Text

Rev 0 to Offsite Dose Calculation Manual for TU Electric Comanche Peak Steam Electric Station
	ML20235R248
Person / Time
Site:	Comanche Peak
Issue date:	03/31/1989
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20235R247	List: ML20235R244; ML20235R248;
References
	PROC-890331, NUDOCS 8903030219
	Download: ML20235R248 (192)
	v • d • e

9 1 1

0FFSITE DOSE CALCULATION MANUAL '

F0P.

TV ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION REVISION O MARCH 1989 O

-e ,

g9030 k f3_ ~ p LC eva b

TABLE OF CONTENTS O List of Tables Paae 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

\

SECTIONS 3.0 AND 4.0 - CONTROLS AND SURVEILLANCE I 3/4 0-0 REQUIREMENTS 3/4.0 - Applicability I 3/4 0-1 3/4.3.3.4 - Radioactive Liquid Effluent I 3/4 3-72 Honitoring Instrumentation 3/4.3.3.5 - Radioactive Gaseous Effluent I 3/4 3-77 Monitoring Instrumentation 3/4'.3.3.6 - Meteorological Monitoring I 3/4 3-82 Instrumentation 3/4.7.15 - Sealed Source Leakage I 3/4 7-1 3/4.11.1.1 - Liquid Effluent Concentration I 3/4 11-1 3/4.11.1.2 - Liquid Effluent Dose I 3/4 11-5 3/4.11.1.3 - Liquid Radwaste Treatment System I 3/4 11-6 3/4.11.2.1 - Gaseous Effluent Dose Rate I 3/4 11-7 3/4.11.2.2 - Gaseous Effluent Dose - Noble Gas I 3/4 11-11 3/4.11.2.3 - Gaseous Effluent Dose - Iodine-131, I 3/4 11-12 Iodine-133, Tritium, and Radioactive Material in Particulate Form 3/4.11.2.4 - Gaseous Radwaste Treatment System I 3/4 11-13 e i Rev. 0 3/89 l

l TABLE OF CONTENTS ;

PiL92 3/4.11.4 - Radioactive Effluents Total Dose I 3/4 11-14 3/4.II.'1- Radiological Environmental Monitoring I 3/4 12-1 Program 3/4.12.2 - Land Use Census I 3/4 12-13 3/4.12.3 - Interlaboratory Comparison Program I 3/4 12-14 BASES I B 3/4 3-6 l SECTION 5.0 - DESIGN FEATURES I 5-0 5.1.3 - Maps Defining Unrestricted Areas and I 5-1 Site Boundary for Radioactive Gaseous and Liquid Effluents SECTION 6.0 - ADMINISTRATIVE CONTROLS I 6-0 6.9.1.3 - Annual Radiological Environmental I 6-18 Operating Report 6.9.1.4 - Semiannual Radioactive Effluent I 6-19 A Release Report O

PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS II 1-1 1.1 General Methodology for Determining Liquid II 1-1 Effluent Monitor Setpoints 1.1.1 Isotopic Concentration of the Waste Tank II 1-2 1.1.2 Maximum Effluent Flow Rate (f) II 1-2 1.1.3 Dilution of Liquid Effluents Due to II 1-3 Circulating Water Flow (F) 1.1.4 Actual Dilution Factor (ADF) II 1-3 1.1.5 Required Dilution Factor (RDF) II 1-4 1.1.6 Upper Setpoint Limit for II 1-5 Detector XRE-5253 O l l

ii Rev. 0 3/89

l TABLE OF CONTENTS O =

1.2 Dose Calculation for Liquid Effluents II l-7 1.2.1 Calculation of Dose Due to a II 1-7 Batch Release !

I 1.2.2 Calculation of Dose Due to II l-9 I Radionuclides Buildup in the Lake 1.3 Dose Projections for Liquid Effluents II 1-11 1.4 Service Water Effluent Radiation II 1-16 Monitort IRE-4269/4270 I 1.5 Turbine Building Sump Effluent Radiation II 1-17 Monitor 1RE-5100 1.6 Definitions of Common Liquid Effluent Parameters II l-18 2.0 GASEOUS EFFLUENTS II 2-1 I I

2.1 Gaseous Effluent Monitor Setpoints II 2-1 j 2.1.1 Dose Rates Due to Noble Gases II 2-3 2.1.2 Plant Vent Stack Noble Gas II 2-5 Monitors XRE-5570A/B and XRE-5567A/B 2.1.3 Plant Vent Flow Monitors 11 2-7 l 2.1.4 Auxiliary Building Ventilation Exhaust II 2-8 I Monitor XRE-5701 2.1.5 Containment Atmosphere Gaseous II 2-10 Monitor 1RE-5503 2.1.6 Dose Rates Due to Radiciodines, II 2-12 Tritium, and Particulate 2.1.7 Plant Vent Stack Iodine Monitors II 2-13 XRE-5575A/B 2.1.8 Plant Vent Stack Particulate II 2-14 Monitors XRE-5568A/B l

1 O

iii Rev 0 3/89

l TABLE OF CONTENTS !

ld Em 2.2 Gaseous Effluent Dose Calculations II 2-17 2.2.1 Dose Due to Noble Gases II 2-17 2.2.2 Dose Due to Radioiodines, Tritium, II 2-18 and Particulate 2.2.3 Dose Projections for Gaseous Effluents II 2-20 2.2.4 Dose Calculations to Support Other II 2-20 Requirements 2.3 Meteorological Model II 2-47 i 2.3.1 Dispersion Calculations II 2-47 2.3.2 Deposition Calculations II 2-49 2.4 Definition of Gaseous Effluent Parameters II 2-50 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING II 3-1 3.1 Sampling Locations II 3-1 3.2 Interlaboratory Comparison Program II 3-1 l

APPENDIX A. Pathway Dose Rate Parameter-(Pi ) A-1 B. Inhalation Pathway Dose Factor (Ri ,a,o) B-1 C. Ground Plane Pathway Dose Factor Rj) C-1 D. Grass-Cow-Milk Pathway Dose Factor (Ri ,a,o) D-1 l E. Cow-Meat Pathway Dose Factor (Ri ,a,o) E-1 F. Vegetation Pathway Dose Factor (Ri ,a,o) F-1 l

O '

iv Rev 0 3/89 l

List of Tables Table No. Titig Eagg PART I - RADIOLOGICAL EFFLUENT CONTROLS 1.1 Frequency Notation I l-5 1.2 Operational Modes I l-6 3.3-7 Radioactive Liquid Effluent Monitoring I 3/4 3-73 Instrumentation 4.3-3 Radioactive Liquid Effluent Monitoring I 3/4 3-75 Instrumentation Surveillance Requirements 3.3-8 Radioactive Gaseous Effluent Monitoring I 3/4 3-78 Instrumentation 1

! 4.3-4 Radioactive Gaseous Effluent Monitoring I 3/4 3-80 Instrumentation Surveillance Requirements 3.3-9 Meteorological Monitoring Instrumentation I 3/4 3-83 l 4.11-1 Radioactive Liquid Waste Sampling and I 3/4 11-2 Analysis Program l

( 4.11-2 Radioactive Gaseous Waste Sampling and Analysis Program I 3/4 11-8 ,

3.12-1 Radiological Environmental Monitoring I 3/4 12-3 Program 3.12-2 Reporting Levels for Radioactivity I 3/4 12-9 Concentrations in Environmental Samples

'l 4.12-1 Detection Capabilities for Environmental I 3/4 12-10 Sample Analyses (LLDs)

PART II - CALCULATIONAL METHODOLOGIES 1.1 Site Related Ingestion Dose Commitment II l-12 Factor (Aj )

2.1 Dose Factors for Exposure to a Semi- II 2-16 Infinite Cloud of Noble Gases 2.2 Pathway Dose Rate Parameter (Pj) II 2-23 2.3 Pathway Dose Factors II 2-24 .

