 0.00E+00 0.00E+00 I.131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 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.140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 0.00E40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-144 0.00E600 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 0.00F+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rev 8 COMANCE PEAK . LNTS 1 APO 2 PART I 2-37 01/93

TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: 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+00 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 KN-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 l FE.59 3.87E+05 9.09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 l

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 l ..............................................................................

l NI-63 8.08E+08 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E+07 ZN. 6 5 . . 1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.51E+08 0.00E+00 3.30E+08 R5-86 0.00E+00 3.12E+08 1.45E+08 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 0.00E+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 0.00E+00 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.59E+05 19 110M 6.99E+06 6.47E+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE-i?5M 1.96E+06 7.09E+05 2.62E+05 5.89E+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.131 3.56E+08 5.09E+08 2.92E+08 1.67E+11 8.73E+08 0.00E+00 1.34E+08 I.133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41E+07 0.00E+00 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 6.67E+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 1.80E+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+04 ND.147 1.13E+01 1.31E+01 7.82E.01 0.00E+00 7.65E+00 0.00E+00 6.28E+04 Fhev 8 COMANCE PEAK . UMTS 1 AhD 2 PART I 2-38 01/93

4 I i

TABLE 2.4 1

PATHVAY DOSE FACTORS

l AGE GROUP: TEEN i

PATHWAY: CRASS-GOAT MILX i

l i NUCLIDE l---------------------- ----- ORCAN DOSE FACTORS j

l BONE LIVER T. BODY j THYROID K

....................................................IDNEY LUNC GI-LLI ,

j H.3 .......................... I 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+0

, P-32 j 3.78E+10 2.34E+09 1.46E+09 0.00E+00 0.0

................................................... 0E+00 0.00E+00 CR-51 ..........................

3.18E+09 i MN.54 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+ '

l i

FE-55 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+

5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.00

.....................................................E+00 FE.59 .........................

2.61E+05 1.78E+05 i

4 CO.58 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+

CO.60 0.00E+003.9.53E+05 0.00E+00 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+

34 E+06 7.52E+06 0.00E+00 :

$ ................................................ 0.00E+00 NI.63 0.00E+00 4.35E+07 i

ZN.65 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.60E+ :

1 R3 8 6, _ 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0 0.00E+00 5.62E+08 0.00E+00 3.72E+

.................................................. 00E+00 0.00E+00 8.40E+07 l l SR-89 ........................... \'

SR.90 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+

Y-91 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+

1.90E+03 0.00E+00 5.09E+01 0.00E+0

............................................. 0................................

ZR-95 0.00E+00 0.00E+00 7.78E+05 NB.95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E RU.103 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+

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 5.68E+02 0.00E+00 8.69E+03 0.00E+00 2.16E+

i AG.110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3 TE.125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 i

}

................................................. 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 2.52 i

TE.129M I-131 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1 0.00E+00 1.79E+08 1-133 56E+09 ...........................

CS.134 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 CS.136 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2. 89E+09 4.55E+08 4.27E+08

...............s..................................

CS.137 ...........................

BA-140 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07E+09 7.60E+08 CE-141 5.84E+06 7.16E+03 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+06 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 2.04E+06

.......................................................... 0.00E+00 CE.144 ...................

PR.143 7. 90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00. 1.99E+07 ND.147 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 2.18E+01 2.37E+01 1.42E+00 0.00E+00 1.39E+01 0 8.54E+04

............................................................ 00E+00 ...-..-----------

Rev 8 COMANCE PEAK - UMTS 1 AbD 2 PART I 2-39 i

l I

l l

I TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: CRASS. COAT MIIX l ORGAN 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+0i 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 0.00E+00 2.52E+0 6.71E+05 0.00E+00 7.06E+05 0.00E+00 2.11E+06 FE-55 1.45E+06 7.71E+0. 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+06 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 NI-63 3.56E+09 1.91E+08 1.21E+C8 0.00E+00 0.00E+00 0.00E+00 1.28E+07 l ZN.65 - 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E+08 '

RS-86 0.00E+00 1.05E+09 6.47E+C8 0.00E+00 0.00E+00 0.00E+00 6.77E+07 l ..............................................................................

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 3.16E+09 ,

Y-91 4.69E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.24E+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 1.29E+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+C6 2.40E+06 1.18E+06 2.49E+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 I-131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.00E+00 1.40E+08 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07 CS.134 6.80E+10 1.12E+11 2.35E+10 0.00E+00 3.46E+10 1.24E+10 6.01E+08 CS.136 3.04E+09 8.36E+09 5.41E+09 0.00E+00 4.45E+09 6.64E+08 2.94E+08 CS.137 9.68E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA.140 1.41E+07 1.24E+04 8.23E+05 0.00E+00 4.02E+03 7.37E+03 7.15E+06 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 5.34Edil 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 Rev 8 COMANCIE PEAK . UMTS 1 APO 2 PART I 2-40 01/93

l l

l i

l TABLE 2.4 PATHWAY DOSE FACTORS AGE CROUP: INFANT PATHWAY: GRASS-GOAT-MILK l ORGAN DOSE FACTORS NUCLIDE I..--..------- ---------------------------- -----------.------------.-

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI 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 2.60E+09 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. 72 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 2.92E+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 l 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 l R3 86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 SR.89 2.65E+10 0.00E+00 7.59E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+08 l SR-90 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 I

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 3.27t+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 I.133 4.36E+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

.............................................................................. j CS.137 1.54E+11 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 BA-140 2.90E+07 2.90E+04 1.50E+06 0.00E+00 6.89E+03 1.78E+04 7.13E+06 l 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 0.00E+00 1.60E+07 PR-143 1.78E+02 6.66E+01 8.83E+00 0.00E+00 2.48E+01 0.00E+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6 89E+04 Rev 8 COMANCE PEAK - UMTS 1 APO 2 01/93 ,

PAFTT I 2-41 l

1 l

+ 1 i

1 1

TABLE 2.4 l PATHWAY DOSE FACTORS I l !