O v Rev. 0 3/89

List of- Tables Table No. Title .P_iLqg 2.4 Atmospheric Dispersion and Depletion II 2-45 Parameters for Radiological Effluent Control 3/4.11.2.3 Calculations 2.5 Controlling Receptors, locations, and II 2-46 Pathways (For Dose Calculations Required by Radiological Effluent Control l 3/4.11.2.3) 3.1 Environmental Sampling Locations II 3-3 i

l O

l l

O vi Rev. 0 3/89

l I

l List of Fiaures Fiaure Title PjLq1t l PART I- RADIOLOGICAL EFFLUENT CONTROLS l J

J 5.1-3 Site Boundary and Unrestricted Areas I 5-2 1 J

PART II - CALCULATIONAL METHODOLOGIES

)

1.1 Liquid Effluent Discharge Pathways II 1-22 1.2 Energy Response to Gamma Radiations II 1-23 for RD-33 Type Detector 1.3 Circulating Water Pump Curves II l-24 1.4 Liquid Waste Processing System II J-25 2.1 Gaseous Waste Processing System II 2-56 2.2 Plume Depletion Effect for Ground II 2-57 Level Releases 2.3 Vertical Standard Deviation of II 2-58 Material in a Plume 2.4 Relative Deposition for Ground- II 2-59 Os Level Releases 2.5 Open Terrain Correction Factor II 2-60 3.1 Radiological Environmental Monitoring II 3-9 Locations O

vii Rev. 0 3/89

Cross Reference to Technical Specifications and REC Number or Document Section Requirement ODCM Section PART I-RADIOLOGICAL EFFLUENT CONTROLS (REC)

Tech Specs 6.8.3.e.1 Effluent monitoring instrumentation 3/4.3.3.4 and operability, surveillance, and 3/4.3.3.5 setpoint requirements l I

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 I 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 Tech Specs 6.8.3.e.5 Determine cumulative and projected 3/4.11.1.2, doses due to radioactive effluents 3/4.11.2.2, !

3/4.11.2.3, 3/4.11.1.3, and 3/4.11.2.4 Tech Specs 6.8.3.e.6 Effluent treatment systems 3/4.11.1.3 and operability requirements 3/4.11.2.4 1

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 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 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 1.2 REC 3/4.11.1.3 Dose projections for liquid 1.3 releases viii Rev. 0 3/89

Cross Reference to Technical Specifications and REC O

V Number or -

Document Section Requirement 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, 2.1.6 and particulate with half lives greater than eight days REC 3/4.11.2.2 Air dose due to noble gases 2.2.1 REC 3/4.11.2.3 Doses due to iodines, tritium, 2.2.2 l and particulate with half-lives ]

greater than eight days J REC 3/4.11.2.4 Dose projections for gaseous 2.2.3 releases j REC 3/4.11.4 Total dose due to releases of 2.2.4 l radioactivity and direct radiation REC 3/4.12.1 Description of radiological 3.1 environmental sampling locations

,Q V

REC 3/4.12.2 Dose calculations for identifying 2.2.4 changes to environmental sampling locations REC 3/4.12.3 Description of the Interlaboratory 3.2 Comparison Program l REC 3.3.3.4 Radioactive liquid effluent monitoring channels alarm / trip setpoints o liquid waste monitor (XRE-5253) 1.1.6 o turbine building sump monitor -1.5 (IRE-5100) o service water monitor 1.4 (1RE-4269/4270)

O ix Rev. 0 3/89

Cross Reference to Technical Specification _s__and REC Number or Document Section Requirement 00CM Section REC 3.3.3.5' Radioactive gaseous effluent monitoring channels alarm / trip setpoints o noble gas release rate monitors 2.1.3 XRE-5570A and XRE-55708 (WGRM release rate channels) o noble gas activity monitors 2.1.2 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 2.1.4 (auxiliary building vent monitor)

XRE-5701 o sampler flow rate monitor 2.1.3 XFT-5570A2/82 1 1

Tech Specs 3.3.3.1 Radiation monitoring channels alarm / trip setpoint o Containment atmosphere gaseous 2.1.5 p monitor (containment vent i

l monitor) 1RE-5503 j Tech Specs 6.9.1.4 Assessment of radiation doses due 2.2.4 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 2.2.4 REC 6.9.1.4 the public inside the site boundary Tech Specs 6.9.1.4 Assessment of doses to the most 2.2.4 REC 6.9.1.4 likely exposed member of the public from reactor releases and direct radiation O

x Rev. 0 3/89

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).

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," TV Electric, Comanche Peak Steam Electric l Station.

l

5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC q

Regulatory Guide 1.111 (March 1976). l

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

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

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

8. " Technical Specifications," TV Electric, Comanche Peak Steam Electric

r-

, Station.

9. " Radioactive Effluent and Environmental Monitoring Manual," TV Electric, Comanche Peak Steam Electric Station.

O xi Rev. 0 3/89

INTRODUCTION The 0FFSITE DosC CALCULATION MANUAL (0DCM) is a supporting document of the CPSES Technical Specification. The ODCM contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.3 and 6.9.1.4, and (3) Controls for Meteorological Monitoring .

Instrumentation and Sealed Source Leakage. The ODCM also describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid i and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Liquid and Gaseous Radwaste Treatment System configurations are shown in Figures 1.4 and 2.1. l The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in the i

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

10 l xii Rev. 0 3/89

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 appli$d in this manual where applicable to provide a more workable document for implementing the Radiological Effluent Control requirements.

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

This manual is designed to provide necessary information in order to simplify the dose calculations. The dose calculations can be optionally expanded to {

I several levels of effort. The complexity of the dose calculations can be '

expanded by several levels of effort, aiming toward a full calculation in accordance with Regulatory Guide 1.109. Future changes to the 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 complex calculations. A beneficial approach to implementing the Radiological Effluent Control Program and Regulatory Guide 1.21 (Semiannual Radioactive Effluent Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses.

l I

lO xiii Rev. 0 l 3/89

l O

PART I EADl0 LOGICAL EFFLUENT CONTROLS O

O

l O 1 l

SECTION 1.0 DEFINITIONS O

i O COMANCHE PEAK - UNIT 1 I 1-0 an. 0 3/89

1.0 DEFINITIONS k 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 steps such that the entire channel is calibrated.

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

DIGITAL CHANNEL OPERATIONAL 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 0PERABILITY of alarm and/or trip functions.

REV. 0 O co"^"c"E ee^x . UNIT 1 111 3,eg

DEFINITIONS O

y/ DOSE E0VIVALENT 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, I-134, and I-135 actually present. The thyroid dose conversion factors used for this c&lculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.

FRE0VENCY NOTATION i 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 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors. Also excluded from l this category are persons who enter the site to service equipment or to make l deliveries. This category does include persons who use portions of the site l for recreational, occupational, or other purposes not associated with the '

plant.

p>

t 0FFSITE DOSE CALCULATION MANVAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) 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, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

REV. O COMANCHE PEAK - UNIT 1 I 1-2 3/89

1 l

DEFINITIONS l

l O '

OPERATIONAL MODE - MODE l

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

PRIMARY PLANT VENTILATION SYSTEM 1.24 A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulate 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.

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

RATED THERMAL POWER

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

REPORTABLE EVENT l

1.31 A REPORTABLE EVENT shall be any of those conditions specified in ;

10CFR50.73.

SITE B0UNDARY 1.33 The SITE BOUNDARY shall be that line as shown in Figure 5.1-3.