. 1 AGE GROUP: ADULT PATHVAY: VEGETATION I l

l ORGAN DOSE FACTORS l NUCL1DE l-..........-.....---.--..--......--..-............................... l l BONE LIVER T. BODY THYKOID KIDNEY LUNG GI-LLI !

.............................................................................. l H.3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 i i P.32 1.40E+09 8.69E+07 5.40E+07 0.00E+00 0.00E+00 0.00E+00 1.57E+08 j ..............................................................................

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 i FE-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 I FE-59 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 CO.58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 J

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 6.75E+08 0.00E+00 6.36E+08 RB.86 0.00E+00 2.19E+08 1.021:+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 i i,

j 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 0.00E40 0.00E+00 1.75E+10 j 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+00 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 0.00E+00 1.82E47 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 1.25E+10 AG.110M 1.05E+07 9.75E+06 5.79E+06 0.00E40 1.92E+07 0.00E+00 3.98E+09 1

TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 T **c 127M 3.49E48 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 8.08E+07 1.16 E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07

! I.133 2.09E46 3.63E+06 1.11E+C6 5.34E+08 6.33E+06 0.00E+00 3.26E+06 J CS.134 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 CS.136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41E+07 1.29E+07 1.92E+07 CS.137 6.36E+09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+0B 4 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 CE.144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+10 PR-143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08 I ND-147 3.34E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 Rev8 COMANCFE PEAK - LNTS 1 AiO 2 PART I 2-42 01/93

i i

r i

i i

TABLE 2.4 PATH' JAY DOSE FACTORS AGE CROUP: TEEN PATH' JAY: VECETATION l ORGAN DOSE FA NUC LI D E l . . . . . . . . . . . . . . . . . - . - . . . . . . . . . . . .-......-...................

. . . . . . . . . . CTORS \

l BONE LIVER T. BODY THYROID KIDNEY LUNG G

........................................................................I-LL1 H-3 ......

0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 P.32 1.60E+09 9.91E+07 6.20E+07 0.00E+00 0.00E+00 0.00E+00 1.34

.........................................................................E+08 CR-51 MN-54 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 ,

FE-55 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+0B 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08

.................................................................... 1.00E+08 FE-59 .........

CO-58 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+0B 9.91E+0B CO.60 0.00E+00 4.36E+07 1.01E+08 0.00E+00 0.00E+C0 0.00E+00 6.01E+0B 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+0 3.24E+09

................................................................. 0 NI-63 ............

ZN.65 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 RB.86 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 0.00E+00 2.73E+08 1.28E+08 0.00E+00 0.00E+00 0.00 4.04E+07

...............................................................E+00 SR-89 ...............

SR.90 1.52E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 Y-91 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 '

7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0 3.22E+09

............................................................ 00E+00 ZR-95 .................

i NB.95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 RU.103 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 5.70E+08 RU.106 0.00E+00 ...................

I 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 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 4.37E+08

.......................................................... 0.00E+00 ...................

i TE.127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE.129M 1 131 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 !

7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00 2.13E+07

...............................................................E+00 I.133 ...............

CS.134 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS.136 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.0BE+0B 4.39E+07 1.73E+08 1.16E+08 0.00E+00 9.41E+07 1.48 1.39E+07

...............................................................E+07 CS.137 ...............

BA.140 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 CE.141 1.39E+08 1.71E+05 8.97E+06 0.00E+00 5.78E+04 1.15E+05 2.15E+08 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5

...................................................................... 41E+08 CE-144 PR-143 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 ND-147 6.99E+04 2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 Rev 8 COMANCE PEAK . UMTS 1 AND 2 PART I 2-43 m3 i

i l

TABLE 2.4 PATWAY DOSE TACTORS AGE GROUP: CHILD PATWAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE l-------------------------------------- ------------------------------

l BONE LIVER T. BODY THYROID KIDNEY LL'NG GI-LLI H.3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 P-32 3.35E+09 1.57E+08 1.29E+08 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+0B 1.77E+38 0.00E+00 1.86E+08 0.00E+00 5.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 0.00E+00 0.00E+00 2.40E+08 7.87E+07 l FE.59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+0B l 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 l

j ..............................................................................

l NI-63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 l l

ZN. 64 . 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 j RB-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 l SR-90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 t Y-91 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 ZR-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 B.85E+08 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 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2.58E+09 TE-125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+0B l 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 1.2BE+07 I l ..............................................................................

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 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 CS-136 ,8.28E+07 2.28E+08 1.47E+08 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 Rev 8 COMANCE PEAK - UMTS 1 APO 2 PART I 2 44 01/93 l - - - -

l i I

I l !

TAEMJE 2.4 -

1 PATHWAY DOSE FACTORS i

l ACE GROUP: INFANT PATHWAY: VECETATION I l ORGAN DOSE FACTORS l NCCLIDE l--.-.-------------- --------------------.-------------------- ----... i l BONE LIVER T. BODY THYROID KIDNEY LUNG CI.LLI l

b$3~b$bbbbb'~b$bbbbb'~b$bbbbbb$bbbbb"b$bbbbb'~b[bbbbbb[bbbIbb' l t

1 .

l P.32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '

l l CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i MN-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t FE.55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 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 i ZN-65 . ,- 0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l RB-86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;

I 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+CO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i NB.95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

.. ... I .. I ..I .. . .. . .. I .. .' .

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 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

.............................................................................. j I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I CS-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j CS.136 0.00E+00 0.00E40 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-140 0.00E+00 0.00E+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 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 Rev 8 COMANCFE PEAK - UNTS 1 AND 2 PART I 2-45 01/93 1

l l

l i

i l

TABLE 2.4 )

l l PATHVAY DOSE EACTORS AGE GROUP: ADULT PATHVAY: INHALATION i l ORGAN DOSE FACTORS NUCLIDE l........-----.----.---------------- -- --.-----------------------.--- l l BONE LIVER T. BODY THYROID KIDNEY LUNG 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 !

MN.54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 !

FE-SS 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 l

............................................................................... i FE.59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 i 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 NI.63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 1.34E+04 i 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 1.66E+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+00 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 5.0$E+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 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE.125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE.127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE.129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 1-133 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 2.1BE+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

i

$ TABLE 2.4 PATHVAY DOSE FACTORS 1

AGE GROUP: TEEN PATHVAY: INHA1ATION

} l ORGAN DOSE FACTORS 1

NUCLIDE l..--..--------.--~ ~ -~. ~-~.------....-..---.....-......~.~ ..

3 l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI j

l H.3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 l j P.32 i 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.2SE+04 CR-51 i MN.54 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 FE.55 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E40 1.24E+05 6.39E+03 FE-59 I

CO-58 1.59E44 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 CO.60 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 l

NI-63 j ZN-65 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04

RS.&6 - 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 i ...............................................................................

SR-89

] SR.90 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 Y.91 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 4

6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09

' ..........................................................................E+05 ZR-95

! NB.95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05

) RU.103 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09

..........................................................................E+05 RU.106 AG.110M 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.60E+05 TE.125M 1.38E+04 1.31E+04 7.99EM3 0.00E+00 2.50E+04 6.75E+06 2.73E+05 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE.127M TE-129M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 I.131 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 j ...............................................................................

I-133 CS.134 1.22E+04 2.05E+04 6.22E+03 2.92EM6 3.59E+04 0.00E+00 1.03E+04 CS.136 5.02E+05 1.13E+06 5.49E45 0.00E+00 3.75E+05 1.46E+05 9.76E+03 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS.137 BA-140 6.70E+05 8.48E45 3.11E45 0.00E+00 3.04E+05 1.21E+05 8.48E+03 CE-141 5.47E+04 6.70E+01 3.52E43 0.00E+00 2.28E+01 2.03E+06 2.29E+05 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+O6 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 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 Rev 8 COMANCE PEAK . LNTS 1 APO 2 PART I 2-47

7 TABLE 2.4 PATWAY DOSE FACTORS AGE GROUP: CHILD PATWA

.............................................Y:..................................

l INHA1ATION NUCLIDE ORGAN DOSE EACTORS l.........---...--....----... ,

l BONE LIVER T. BODY T

KIDNEY

..........................................HYROID H.3 LUNG GI.LLI 0.00E+00 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 0.0

.......................................... 0E+00 CR-51 0.00E+00 0.00E+00 4.22E+04 0.00E+00 0.00E+00 KN-54 1. 54 E+02 8.55E+01 2.43E+01 1.70E+04 1.085+03 FE-55 0.00E+00 4.74E+04 4.29E+04 2.52E+04 9.51E+03 7.77E+03 0.00E+ 0.00E+00 1.00E+04 1.58E+06 2

............................................. 00 FE-59 0.00E+00 1.11E+05 2.87E+03 CO-58 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 CO-60 0.00E+00 1.77E+03 0.00E+00 1.31E+04 3.16E+03 2.26E+04 0.0 0.00E+00 0.00E+00 1.11E+06

.......................................... 0E+00 NI.63 0.00E+00 7.07E+06 9.62E+04 ZN.65 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+0 RB.86 4.26E+04 1.13E+05 0.00E+00 1.98E+05 7.03E+04 1.14E+05 0 0.00E+00 7.14E+04 9.95E+05

......................................... 00E+00 SR.89 0.00E+00 0.00E+00 7.99E+03 SR.90 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 Y.91 1.01E+08 9.14E+05 0.00E+00 0.00E+00 2.44E+04 6.44E+06 0.00E+00 0.00E+00 1.48E+0

....................................... 0.00E+00 ZR.95 0.00E+00 2.63E+06 1.84E+05 NB-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+0 RU.103 2.35E+04 9.18E+03 2.79E+03 0.00E+00 1.07E+0 6.55E+03 0.00E+00 8.62E+03 6.14E+0 RU.106 0.00E+00 7.03E+03 6.62E+05 4.48 3.....................................E+04 .....