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

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

A V COMANCHE PEAK - UNIT 1 I 1-3 REV. O 3/89

l l

I DEFINITIONS O UNRESTRICTED AREA 1.41 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY l access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE B0UNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

l VENTING 1.42 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

WASTE GAS HOLDUP SYSTEM 1.43 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for I the purpose of reducing the total radioactivity prior to release to the environment.

O i O COMANCHE PEAK - UNIT 1 I 1-4 REV. O 3/89

TABLE 1.1 FRE0VENCY NOTATION NOTATION FRE0VENCY 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.

R At least once per 18 months.

S/V Prior to each reactor startup.

N.A. Not applicable.

P Completed prior to each release.

O l

REV. O COMANCHE PEAK - UNIT 1 I l-5 3/89

TABLE 1.2 OPERATIONAL MODES AVERAGE REACTIVITY % RATED COOLANT MODE -

CONDITION. Keff THERMAL POWER

TEMPERATURE i

1. POWER OPERATION 2 0.99 > 5% 2 3500F j

2. STARTUP 1 0.99 s 5% 2 3500F

3. H0T STANDBY < 0.99 0 2 3500F l

4. HOT SHUTDOWN < 0.99 0 3500F>Tavg

> 2000F

5. COLD SHUTDOWN < 0.99 0 1 2000F

6. REFUELING ** 1 0.95 0 s 1400F I O

Excluding decay heat.

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

1 l

i

~

COMANCHE PEAK - UNIT I 1-6 3/89

O I

SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS I

COMANCHE PEAK - UNIT 1 I 3/4 0-0 3 89

I 3/4 CONTROLS AND SURVEILLANCE RE0VIREMENTS 3/4.0 APPLICABILITY #

CONTROLS 3.0.1 CompliancewiththeControlscontainedinthesucceedingControlsis required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION ,

requirements shall be met.

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

l 3.0.3 When a Control is not met, except as provided in the associated ACTION '

requirements, within I hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

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

b. At least H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and I

c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . l Where corrective measures are completed that permit operation under the ACTION O 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 ,

l continued operation of the facility for an unlimited period of time. This j 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.

O COMANCHE PEAK - UNIT 1 I 3/4 0-1 aev. o 3/89.

f

APPLICABILITY SURVEILLANCE RE0VIREMENTS O 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, but

b. The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

Exceptions to these requirements are stated in the individual controls. ;

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance 4.0.2, shall constitute noncompliance with ti.e OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

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

REV. O COMANCHE PEAK - UNIT I I 3/4 0-2 3/89

INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS _

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 channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM) .

APPLICABILITY: At all times.

ACTION:

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

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

SURVEILLANCE RE0VIREMENTS 4.3.3.4 Each radioactive liquid 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 4.3-3 .

REY. O COMANCHE PEAK - UNIT 1 I 3/4 3-72 3/89 O

C A

h' N

O I

T A

T SE n N MLL i E UEB a M NNA r U I NR 1 1 t 1 R NAE /

T I HP 1 S MCO N

I G

N I

R )

O 0 7 T 7 I g 2 3 N e n 4 O n i -

3 M i d E L i R E T v 1 L N t o B E n r ,

A U e P 9 T L u 6 F l t 2 o

O F f 4 E ) f N - )

3 E E 8 D d 5 t R 8 I n 2 s u I 2 U a 5 p B ( 5 Q - m -

I m E u m e T L r R S r n F ae X ae i X E l s ( ) l s L (

V Aa s Aa I e e n e t e T gl n i gl n n C ne i a ne e i A T iR L r iR u L 0 N d D d l s I E if t if f e t D M vo n r vo f c n A U o e o o E ;

e R R rn u o rn v u T P o l l P o m e l S i f F i e D f N st f ( st t f I ra E ra s t E on g on y n ti e n ti S e e i m t i im m t nr s d nr r e s oe a l oe e r a MT w i MT t u w yc d u) a s d a B0 yc W a a ti R 0 ti e R it e1 it e M va d n5 va c d im i i - im i e i t o u bE t o v t u ct q rR ct r a q au i uI au e R i oA L T( oA S L i i w d d o a . . a . l .

R a b R a F a 1 2 3 O .

A5 o nhzem AR , ~ [1 y0 R3

l TABLE 3.3-7 (Continued) q ACTION STATEMENTS b ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this

, pathway may continue provided that prior to initiating a 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 Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue provided grab samples are-analyzed for radioactivity at a lower limit of detection of no more than-10-7 )

microcurie /ml: I

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 O b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.

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-4510, & '

1RE-4511) OPERABLE and indicating an activity of less than IX10-4 microcurie /ml, a grab sample is collected and analyzed for radioactivity at a lower limit of detection of no more than 10-7 microcurie /ml at least every T. 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 analyzed for radioactivity at a lower limit of detection of no more than 10-7 microcurie /ml.

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

REV. O COMANCHE PEAK - UNIT 1 I 3/4 3-74 3/89

O S LLIS AETE TNAT I NR

(

1 Q

2

(

Q 3

(

Q A.

N GAE T I HP N D C O' E

M L E A R N I OT U LI S . . .

0 GETE E ONAT A. A. A.

R LNR N N N Q AAE E NHP C ACO N

A L

L N I

LO E EI V NT R NA ) ) )

U AR 4 4 4 S HB ( ( (

CI R R R R N L O A I

C T

_ A

_ T E .

_ N CK E RC A.

M 3 UE P M M N U OH R SC

_ 3 T

_ 4 S

_ N E I L

_ L E e )

B G NK s 5 A N NC a (

T I AE D D e D D R HH l O

O CC e T ) R I

3 N d 5 tf O n 2 s uo M a 5 p B

_ - m n T

N m

r E

R S u mo ri e

n E ae X at i

_ U l s ( ) l a L

_ L Aa s An F e e n i t e F

E gl n i gm n n ne a nr e u'

_ i i i R L r ie L D d D dT l s I i f t i f e t U vo n r) vc f c n O o e o0 oi E i e I

rn u o0 rt v u L P o l f

l 1 Pa m) e l E

i F5 m e0 D f V

st ra f

E

( - so t7 f E rt s2 t E I

on gR ou y4 n T

C ti e nI tA S - e e A

i m t i( i E m t

_ nr s de ng rR e s

_ 0 oe a l n on eI r a I

MT w i i Mi t u w

_ D T d uL d a , s d)

A N yc a B yi W9 a a8 R E ti R t t v 6 e R8

_ M it en i o e2 M 2

- U va d ne vr c4 d5

_ R i m i i u iP i - e i -

_ T t o u bl t vE t uT

_ S ct q rf ct rR a qF N au i uf ao eI R i X I

oA L TE oN S( L(

i d

i w

_ a . .

d a .

o l .

R a b R a F a

_ 1 2 3 O

R i* . O hm ;Rg hz [1 R$

~

i 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).

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

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

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

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

(5) CHANNEL CHECK shall consist of verifying indication of flow during 1 periods of release. CHANNEL CHECK shall be made at least once per 24 l hours on days on which continuous, periodic, or batch releases are made, l

REV. O COMANCHE PEAK - UNIT 1 I 3/4 3-76 3/89 i

l

i INSTRUMENTATION RADI0 ACTIVE GASE0US EFFLVENT 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 channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-8 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel 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 i inoperable, or change the setpoint so it is acceptably conservative.

i b. With less than the minimum number of radioactive gaseous effluent I

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 l 6.9.1.4 why this inoperability was not corrected in a timely manner. '

n* c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 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 .