AG.110M 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1,P4E+05 1.43E+07 4.29E+05 TE-125M 1.69E+04 6.73E+03 1.14E+04 2.33E+03 9.14E+029.14E+03 0.00E+00 2.12E+04 5.48E+06

....................................... 1.92E+03 TE.127M 0.00E+00 4.77E+05 3.38E+04 TE.129M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.1 I-131 1.92E+04 6.85E+03 4.81E+04 4.81E+04 3.04E+03 2.73E+04 1.6 6.33E+03 5.03E+04 1.76E+06 1

.......................................... 2E+07 I.133 7.88E+04 0.00E+00 2.84E+03 CS.134 1.66t+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00EF00 5.48 CS.136 6.51E+05 1.01E+06 6.51E+04 1.71E+05 2.25E+05 1.16E+05 0.00 0.00E+00 3.30E+05 1.21E+05 3.8

............................................E+00 CS-137 9.55E+04 1.45E+04 4.18E+03 BA.140 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62 CE.141 7.40E+04 6.48E+01 3.92E+04 1.95E+04 4.33E+03 2.90E+03 0.00 0.00E+00 2.11E+01 1.74E+06 1.02E

............................................E+00 CE.144 8.55E+03 5.44E+05 5.66E+04 PR-143 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+0 ND.147 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 1.08E+04 8.73E+03 6.81E+02 0.00E+0 4.81E+03 3.28E+05 6.21E+04

.............................................. 0.........................-....--

COMANCE PEAK - LNTS 1 APO 2 -

Rev 8

, PART I 2-48 01/93

,a

1 I

TABLE 2.4 PATHVAY DOSE FACTORS l j

ACE CROUP: INFANT PATHVAY: INHAIATION l ORGAN DOSE TA sect 10t l..........................................CTORS ...........................

l BONE LIVER 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 ' 61E+04 :

CR 51 MN.54 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3 W +02 FE.55 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+v2 ,

1. 97E44 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09

..........................................................................E+03 FE.59 .....

{

CO-58 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 Co.60 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 0.00E40 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06

..................................................................... 3.19E+04 NI.63 .......

1 ZN 65 3.39E+05 2.04E44 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 R3 8 6, _

1.93E404 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E45 5.14E+04 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00

..................................................................... 3.04E+03 5R.89 .........

SR.90 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 i

Y.91 4.09E+07 0.00E+00 2.59t+06 0.00E+00 0.00E+00 1.12E+07 1 31E+05 5.88E45 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+0 7.03E+04 i

.................................................................. 6 ZR.95 ............

NB.95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 RU 103 1.57E+04 6.43E+03 2.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E45

..................................................................... 1.61E+04 RU.106 AC.110M 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 TE.125M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 4.76t+03 1.99E+03 6.58E+02 1.62E+03 0.00E40 4.47E+05 1.29E+04 TE.127M TE.129M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 4

1 131 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18t+04 1.68E+06 6.90E+04 3.79E+04 4.44E+04 1.96E+04 1.48t+07 5.18E+04 0.00E+00 1.06E+03 1

I-133 i CS.134 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 C5 136 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18t+04 1.43E+03

...............s...............................................................

CS.137 AA 140 5.49E+05 6.12E+05 4.55E44 0.00E+00 1.72E+05 7.13E+04 1.33E+03 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E46 3.84E+04 CE.141 2.77t+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17t+05 2.16E+04 CE-144 F1-143 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38t+05 9.84E+06 1.48E+05 ND.147 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97t+03 4.33E+05 3.72E+04 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E43 3.22E+05 3.12E+04 l

Rev 8 COMANCFE PEAK . t.NTS 1 AND 2 PART I 2-49 01/93

I l i TABLE 2.5 8 !

l (Sheet 1 of 2) j 1

l CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1), AND 5- I ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS .

j REQUIRED 8Y RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) l l '

l '

j Pathway Distance X/Q D/Q 5 l

{ Sector (Note 2) (Miles) (Notes 3. 4) (Notes 5. 6) i I Resident 2.20 9.28E-07 5.32E-09 5 N Garden 4.30 --

1.48E-09 8 Milk Cow Hone -- --

8 1

l j Resident 2.30 5.12E-07 2.60E-09 5 j NNE Garden 2.50 --

2.30E-09 5

] Milk Cow None -- --

5 1 ,

i Resident 2.30 3.58E-07 1.28E-09 5 i j NE Garden 2.50 --

1.00E-09 8 :

, Milk Cow 4.50 --

2.70E-10 8 ;

l t

l Resident 2.40 2.58E-07 7.08E-10 5 :

ENE Garden 2.5 --

6.10E-10 7 Milk Cow None -- --

5 l j Resident 2.40 3.02E-07 ~6.62E-10 5 ;

3 E Garden 2.80 --

4.87E-10 8 4

Milk Cow None -- --

5 i

Resident 2.0 4.7E-07 1.20E-09 7 I 1

ESE Garden 2.30 --

9.00E-10 5 Milk Cow None -- --

5 4 Resident 2.10 6.58E-07 2.56E-09 8 1 SE Garden 2.50 --

1.60E-09 5 j Milk Cow None -- --

5 Resident 1.60 9. %E-07 5.92E-09 5 SSE Garden 1.7 --

5.24E-09 7 Milk Cow 2.20 --

1.80E-09 5 l l

1 Resident 1.60 7.74E-07 4.66E-09 5 S Garden 1.8 --

5.38E-09 7 Milk Cow None -- --

7 1; Resident 1.90 4.42E-07 2.06E-09 5 i

SSW Garden 4.80 --

2.23E-10 8

, Milk Cow None -- --

5 REV. 8 i

_ -~ _

i 1

i TABLE 2.5 8 l (Sheet 2 of 2) I

- CONTROLLING RECEPT 0R PATHWAYS AND LOCATIONS (NOTE 1), AND 5 ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3) 7

i Pathway Distance X/Q 0/Q 5 l

! Sector (Note 21 (Miles) (Notes 3. 41 (Notes 5. 61 Resident 1.00 1.60E-06 7.50E-09 '7