1 1

REV. O COMANCHE PEAK - VNIT 1 1 3/4 3-77 3/89 l

n

\ /

O N

O '

I 4 6 7 7 5 T 3 3 3 3 3 C

A f

0 I

T A

T Y N T E I M L U I R B T

S A

N C * * * *

I I

L G P N P I A R

O T

8 I

- N 3 O M

3 T

E N k k k k k L E c c c c c B U a a a a a A L S

t t t t t T F s s s s s o

F L /

E / / / /

E 1 1 1 1 1 NE S NL U AB O HA E CR S E A MP G UO M ] ]

I E ) )

V N l r l I

I M

e o e T n t n C n i n A a n a O mn ro h o h r I c M c o)

D ai t2 A el t B e e8e i8 R tAa 0t N t0t n0 a n 7 a O a7 a o7 R gi 5 r I R5 r M nm 5 T 5

~

M5 E eir

) e) 5 T

- e A e- e d l d e-sde Es L sEs i pi tT S aiT Ra I aR a k mk aF Y ev X e T eX e rs as RX S l oc l N l l e S eri &e E e&e l e e w, P RPt r V R r pl el T U o2 N D aeA A mp t p l A E L s - ms0t a oa7 n T

N s0t a7 n am Sa am l a F0 M O 7 U H Grt e5 e A G5 e s us r5 oul 5 u L 5 u e c e5 R etAe P T S l i REf l e - l l Ef nM i M l -

S A iG tG pT N

bnd Rf Y bRf dR rR mF G oonfX R oX e oW aW I

E NMao[(e A M

N[( I( P(

aX S(

T I S R . .

A W a P a b c d 1 2 o

N5 o hm mk h5* ~ _ [4c ,o N

tr[

TABLE 3.3-8 (Continued)

TABLE NOTATIONS

At all times.

- During Batch Radioactive Releases via this pathway. '

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

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

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

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

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 35- With the number of channels OPERABLE less than required by the 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 .

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

(a) A Plant Vent Noble Gas Activity Monitor (XRE-5570A, XRE-55708 (low range activity) or XRE-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 Rate Monitor (XFT-5570A1, XFT-557081) is OPERABLE, and an alternate Plant Vent Noble Gas Activity Monitor is OPERABLE (XRE-5567A, XRE-55678) or grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or (c) The plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and grab 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 .

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 O 4.11-2.

REV. O COMANCHE PEAK - UNIT 1 I 3/4 3-79 3/89

) ) . . .

LLIS 1 2 AETE ( ( A. A. A.

TNAT Q Q N N N S I NR T GAE N I HP E D C 0~--1 M L' E

R A I N U OT Q LIS . . . .

E GETE R ONAT A. A. A. A.

LNR N N N N Q E AAE C NHP N ACO A

L L

I E N V O I

R U LT ) ) . .

S EA 3 3 NR ( ( A. A.

N NB R R N N R O AI I HL T CA A C T

N E E

M CK . . .

4 U RC

- R UE A. A. A.

3 T OH P # N N N S SC 4 N I

E L L G E ) )

B N NK 4 4 A I NC ( (

AE OT R P D W W D O HH T CC I

N O e e M s s a a T e e N l l E e e U - r r L

F r t rt F oc n on E ti e t e it u i u S na l nl U om Mo f

f of r O Mf o)

E t e e t2 S eue( e( iB A tAsB N t8 n0 G a a0 O a0 o7 M Rde7 I R7 r M5 E E nl 5 T 5 ) e)

T eae5 5 V

S s A e5 d l d e-I R - L s - i pi tT T Y S

as erfR]

E I aE k mk aF C T eR] rs aS RX A P l aoX) N l X) e S 0 el ,le E e l e e w I U RAn V R ,le pl el o2 D O oAn An mp t p l A A

R L

O s gi 0 n ant 7 a T

N s0 n a7 a Sa am am l a F0 H 7 Gia5h A G5h s uS r5 dn5 c L 5 c e c e5 S eii- P e- nM A l vmEe i M l -

G l E e i G tG pT borRt Y bRt dR rR mF T oreX a R oXa oW aW N E NPT[ r A aX E N[ r I( P( S(

T M M S I U A .

R . .

R W a P a b c d

T S

N .

I 1 2 O -

A5 O 9 AM g .

o

~ .- w1 wd RS l' l

BBIE 4.3-4 (Continued)

TABLE NOTATIONS

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 occurs if any of the following condition exists:

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 control room alarm annunciation occurs if any of the following 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 the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These O standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference 1 standards certified by NBS, or standards that have been obtained from suppliers that participate in measurement assurance activities with NBS shall be used.

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

REV. O COMANCHE PEAK - UNIT 1 I 3/4 3-81 3/89

I INSTRUMENTATION

)

METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in Table 3.3.3-9 shall be OPERABLE. j l

APPLICABILITY: At all times. l ACTION:

a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to CPSES Technical 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 RE0VIREMENTS 4.3.3.6 Each of the above meteorological monitoring instrumentation channels l 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

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

r i

REV. O COMANCHE PEAK - UNIT 1 I 3/4 3-82 O 3/89 1 l

1

TABLE 3.3-9 fm METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT LOCATION OPERABLE

1. WIND SPEED 1 of 3

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.

3. AIR TEMPERATURE - A T 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

(]

v Nominal Elev. 10 m.

Mounted on backup tower.

l l

O V COMANCHE PEAK - UNIT 1 REV. 0 I 3/4 3-83 3/89

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

APPLICABILITY: At all times.

ACTION j

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

limits, immediately withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

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

SURVEILLANCE RE0VIREMENTS 4.7.15 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

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

The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.

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.

REV. O COMANCHE PEAK - UNIT 1 I 3/4 7-1 3/89

SURVEILLANCE RE0VIREMENTS (Continued)

O

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

Reports - A report shall be prepared and submitted to the Commission on an !

annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.

! l l ?

l l

O 1 i

l REV. 0

)* COMANCHE PEAK - UNIT 1 I 3/4 7-2 3/89

1 3/4.11 RADI0 ACTIVE EFFLVENTS 3/4.11.1 LIOVID EFFLVENTS CONCENTRATION CONTROLS 3.11.1.1 fn accordance with CPSES TS 6.8.3.e.2 and 3, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or concentration shall be limited to 2 x 10 gntrained noble microcurie /mlgases, the total activity. .

1 APPLICABILITY: At all times. J ACTION:

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

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

SURVEILLANCE RE0VIREMENTS O 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according l to the sampling and analysis program of Table 4.11-1.

1 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.

COMANCHE PEAK - VNT! 1 I 3/4 11-1 3 9 I

( TABLE 4.Il-1 l

. Radioactive Liquid Waste Sampling and Analysis Program LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) (1)

TYPE FREQUENCY FREQUENCY ANALYSIS DiC1/ml)

1. Batch Waste P P Release Each Batch Each Batch Principal Gamma 5x10~

Tanks (2) Emitters (3)

-6 I-131 1x10

a. Waste Monitor P M Dissolved and Tanks One Batch /M -5 Entrained Gases 1x10 (Gamma Emitters)

b. Laundry Holdup and P M Monitor Each Batch Composite (4) H-3 1x10

-5 Tanks ,

~ l Gross Alpha 1x10

c. Wastewater l Hold-up Tanks P Q Sr-89, Sr-90 5x10

-8 g)

Each Batch Composite Te-55 1x10

-6

d. Condensate P P Principal Gamma Polisher Each Batch Each Batch Emitters (3) 5x10

_7 Backwash Recovery -6 I-131 1x10 Tanks (6)(7)

e. Component M Cooling (4) -5 Composite H-3 1x10 Water Drain Tank (7)

2. Continuous W W Releases (5) Grab Sample

_7 Emitters (3) 1-131 ~0 1x10 Turbine Bldg Sumps No. M

, (4) H-3 1x10

-5 1 & 2 Effluents Compostte (6)(7) r\

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-2 3/89

TABLE 4.11-1 (Continued)

TABLE NOTATIONS (1) The LLO is defined, for purposes of these specifications, as the smallestconcentration of radioactive material in a sample that will yield a net c'ount, 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: ,

l 4.66 sb !

LLO = (

E V 2.22 x 106 . y . exp (-Aat)

Where:

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

sb = the standard deviation of the background counting rate or of ,

the counting rate of a blank sample as appropriate (counts per j minute),

E = the counting efficiency (counts per disintegration),

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

2.22 x 106 = the number of disintegrations per minute per microcurie, i l

Y = the fractional radiochemical yield, when applicable, )

A = the radioactive decay constant for the particular radionuclides (sec-1), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and at should be used in the calculation. 1 It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not r, an a posteriori (after the fact) limit for a particular measurement.

(2) A batch release is the <lischarge of liqui'l wastes of a distrete vulume.

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

s O

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-3 3/89

TABLE 4.11-1 (Cont _iAu_qdl TABLE NOTATIONS O (3) The principal gamma emmiters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. 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 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.

(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 reprocentative I 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 required to be sampled and analyzed in accordance with this table if either of the following conditions exist:

(a) Activ'ty is present in the secondary system as indicated by either i Stearr Generator 810wdown monitors or secondary sampling and {

analysis; or l O (b) Activity was present in the respective tanks or sumps during the previous 4 weeks.

l If neither of the above situations exists, then sampling and analysis of these tanks and sumps need not be performed.

(7) All flow from this waste stream shall be diverted to the Wastewater I Holdup Tanks when results of sample analyses show radioactivity present in the waste stream at concentrations greater than or equal to the LLO values given in this table. Sampling and analysis of the respective tanks or sumps are not required when flow is diverted to the Wastewater Holdup Tanks.

O v

REV. O COMANCHE PEAK - UNIT 1 1 3/4 11-4 3/89

RADI0 ACTIVE EFFLUENTS M

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

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

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

APPLICABILITY: At all times.

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 the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to. reduce the C~~)s 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 REQUIREMENTS 4.11.1.2 Culmulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

O COMANCHE PEAK - UNIT 1 I 3/4 11-5 REV. O 3/89

1 1

RADI0 ACTIVE EFFLUENTS ,

LIOUID RADWASTE TREATMENT SYSTEM O CONTROLS 3.11.1.3 In accordance with CPSES TS 6.8.3.e.6, the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used .

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

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the 1 Commission within' 30 days, pursuant to Specification 6.9.2, a Special )

Report that includes the following information: ,

1. Explanation of why liquid radwaste was being discharged without

~

treatment, identification of any inoperable equipment or

( subsystems, and the reason for the inoperability, t

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

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

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

l O COMANCHE PEAK - UNIT 1 1 3/4 11-6 REV. O 3/89 l

I

l l

RADIOACTIVE EFFLUENTS q

4 3/4.11.2 GASE0US EFFLVENTS DOSE RATE i

3.11.2.1 In accordance with CPSES TS 6.8.3.e.3 and 6.8.3.e.7, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE B0UNDARY (see Figure 5.1-3) shall be limited to I the following: ;

s

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

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 mrem /yr to any organ.

APPLICABILITY: At all times.

i 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 RE0VIREMENTS !

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131, Icdine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance the methodology and parameters in the ODCH by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-7 3/89

LI l T m 6 6 I RC/ _ - - - - - - -

EEi 0 0 0 0 0 0 0 0 0 WTC 1 1 1 1 1 1 1 1 1 OE p x x x x x x x x x LD y l l l l l l l I l

) ) ) )

2 2 2 2

( ( ( (

s s s s r r r r

) e e e e

t t t t

( t t t t i i i i m m m m m a S E E E E r I g S a a a a o Y m m m m

_ r L m m m m P A a a a a 0

_ N G G ) C ) G a 9

_ s A e e h -

_ i l l d l d l p r

_ s Y a a i a i a l S x

y FT p p x p p A G

_ l OI i i o i o i ,

_ a V c c ( c ( 1 c s 9

_ n EI n n n 3 n s 8 l

_ A PT i i 3 i 3 1 i o - b

_ YC r r - r - - r r r d TA P P H P H I P G S N

_ n

_ 2 a

_ l g I n

_ . i

_ 4 l p

) e e

_ 3 - l l E m ( rp rp am am L a e

_ B S s e e P a P a A a n t S S T e Y k e i a e e sC SC n a O

t l ) ) d r ) l t e t e s MI N a e 3 7 oe 7 u it i t G r a USE T R ( ( ib ( ce sa sa W MYU P P M M W ior W il Molpu Qol e I LQ h h o t p pu l a s NAE rm mc mc c c d s b t u I NR a a ad aa oi oi o e

_ o MAF E E RA PS C t Ct N B e

s a

G e

v )

i 3 )

t ( 5 ) ) ) ) )

c e ( 6 6 6 6 6 a e s e ( ( ( ( (

o l a , l s s s s i Y k p e ) p u u u u d

a GC NN nm aa l

e 4 m a

o o o o

( u u u u R I E TS R S n n n n LU P P , i i i i i PQ hb h ) b t t t t t ME c a c 3 a n n n n AR ar a ( r o o o o

_ SF EG E M G C C C C C e e E g g a

P r Y r u

_ T o P t

_ E S t

_ S n t A s e n E a m e

_ L G nt V E i n ae R e t

_ t k t V n S s n n a aa or

_ U l O WT C o P

_ E

_ S A . . .

G 1 2 3 O

yQ g a E2nx* mR , c2 4 - -

~ N* . -

wN@

N?

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1) The LLO 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 s b LLO =

E . y . 2,22 x 10 6 . y . exp (-Aa t)

Where:

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

sh = the standard deviat on of the backaround ounting rate or of tne counting rate of a b'ank sample as 6ppropriate (counts per minute), !

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

O v the ee nie s4ze (e"4t> er e>> er veie e).

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 radionuclides l

('sec-1),and '

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

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

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

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-9 3/89

l TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(]

v 1

(2) The principal gamma emitters for which the LLD specification applies l include the following radionuclides: Kr-88, KR-88, Xe-133, Xe-133m, I Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, l Zn-65, I-131, Cs-137, CS-137, Ce-141 and Ce-144 in iodine and particulate I 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 B, 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) I analysis of primary coolant activity performed pursuant to Technical '

Specification 4.4.7 shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not 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.

O (5) Tritium grab samples shall be taken at least once per 7 days from the d ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. l l

(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 sampler.

Sampling shc11 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) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-10 3/89

RADI0 ACTIVE EFFLUENTS 1

DOSE - N0BLE GASES CONTROLS

)

{

I 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 J and beyond the SITE B0UNDARY (see Figure 5.1-3) shall be limited to the I 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 I

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 gaseous I effluents exceeding any of the above limits, prepare and submit to the l 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,

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

SURVEILLANCE RE0VIREMENTS l l

4.11.2.2 Cumulative dose contributions for the current calendar quarter and I current calendar year for noble gases shall be determined in accordance with I the methodology and parameters in the ODCM at least once per 31 days.

1 :

l l

l REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-11 3/89 i

86DI0 ACTIVE EFFLUENTS DOSE 10 DINE-131. IODINE-133. TRITIUM. AND RADI0 ACTIVE MATERIAL IN O,,

s 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 1 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 B0UNDARY (see Figure 5.1-3) shall be limited to the following:

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

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

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-131, Iodine-.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 Commission within 30 days, pursuant ,

to Specification 6.9.2, a Special Report that identifies the cause(s)

O- for exceeding the limit and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance 1

i with the above limits,

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

SURVEILLANCE RE0VIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter 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 the ODCM at least once per 31 days.

l l

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-12 3/89

RADIOACTIVE EFFLUENTS l

GASEOUS RADWASTE TREATMENT SYSTEM l

CONTROLS i 3.11.2.4 I'n 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 B0UNDARY (see Figure 5.1-3) would exceed: )

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

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

l APPLICABILITY: At all times. 1 ACTION:

t l a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to specification 6.9.2, a 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 1

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

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

SURVEILLANCE RE0VIREMENTS _

l I

4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and l

beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM 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.