! 4.44E-10 8 i SW Garden 3.20 --

i 5

) Milk Cow None 1

4 Resident 1.00 1.80E-06 6.50E-09 5 I WSW Garden 1.20 --

4.78E-09 8 5

Milk Cow None i l Resident 1.50 8.40E-07 2.80E-09 5 W Garden 1.50 --

2.80E-09 5 l

4 Milk Cow None -- --

5

' Resident 2.95 3.76E-07 1.07E-09 8 WW Garden 3.70 --

6.02E-10 8

{~

Milk Cow None -- --

5 4

! Resident 2.70 6.98E-07 2.24E-09 5 Hone -- --

5 l NW Garden Milk Cow None -- --

5 l I Resident 2.70 7.62E-07 3.22E-09 5 NNW Garden 3.70 --

1.50E-09 8 Milk Cow 4.40 --

1.01E-09 8 i

NOTES:

(1) Receptor locations are taken from the nearest receptor 5 locations identified in the CPSES 1991 land use census.

(2) m In addition to the pathways shown, the inhalation and ground 5 1 plane pathways are present at the nearest resident.

l (3) g( 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 0/Q values at other distances were determined by linear interpolation.

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l COMANCHE PEAK - UNITS 1 AND 2 01/93 l PART ll 2-54 l

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COMANCHE PEAK - UNITS 1 AND 2 PART ll 2-55 01/93 1

l

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i l

l SECTION 3.0 l

RADIOLOGICAL ENVIRONMENTAL MONITORING l 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 l Control 3/4.12.1, sampling locations will be modified as !

l required to reflect the findings of the Land Use Census. ;

, Dose calculations used in making this determination will 8 l <

be performed as specified in Section 2.5. ;

1 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 locations may be j 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 f 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 COMANCHE PEAK - UNITS 1 AND 2 PART II 3-1 01/93 ;

i participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the '

control limits indicate a need to check the instruments or procedures used. 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.

l i

l l

l CDMANCHE PEAK - UNITS 1 AND 2 PART II 3-2 01/93

i 4

! Table 3.1 1

l Environmental Sampling Locations

] Sampling Location Sample i

Point (Sector - Miles) Iygg(1)

Al N-1.45 (Squaw Creek Park) A l A2 N-9.4 (Granbury) A i

j A3 E-3.5 (Children's Home) A j A4 SSE-4.5 (Glen Rose) A l AS S/SSW-1.2 A

A6 SW-12.3 (Control) A !

1 i A7 SW/WSW-0.95 A 4

A8 NW-1.0 A

{

j' R1 N-1.45 (Squaw Creek Park) R i j ,_ R2 N-4.4 R

R3 N-6.5 R i

i R4 N-9.4 (Granbury) R 1

l R5 NNE-1.1 R

. R6 NNE-5.65 R I

j R7 NE-1.7 R R8 NE-4.8 R i R9 ENE-2.5 R

?

i R10 ENE-5.0 R i

j R11 E-0.5 R 1

1 I

1 i

i i

i C0%NCHE PEAK - UNITS 1 AND 2 PART II 3-3 01/93 -

Table 3.1 (Continued)

Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Ty.pg(1)

R12 E-1.9 R R13 E-3.5 (Children's Home) R R14 E-4.2 R l l

R15 ESE-1.4 R l I

R16 ESE-4.7 R :

l R17 SE-1.3 R l

\

R18 SE-3.85 R l i

R19 SE-4.6 R !

R20 SSE-1.3 R

R21 SSE-4.4 (Glen Rose) R l R22 SSE-4.5 (Glen Rose) R R23 S-1.5 R l R24 S-4.2 R R25 SSW-1.1 R l 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 COMANCHE PEAK - UNITS 1 AND 2 PART II.3-4 01/93

l i

l l

l Table 3.1 (Continued)

I I Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Tygg(l)

R32 WSW-7.0 (Control) R R33 W-1.0 R R34 W-2.0 R R35 W-5.5 R R36 '4NW-1. 0 R R37 WNW-5.0 R l l

R38 WNW-6.7 R

]

R39 NW-1.0 R i

R40 NW-5.7 R l

~R41 NW-9.9 (Tolar) R R42 NNW-1.35 R R43 NNW-4.6 R l

SW1 N-1.5 (Squaw Creek Reservoir Marina) SW SW2 N-9.9(LakeGranbury) SW/0W(2)

SW3 N-19.3 (Control-Brazos River) SW SW4 NE-7.4 (Lake Granbury) SW SW5 ESE-1.4-(Squaw Creek Reservoir'; SW(3)

SWE NNW-0.1 (Squaw Creek Reservoir) SW/0W(4)

GW1 W-1.2 (NOSF potable water) GW GW2 WSW-0.1 (Plant potable water) GW(4),(5) l COMANCHE PEAK - UNITS 1 AND 2 PART II 3-5 01/93 ,

=- _ .- - . - . . . . ..