REV. O COMANCHE PEAK - UNIT 1 1 3/4 11-13 3/89

RADI0ACilVE EFFLUENTS q 3/4.11.4 TOTAL DOSE CONTROLS

~

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

APPLICABILITY: At all times.

l ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a., or 3.11.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR 20.405c, shall include an s analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel c 'e sources, including all effluent pathways and direct radiation, or the calendar year that includes the release (s) covered by this report. It shall also describe levels of l

radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, 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.

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

SURVEILLANCE RE0VIREMENTS I 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

REV. O COMANCHE PEAK - UNIT 1 I 3/4 11-14 3/89 O

i

RADI0 ACTIVE EFFLUENTS (Continued) 3/4.11.4 TOTAL DOSE SURVEILLANCE REQUIREMENTS 4.11.4.2 C'umulativedosecontributionsfromdirectradiationfromtheunits and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4.

1 1

l l

O j

N REV. 0-

). . COMANCHE PEAK - UNIT 1 I 3/4 11-15 3/89 L _ _ - _ __- - _ _ _ _ -_ __ _ _ _ _ -_- - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --

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

APPLICABILITY: At all times.

ACTION:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3, a description of the reasons 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 in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the 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 to be taken to reduce radioactive effluents so that the potential annual dose

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

concentration (1) reporting level (1) + concentration reporting level (2)(2) + .. 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. This report is not required i if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported i and described in the annual Radiological Environmental Operating j Report required by Control 6.9.1.3.

The methodology and parameters used to estimate the potential annual dose to !

a MEMBER OF THE PUBLIC shall be indicated in this report.

REV. O !

COMANCHE PEAK - UNIT 1 1 3/4 12-1 3/89 l l

(3 v

l l

l 1

l

RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS

\ ACTION (Continued) i

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them within 30 i

days to the Radiological Environmental Monitoring Program given in 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 Release Report, a complete, legible copy of the entire ODCM, j including a revised figure (s) and table for the ODCM reflecting the new location (s). )

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

SURVEILLANCE RE0VIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected l

' pursuant to Table 3.12-1 from the specific locations given in the table and )

figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of ;

i Table 3.12-1 and the detection capabilities required by Table 4.12-1. '

O i 4

I l

)

l REV. O COMANCHE PEAK - UNIT 1 I 3/4 12-2 3/89 1

~ - _ - _ _ - - - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

l il

)

y 3 y (

Y l t s C r i i N e . v d s E t : y i ny .

US r r l t al y QI a e k : cg a l s ES u t e r ay n r

- RY q s e e of aye

-g FL iy i w l bt A e n p d o;c( r DN s n s m al ei a NA o a i a rl gpeu A C s

P EO F

d

.a m

e l n a y

S e t t

onot q af ati h os) escsonipo Y m i n a bi -

T a d a l sr mi G o u syeaot i

i 1 o 3 1

i c sl t mca oal m t rniaf o c -_

d - r G af gol -

a I a _

R P .

Y C - y N - c b E re DU el d m NQ pl e a AE ooer r R cri g GF r ou o N eemq r I N . ll e P LO y pprr g PI MT l

r mmo aa n AC e ss ,fi g i SE t y n r L r shl yi o L a utkld t O u oiet a Q

i n

C uweno n wel 1 o i n u M t onqt 2 nioes 1 l oti ru

.a C atfd

_ 3t n s - y Ee srr ne n e b Lm neu : ih i b sr l t Bn ot s s t aaeo n Ao i ea w e e oeenr e Tri t me o nn nne t rnot r aim l oi oih a n : e

-s v t s el t s ,no s f n sort o ,r ,r nt sic n f E

g d oaf f r so nt E som osr o i e nt o ieed s i e d g l ne s ocT ocr t rt na t s t a a i rt ea ieI i ef aena a o nsr

_ c rons t sS t s t t e e c l i ee

_ i g omeod a a e snc ,v o c ,hga v o

) t md e tl e tl g i sr l g

iru norga c sah san e nl e m si l ct ca hl oos e oE nhl ;

o S o t nl fi fi r t aio v rT o aQ i N mosip o gf og ith o i fI i eu/

d a

E V

O I

wnd eti r , gl oo gl om k

f cact oel s f

s Sth nD n at n R I T oy noa no- pu s m eec al TDA ih ecl ire i r8 esp ,a o l eof e ANC t t nes ror ro c ose r prl od v _

FTAO uioru ea; eod nnper . f mh ee _

ON ES L ow o rt Y rt t n ai cas atY , tl r hd u eelR ee a l sn n s s R sa -

RSEE rt nn nmaA t m- 6 ad aeoo e eA rl d EELL yeiai n rD u ; b e d wi l ehD oun BRPP th w t ih eN oh e chit t p etNt cu MPMM rt gn cnU cet eacs a m r U cl o UEAA oirno naeO nahi hl uert a h oO ear NRSS F eoic AegB Aet s Tpsros S TtB scg

)

2

(

n Y o d A i ns WE t ae HL a t TP i ea AM d nl PA a i u S R ed c E noi RR t rit

. UO c ocr e

_ S/ bi a OD r rdP PN i i a XA D AR E

1 2 f

EC E7 c

)

.. h);

,3c E cC33 T52 2* '

C

2q ~~ a ,) s

,Qu [S 4

j l 1 l1lI <Ill !lll1 .lIlll

ni Y ass s CS oi i NI cps cs ES i my iy UY pol pl QL oC a oa

,, EA t n t n

- RN o a oa FA s . s i ym im DF l u u NO ahi ai A mt t mt mni mi E aor ar P

G mt Gt

. Y T

)

so m g m

_ a Y f .f ir .

_ r C os os ey f e

- g N e l

_ o E el el rn p r U t pt puw ,m

_ P Q i mimb oea

_ E s a s and s s g DR ososat i n NF p p rewb

) i A mb mbGl ra d r N oaoa er .

e ut o GO NI c r c r e gh g g gk nt y

l nin I T y .y aiO y y r i LC l yl yL v l l e t o PE hl hl i h t

_ nM ML AL t k t k ne .h t t r o n eneecR n n a C la

(

SO C

o eoeh eC o M wM wwrS m M o

Q u

t

_ 1 n

_ - e

_ 2 m )

1 n 8

. o ot (

3 r i t s) d

- a3 e E v d 5 e( t L n n 1 l . c B E - u l . y e A ycr uo oeen ) r sf Tl a tl g rlh o t pt i 6

(

u ef c i a nm b c a nce t r n r i

g eu g oanc i ra u e o cxie o er ob e

l (

h mt a t msr a di r vr vG s o S oee i o rnd e R e ot moa

_ i N mch v s k w

_ d E O o gad of d e s a t y a V I rai n r t n R y oL l R I T f hl a f sni r z me TDA a aaw f k u af ANC eoeu; e ok t e b ro ri FTAO l h nQ l , st e n B fl ON L pyt n/ pnin r a -m ES mt aD mod e C r l a sf RSEE aig ai l G oe ei EELL snndl st ma w rr l BRPP iiee ak v a e t t py MPMM ecvt v ec e u k ns ml UEAA niaae no0 r q a op an NRSS Ovhll Ol3 p S L C u S o Y

A WE HL TP AM e e PA n c d S r a n E o f u RR b r o UO r u r S/ e S G OD t PN a . .

XA W a b E

3 O

82$

y2*.

Ey - w1 ha W

C n h wr ni n emm N

ES ont e e asass s oi a si n; .