I i

}

l Table 3.1 (Continued) i j Environmental Sampling Locations Sampling Location Sample i Point (Sector - Miles) Iyag(l)

! GW3 SSE-4.6 (Glen Rose) GW(5)

(

GW4 N-9.8 (Granbury) GW(2),(5) l GW5 N-1.45-(Squaw Creek Park) GW(5) j 551 NNE-1.0 (Squaw Creek Reservoir) SS i

SS2 N-9.9 (Lake Granbury) SS j 553 NE-7.4 (Lake Granbury) SS M1 Deleted M 8 ;

i M2 not used (6) M

[ M3 not used (6) g M4 l

{ .. SW-13.5 (Control) M l 1

j F1 ENE-2.0 (Squaw Creek Reservoir) F i

F2 NNE-8.0 (Lake Granbury) F i

FP1 ENE-9.0 (Leonard Bros. Pecan Farm) FP j FP2 E-4.2(truckfarm) FP

}

i FP3 Deleted FP !6 4 FP4 SW-12.2 (Control) FP 6 i

j BL1 N-1.45 BL j BL2 SW-1.0(7) BL

} BL3 SW-13.5 (Control)(7) BL i

d i (1) Types:

A - Air Sample; R - Direct Radiation; SW - Surface Water; 1

GW - Ground Water; SS - Shoreline Sediment; M- Milk; 5 F - Fish; FP - Food Products; BL - Broad Leaf Vegetation.

i b

4 Rev 8 4

, COMANCHE PEAK - UNITS 1 AND 2 PART II 3-6 01/93

_ . . . ~ . .

i i (2) The municipal water system for the City of Granbury is supplied by surface water from Lake Granbury (location SW2) and ground l Each of these input supplies for the well water (location GW4). )

] Granbury municipal water system is sampled. These samples are l i not required for compliance with Radiological Effluent Control l f 3/4.12.1, Table 3.12-1, because they are not affected by plant j i

i discharges. l (3) This sample (location SW5) is representative of discharges from Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury l via the return line to Lake Granbury.

f (4) The plant potable water is supplied by surface water from Squaw l Creek Reservoir (location SW6) and ground well water (location I GW2). Each of these input supplies for plant potable water is 1 sampled.

I i i

(5)- Ground water supplies in the plant site area are not affected by l j 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 l 3/4.12.1 Table 3.12-1. Although not required for compliance i with the Radiological Environmental Monitoring Program

groundwater sampling locations are included in the monitoring j program to provide confirmation that ground water is not affected

, by plant discharges.

(6) Due to the current availability of milk sampling locations, milk 8 4 samples are taken at only the control locations. If additional milk sampling locations are identified in future land use census, l this table will be revised to include up to a maximum of 3 l 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.

d

! Rev 8 COMANCHE PEAK - UNITS 1 AO 2 PART II 3-7 01/93 ;

I

1 l

1 i

i j (7) Per the Radiological Environmental Monitoring Program given in i

1 Radiological Effluent Control 3/4.12.1, Table 3.12-1, broad leaf j vegetation is required to be sampled only when milk sampling is l not performed at all required locations. Broad leaf sampling will be performed at the specified locations if milk samples are j unavailable from any location.

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1 i

i

APPENDIX A

} PATHWAY DOSE RATE PARAMETER j

J

! Pj (inhalation) = K' (BR) DFAi [Eq. A-1) i i

i i

j where:

l P1 = the pathway dose rate parameter for radionuclide, i,'(other i

! than noble gases) for the inhalation pathway, in mrem /yr f per microcurie /m3 The dose factors are based on the f critical individual organ for the child age group.

] K' = conversion factor, 106 pCi/ microcurie

! BR = 3700 m3/yr, breathing rate for child (Ref. 2, Table E-5) '

I

DFAj = the maximum organ inhalation dose factor for the

[ child age group for the ith radionuclide j (mrem /pC1). Values are taken from Table E-9,

Reg. Guide 1.109 (Ref. 2) !

i i

{ Resolution of the units yields:

1 Pi (inhalation) = 3.7 x 109 DFAj (mrem /yr per uC1/m3)

, [Eq. A-2] >

I i

l i

i i The latest NRC Guidance has deleted the requirement to determine Pj j (ground plane) and P1(food). In addition, the critical age group has been changed from infant to child.

1 4

i j CDMANCHE PEAK - UNITS 1 AND 2 PART II A-1 01/93 '

l APPENDIX B I

INHALATION PATHWAY DOSE FACTOR (R i.a,o) f 3

Rf,a,o = k' (BR) (DFAi.a.o) (mrem /yrpermicrocurie/m)[Eq.B-1]

1 l

where:

k' = conversion factor, 106 pCi/ microcurie j BR = breathing rate, 1400, 3700, 8000, and 8000 m3/yr for I infant, child, teenager, and adult age groups, respectively. (Ref. 2 Table E-5)

DFA1 .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 /pC1. The total body is considered as an organ in the selection of a.o. Values are taken from Tables E-7 DFA 1 through E-10, Reg. Guide 1.109 (Ref.2) ;

l l

l I

l l

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

4 i

APPENDIX C j GROUND PLAE PATHWAY DOSE FACTOR (RG)$

1 4

1, R = k' k" (SF) DFG g [(1-e-Ai t)/Aj ] [Eq. C-1]

i l where' l

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

(15 yrs) 4 DFGi =the ground plane dose conversion factor for the ith radionuclide (mrem /hr per pC1/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Ref. 2). These values apply 1

) to all age groups. Dose factors are provided for the i

total body and skin only. Doses to all other organs are I

! assumed equal to the total body dose.

j SF = 0.7, shielding factor, from Table E-15, Reg. Guide 1.109 l (Ref. 2) h 1

4 s

1 1

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

l

l APPENDIX 0 C

GRASS COW-MILK PATHWAY DOSE FACTOR (R ) f i

Rf,,,g =k'[(Q pxUAP) / IA 1 +A w)] x (F,) x (r) x (DFL5,,,g) x

[((f px f )/3 Y p) + ((1-f p x f,) e-Aih t )/Y sg g -A gf t

[Eq. D-1]

where.