UI sh rh1 ocps c csaes QS i wot ri my i . i i re EY s f nG pol py psnum RL ye f a oC a ol oyet i

FA ll d oh n t l t l h st

.to DA N

N ape nmt n .

t s .a oa s u oawa s n pr AF E

O 1 aaaogiym sl i 3b cparmt t ut l u ahi in aa n

i ay a1 h ot l nh e

mi m3t o P 1 al meamni mm m1 ne Y - raureaor ae a ort T I gcsgygmt G s GI maa e

t d i o s bi o a r p ; .

r es ms g pi oe es a

m re r

Y C yk s cl p um t i g N l ei ym st o E k e sl a e wyh s a r U npr P Q e - l t e e E w2 a nb h nh g DR noa .

wot n NF f ra mr y o

) i A oev1 ;

g l ye d r N .

l l rt e o GO t eo3 d ye el s a h aa ut NI i s - mki 1

u t ni I T s eI r ew n nsy i n LC n oll t o PE ol oer a mah nM ML p pnf we mme r h i i mt o AL m min Cl SO o ah ef t e e no

( a C cswpoo S t S am 1 n

- e e 2 m r e e) 1 n a ee s 3 r

. o e r

hh et rn b.(9 l t i t t h ao a s a t t t mo G E v L n BE k

e e l ml aa snI ni gf f id s

od eya5

.itg rn A r o Tl C r ei rt ov h marg t 1 en a i a . ,ht i t t n thl ckl en i

c w a

n o

s e nt a

gceioe8 c ama u pi n g u c wo . k onc o q ope noct r l ml i i e l S a il nnf noaeit o S d u k ae it crmadi rl l et t e a cnd i

d E N

O m

o m o

moa i esol s5 e moa o v mri ppl R

a V I T f r r rg hd mana r1 olr t I

TDA f f nl mt eame nfl ni ANC e . e et n i a o rnk o ms siesa nweh ert oaw FTAO l r l .

l s o f i ,at stl t st ON L pi pn pii d

ES mo mo 5 e eo pnin RSEE a v mxt ss t n gb d rmod e EELL s r ai aea el nson eac BRPP e st s e lpmhhaie niset s m e s a h r k ara ak v MPMM ec et c mit gel eee e UEAA n e no nie aniirirh rnt0 r NRSS OR Ol O wr S awh a m a w gO a3 p

)

d e

u n

i t

Y n A o WE C e HL (

n TP g t i AM e n n l PA n i e e n E

S r o

k n

mmr i oo o

RR b i i k d rh t l UO r r ef S s i S/ e D S e M OD t g PN a . .

n .

XA W c d I a E

3 4 O

,g o aEz z @g , CzZ .

- ;)

u ._7m g'sE

Y as a .

C nn nn N ao ao ES i i UI ct ct c c QS ir i r i i EY po po p p RL

op op o o

,' FA t t t t N oe oe o . o .

DA sl sl ss ss N ib ib ie i e AF i i s s O ad ad ay ay E me me ml ml P

Y m

an m ma ma T

an an a n C o C o C a C a m

a

_ Y .

r C y g N l t

_ o E l s r U a e P Q u v

_ E n r g DR n a n NF a h

) i A i d r N m f e

ut o GO NI e

s o

ni n I T e y y i LC e m l l t o PE l i h h nM ML

_ p t t t

- o AL m n n

_ Cl SO a t o o

_ ( a C S A M M

_ t n

_ 1

_ - e

_ 2 m s 1 n e

. o i e 3 r c g nt i er i n l E v L n pa sl a am - - l t -

B E osh w c ep pod i re t af ad eo nt ocevnd

- s A t t s i cf t d e e e eaiekd ot e htdl l e Tl a ni cy n ai rghl cl sr t e c t ad eb p

i sgun ee c i ii gmvmr

_ i st rti qe f vaedd u f ek e

_ g a rt sd pcrie f et engq ov

_ o eon e url b if i r une 0 pi

_ l p a ec hdi d at spoir hf 3 l

o

(

S ml mn c o h e esf rl ca i N t i p ae arscv el ef t g pl aeog a sul epii a e ros eeaaml

_ E el t g

_ d O yf hh rd a a V I

o f l f f fd t w h aeth gs R I T ol oni ooa s t onnga t fd5l on TDA a y oa1 o

ANC oh ne . r eirka ent e .

ef t itd fb nrh el ernh ciq FTAO

_ ON L l

pi n oi l t e pog l

pf arag s e o we f off amen p vids l b wt e ES mnr o RSEE mt i aac a a moeewr a a rt sorf o e gi mo mrrnin lf ri aagidil EELL s ei . ssh ssaath l s d saiot sl BRPP

_ MPMM ec r va e ees ac eay s wnc as pd n nu f a i nt d UEAA nenr nri nl n yl i mnooonQrc aiiwin/eo niiaiat emonnm NRSS O ria O ad O cab pd Skt t t aD pl O st t wsa

)

d e

_ u n

i s Y t e A n t WE o a

HL C r TP AM

( db s ne t PA n at c S o r u E i h e dd RR t sv oo UO s i n or S/ e FI FP

_ OD g PN n . .

XA I b c E

4 E @ "l 3c oo23 =

y2* ' E** "

,)

,Qo n

(0 $

d l

1 l

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description were pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of-Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. 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 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 the ODCM. Pursuant to Control 6.14, stbmit as a part of or concurrent with the next Semiannual Radioactive Effluent Release Report a complete legible copy of the ODCM including a revised figure (s) and table for the ODCM reflecting the new location (s).

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thernoluminescent dosimeter (TLD) is considered to be one phosphor; two or rrore phosphors in a packet are considered as two or more dosimeters.

Filin badges shall not be used as dosimeters for' measuring direct radiation. (The 40 stations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly.

The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading).

l (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 allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

O COMANCHE PEAK - UNIT 1 I 3/4 12-7 REV. O 3/89

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

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

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

(7) Lake Granbury shall be sampled near the letdown discharge end.at a distance beyond signifiant 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 the methodology and parameters in the ODCM.

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

l l

l REV. O O co"^"c"E ee^k - untT i i 3/4 12-8 3/89

O Di OC O p

/ 0 1

0 0,

1 0

0, 2

l a

e u

F( v

' a s

t s

i x

) e K1 L/ y I i a MCp 3 0 0 0 w 6 7 0 h

( 3 t a

p n

_ i r e

_ s t

_ n a o

_ w i

_ t ) g

_ a t n r e i t w k n

n e H , i

_ c S g r .

n I k 0 0 0 0 0 0 O d d

_ os F/ 0 0 0 0 0 0 G e C e i 0, 0, 0, 0, 0, 0, 0, o s l C n u yp p 0 0 0 0 0 1 2 2 t m ( 3 1 3 1 2 f e

- i a I b

_ 2 vS

_ 1 i y

.tl . a 3 c a e m at u E on l l

_ Li e a /

_ Bd m E

v i A an C TR or T) p O

1 A 4 ri L 'm 'l 0 ov U/ 2 f n Ci t E I C r f s T p a o

_ l R( P e A 9 e

_ v PS R u

_ e E 0 0 0 F l L ES 1 2 C a

_ g NA v

_ RC 0 n O 4 a i BR t RO s ,

r I i s o A t p s s e i i R h x T e y

. a

_ ) s w e

h

l . t

( pd a me

) ( p R/

1 0 0 0 0 0 0 0 2 0 0 0 as

_ 0 0 0 0 0 0 0 3 5 0 su r Ei 0, 0 4 0, 3 3 4 2 e Tc re t A p 0 1 1 eb a W(

2 t ay

. w

_ wa g g m n

_ i n/ k i1 n kC i np r i d r0 0 d0 o S 5 4 n I 9 1 r 0, S - 4 7 - o0 f Y, 4 9 8 0 5 b 1 3 3 a F3 I i 5 5 5 6 6 N 3 1 1 L A 3 - - - - - - 1 - - - ) )

N - n e o o n r - s s a *

A H M F C C Z Z I C C B (

O

(

$*. o a B2S" ~my , C m ya .o**

r RS

DC E p S(

S)

Tt C e U w D

O ,

R g Pk 0 0 0

/ 6 6 8

( Di OC O p F(

s i

s y

l )

a K1 n L/

A I 1 1 5 8 5 MC 1 1 1 e p l (

p m ) .

a D d S L e .