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

QF = cow consumption rate, 50 kg/ day, (R.G. 1.109) f VAP = Receptor's milk consumption rate; 330, 330, 400, 310 j liters /yr for infant, child, teenager, and adult age !

groups, respectively (R.G. 1.109)

Yp = agricultural productivity by unit area of pasture feed ;

a grass, 0.7 kg/m2 (NUREG-0133) !

Ys = agricultural productivity by unit area of stored feed. l 2.0 kg/m2, (NUREG 0133) l Fm = stable element transfer coefficient (Table E-1, R.G.

1.109) r = fraction of deposited activity retained in cow's feed i grass 0.2 for particulates, 1.0 for radiciodine I l

(Table E-15. R.G. 1.109) i DFli ,a,o = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14. R.G. 1.109)

Ai = 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)

COMANCHE PEAK - UNITS 1 AND 2 PART II 0-1 01/93

i l

a i

! APPENDIX D (CONTINUED) j

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

1.109)

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

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

]

I while the cow is on pasture.

i The concentration of tritium in milk is-based on the airborne C

concentration rather than the deposition. Therefore, R $3 l based on (X/Q):

a C

R t,a.o m F UAP DFL t,a,o (.75 (.5/H)) [Eq. D-2) 4 j where:

l k'" = 103 grams /kg

H = 8 grams /m3, absolute humidity of the atmosphere

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

! .5 = ratio of the specific activity of the feed grass water to

the atmospheric water. (NUREG-0133)

DFL t .a.o = the ingestion dose factor for tritium and organ, o,

for each respective age group, a (Tables E-11 to E-14, j R.G. 1.109) i i

All other pars wters and values are as given above.

l C

NOTE: Goat-milk pathway factor, R 1 a.o will be computed using i the cow-milk pathway factor equation. Fu factor for goat-milk i 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 01/93 i

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

l 1

i APPENDIX E !

COW-MEAT PATHWAY DOSE FACTOR (RMi,a.o) i l

2 R

i,a,o IOF xUgp)/(A $ + A g ) x (Ff ) x (r) x (R$,,,g) x t t

[((f x f g)/Y ) + ((1 - f f ) e~ i h)/Y ) x g 9f p p p3 s

[Eq. E-1]

where:

i j k' = conversion factor, 106 picocurie / microcurie (pCi/uC1) 4

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

UAP = Receptor's meat consumption rate: 0, 41, 65, 110

) kg/yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109) l Fr - = the stable element transfer coefficients, days /kg.

] (Table E-1, R.G. 1.109) r = fraction of deposited activity retained in cow's feed {

j grass, 0.2 for particulates, 1.0 for radiciodine l j (Table E-15, R.G. 1.109) i j DFli ,a,o = the ingestion dose factor for organ, o, and the ith

radionuclide for each respective age group, a (Tables i

j E-11 to E-14. R.G. 1.109)

A1 = decay constant for radionuclide 1, sec-1 Aw = decay constant for weathering, 5.73 x 10-7 sec 'l (NUREG-0133) tr = 1.73 x 106 sec, the transport time from pasture to l'

receptor (NUREG-0133) th = 7.78 x 106 sec, the transport time from crop to receptor (NUREG-0133)

COMANCHE PEAK - UNITS 1 AND 2 PART II E-1 01/93 4

, __ .~ ._. _ _ ._

i i

APPENDIX E (CONTINUE 0)

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) I fp = 1.0, the fraction of the year that the cow is on pasture f3 = 1.0, the fraction of the cow feed that is pasture grass i while the cow is on pasture. '

The concentration of tritium in meat is based on its airborne ,

concentration rather than the deposition. Therefore R M $$

basedon(X/Q):

R

= k ' k '" Ff Qp UAP (DFLt,a o) x 0.75 x (0.5/H) [Eq. E-2]

.a.o 4

where: !

All terms are as defined above and in Appendix D.

a l

l i

i N

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

\

$ l i APPENDIX F 1 r' 1

Y VEGETATION PATHWAY DOSE FACTOR (R w )

4 i

! R

,a,o = k' x [r/ (Y y(A$ + A ))] x (DFLi,a.o)

EIU ) Il e-A tit 1 i S

i +U f e -

g i t]

h [Eq. F-1]

1

! i l

j where:

1 l l k' = 106 picocurie / microcurie (pCi/uC1) i UL A = the consumption rate of fresh leafy vegetation, O, 26, i

, 42, 64kg/yr for infant, child, t~ onager, or adult age f

groups respectively. (R.G. 1.109) i

! 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) f l

= the fraction of the annual intake of fresh leafy vegetationgrownlocally,1.0(NUREG-0133) i 1

f 9

= the fraction of the stored vegetation grown locally .76

, (NUREG-0133) t l = the average time between harvest of leafy vegetation and 4

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))

j COMANCHE PEAK - UNITS 1 AND 2 PART II F-1 01/93 4

a

APPENDIX F (CONTINUED) yy = the vegetation areal density, 2.0 kg/m2 (Table E-15, 8 R.G. 1.109) i All other parameters are as previously defined.

l The concentration of tritium in vegetation is based on the airborne I concentration rather than the deposition. Therefore, R j is based on (X/Q)

Rf,a.o = k'k" [U f t+Uff] g (DFLt.a,o) (.75 (.5/H)) [Eq. F-2]

l where:

I l

All terms are as defined above and in Appendix D. !

l I

I I

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

t i

i l

l APPENDIX G SUPPLEMENTAL GUIDANCE STATEMENTS HAVE BEEN DELETED 8 l

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

n1 vel FCTRIC ,

1 OFFICE MEMORANDUM i CPSES-9300319 !

TUS-93009 i January 14, 1993 Response Required by:

Acknowledgement Sheet TO: All Copy Holders j

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

REVISION 8 TO THE CPSES OFFSITE DOSE CALCULATION MANUAL (ODCM)

Enclosed is Revision 8 to the CPSES Offsite Dose Calculation Manual (00CH) and ,

receipt acknowledgement sheet. Return the acknowledgement sheet as specified. l t

In accordance with-CPSES Technical Specification 6.14b, this revision of the ODCM becomes effective after approval by the Vice President, Nuclear l Operations-on December 30, 1992. The ODCM Revision 8 is effective beginning January 1, 1993 except for selected provisions which are related to Unit 2 systems not yet declared operational and functional. Excepted provisions are ,

determined and being tracked by the Radiation Protection Manager. All !

provisions of ODCM Revision 8 will become effective prior to Unit 2 first '

criticality.

If you have any questions regarding the ODCM, contact Connie Wilkerson at (214) 812-8819.

I D. R. Woodlan 24ST Docket Licensing Manager CLW/grp Enclosure c- CCS E06 l

File # 953 l

i l l

i

!"l1 bel FCTRIC

! OFFICE MEMORANDUM CPSES-hb TUS-93206 June 11, 1993

, Response Required by:

! Acknowledgement Sheet l i j TO: All Offsite Dose Calculation Manual Holders !

SUBJECT:

ERRATA - CPSES UNITS 1 AND 2 0FFSITE DOSE CALCULATION MANUAL (ODCM)

TUS-93009, dated January 14, 1993, transmitted Revision No. 8 to the CPSES Offsite

. Dose Calculation Manual (ODCM). The attached pages provide errata for Revision 8.

', The errata correct a formula, and add words and phrases approved for incorporation 4

into Revision 8 but not included in the Revision 8 package. Each replacement page with errata is so identified in the footer, and an instruction sheet and new effective page list are provided. These pages are issued as part of the corrective action for DNE Form 93-1202.

These changes do not affect the intended meaning or implementation of Revision 8. )

I If you have questions, please contact Mr. Connie Wilkerson at (214) 812-8819.

f c j D. R. Woodlan j Docket Licensing Manager I

CLW/grp Attachment d

c- CCS E06 j File f 953 1

f 4

+

COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 0FFSITE DOSE CALCULATION MANUAL INSTRUCTION SHEET I The following instructional information and checklist is being furnished to help insert ERRATA pages to Revision 8 into the Comanche Peak Steam Electric Station Offsite Dose Calculation Manual (ODCM) for Units 1 & 2.

Discard the old sheets and insert the new sheets, as listed below.

1 REMOVE INSERT l l

Part 1 3/4-22b 3/4-22b !

3/4-30 3/4-30 i

l B 3/4-5 B 3/4-5 !

B 3/4-10 B 3/4-10 !

1 5-1 5-1 Part II l

1-13 1-13 2-22 2-22 ;

2-26 2-26 l l

EPL-2 thru -4 EPL-2 thru -4 l i

e o f

I I

i l

l i

i COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL t EFFECTIVE PAGE LISTING-Pace No. Revision No'. ;

)

Cover Sheet 8 l

t i 8 j ii 8 iii 8 iv 8 y 8 vi 8 vii 8 :

viii 8 l ix 8 l x 8 xi '

8 l xii 8 l PART I Divider Page 01/93 :

01/93 I 1-0 .-

I 1-1 01/93- ;

I 1-2 8 l I 1-3 01/93 !

I 1-4 8

! 1-5 01/93 i I 1-6 01/93 i l

I 2-0 01/93 I 3/4-0 01/93 1 3/4-1 01/93 I 3/4-2 01/93 I 3/4-3 8 1 3/4-4 8 I 3/4-5 8 I 3/4-6 8 1 3/4-7 8 I 3/4-8 8 i

I 3/4 9 01/93 I 3/4-10 01/93 I 3/4-11 01/93 i l

I 3/4-12 8 I 3/4-13 8 I 3/4-14 01/93

( I 3/4-15 01/93 I 3/4-16 01/93 REY. 8 COMANCHE PEAK - UNITS 1.AND 2 EPL- 1 01/93 1

l

COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE 00SE CALCULATION MANUAL EFFECTIVE PAGE LISTING Pace No. Revision No.

I 3/4-17 8 I 3/4-18 8 I 3/4-19 8 I 3/4-20 8 :

I 3/4-21 8 !

I 3/4-22 8 -

I 3/4-22a 8 I 3/4-22b 8 ERRATA I 3/4-23 8 ;

I 3/4-24 01/93 !

I 3/4-25 01/93 i I 3/4-26 8 i I 3/4-27 8 !

I 3/4-28 8 i I 3/4-29 8 !

I 3/4-30 8 ERRATA l I 3/4-31 8 !

I 3/4-32 8 :

I 3/4-33 8 !

l I 3/4-34 01/93 i I 3/4-35 01/93 ,

I 3/4-36 01/93 ;

I 3/4-37 01/93 l I 3/4-38 8 l I 3/4-39 8 o I 3/4-40 01/93 i I 3/4-41 01/93 !

I 3/4-42 01/93 ;

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CDMANCHE PEAK UNITS 1 AND 2 EPL-2 Rev. 8 ERRATA (6/93)

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COMANCHE PEAK UNITS 1 AND 2 EPL-3 Rev. 8

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CDMANCHE PEAK UNITS 1 AND 2 EPL Rev. 8

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