L sd l ( )

a t ues 1 t n e e u

- n o v b 2 e i e

1 m t H ,

yb

. n c S g a

4 o e I k 0 0 0 0 0 0 my r t F/ 3 6 3 6 3 5 a Ei e i 1 2 1 2 1 1 1 m L v D C /

B n p 11 A E f (

o C/

T p1 r C o t 0 p f i 0

m 05 s i E 31 e L T) i A ff t r L 'm oo i e U/

l w C1 ee i o I C uv b L T p l l a R( aa p A a PS vv C E aa ES 1 n NA 0 7 5 6 , ,

o RG 0 0 0 ss i O 0 t t t BR 0 0 0 ss c RO i i e I xx t A ee e

D yy aa ww hh t t aa pp

)

1 *

rr R/ 4 0 5 0 5 0 5 1 5 8 5 ee Ei 0 1 3 1 3 1 1 1 1 t t TC 0 aa A p W(

2 ww gg nn i i kk nn i i a rr t 0 S e dd 0 5 4 I B 6, 9 1 oo S - 4 7 - nn Y s 4 9 8 5 b 1 3 3 a L s 5 5 5 6 N 3 1 1 L ff A o 3 - - - - - 1 - - - I I N r - n e o n r - s s a *

A G H M F C Z Z I C C B *

$*. o aEst yN'ER -

- w1 7 o RS

I l

TABLE 4.12-1 (Continued) l TABLE NOTATIONS (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 nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.

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

(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 95%

probability with only 5% probability falsely concluding that a blank j observation represents a "real" signal.

1 I

4.66 sh LLD -

~

E V exp (- Aat) 2.22 x 100 l Where:

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

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

E - the counting efficiency (counts per disintegration), i V - the sample size (units of mass or volume),

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

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

t I

O J COMANCHE PEAK - UNIT 1 1 3/4 12-11 REV. O 3/89 l

l l

TABLE 4.12-1 (Continued)

TABLE NOTATIONS (Continued) 5 (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 1 posteriori (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.

I

((()

l I

( REV. O

\ COMANCHE PEAK - UNIT 1 I 3/4 12-12 3/89

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 APPLICABILlJ1: At all times.

ACTION:

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

b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20%

greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s),

via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was O , conducted. Pursuant to Control 6.14, submit as a part of or concurrent with in 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 RE0VIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental 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 B0UNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of tha garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1 Item 4.c. shall be followed, including analysis of control samples.

O REV. O COMANCHE PEAK - UNIT 1 I 3/4 12-13 3/89

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

APPLICABILITY: 4 all times.

ACTION:

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

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

SURVEILLANCE RE0VIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

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.

1 REV. O COMANCHE PEAK - UNIT 1 I 3/4 12-14 3/89

INSTRUMENTATION BASES O 3/4.3.3.4 RADI0 ACTIVE LIOVID EFFLUENT HONITORING 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 Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR 50.

3/4.3.3.5 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in 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 l

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

3/4.3.3.6 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of the second proposed Revision 1 to Regulatory Guide 1.23, "0nsite Meteorological Programs," April 1986.

i l

l l

l I'

REV. 0

, COMANCHE PEAK VNIT 1 I B 3/4 3-6 3/89 l

l l l

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

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

\

l O

i V

l 1

1 REV 0 COMANCHE PEAK - UNIT 1 I B 3/4 7-1 3/89

l 1

3/4.11 RADI0 ACTIVE EFFLUENTS ILASES J

(3 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble >

gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

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

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the 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. !

q V 3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, III. A and IV. A of 10CFR50, Appendix I. The Control implements the guides set !

forth in Section II.A of Appendix I. The ACTION statements 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 ,

l material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclides concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose calculation methodology and parameters in the ODCM 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 equations specified in the ODCM for calculating the doses due to the actual release rates of 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 I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

REV. O COMANCHE PEAK - UNIT 1 I B 3/4 11-1 3/89

RADIOACTIVE EFFLUENTS BASES QQS1 (Continued) '

I This control applies to the release of radioactive materials in liquid 1 effluents from each unit at the site. For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportional among the

~'

units sharing that system. j 3/4.11.1.3 LIOUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Readgaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. This requirement that the appropriate portions of this system be used when specified provides assurance that the. i 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 liquid O effluents from each unit _at the site. For units with shared Radwaste. Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system.

3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE i This control is provided to ensure that the dose at any time at and i beyond the SITE BOUNDARY from gaseous effluents from all units on the site .

will be within the annual dose limits of 10CFR20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10CFR20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE B0UNDARY, to annual average concentrations exceeding the limits specified in Table II of 10CFR20, Appendix B (10CFR 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE B0UNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The methodology for calculating doses for such MEMBERS OF THE PUBLIC, shall be given in the ODCM.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a O COMANCHE PEAK - UNIT 1 REV. O I B 3/4 11-2 3/89

i RADI0 ACTIVE EFFLVENTS l

BASES j O -

)

DDjiE (Continued) l l

MEMBER OF THE PUBLIC at or beyond the SITE B0UNDARY to less than or equal to j 500 mrems/ year to the whole body.or to less than or equal to 3000 mrems/ year i to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year. {

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

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LL0s).

Detailed discussion of the LLDs 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.

O l

i l

REV. O COMANCHE PEAK - VNIT 1 I B 3/4 11-3 3/89 O

1 RADI0 ACTIVE EFFLUENTS

~'\ BASES (U

3/4.11.2.2 DOSE - N0BLE GASES This control is provided to implement the requirements of Sections II.8, III.A and IV. A of 10CFR50, Appendix I. The control implements the guides set forth in :' action I.B of Appendix I. The ACTION statements 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 gaseous effluents to 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 calculational procedures based on models and i data such that the actual exposure of a MEMBER OF THE PUBLIC through i appropriate pathways is unlikely to be substantially underestimated. The dose '

calculation methodology and parameters established in 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 1

Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, I Appendix I, " Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for .

Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in ,

Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. j The ODCM equations provided for determining the air doses at and beyond the SITE B0UNDARY are based upon the historical average atmospheric conditions.

This control applies to the release of radioactive materials in gaseous l' effluents from each unit at the site. Since both units share the radwaste treatment systems, the gaseous effluents are proportioned among the units.

l

)

l O

b COMANCHE PEAK - UNIT 1 I B 3/4 11-4 REV. O 3/89

)

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - 10 DINE-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 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to 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 ODCM calculational methodology and parameters 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 of Gaseous 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 O Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclides pathways to man in the areas at and beyond the SITE B0UNDARY. The pathways !

that were examined in the development of the calculations were: (1) {

individual inhalation of airborne radionuclides, (2) deposition of l radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption'of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

l l

O COMANCHE PEAK - UNIT 1 I B 3/4 11-5 REV. O 3/89 l

l l

___..._._._m .__.......__....__.1 -- - -

I

1 I

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.4 GASE0VS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDVP SYSTEM and the PRIMARY PLANT 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 protions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, !

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. the specified limits governing the use of appropriate portions of the systems 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 effluents.

This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

O 4

l REV. 0 O- COMANCHE PEAK - UNIT 1 I B 3/4 11-6 3/89 I

RADI0 ACTIVE EFFLUENTS BASES O 3/4.11.4 TOTAL DOSE This control is provided to meet the dose limitations of 40 CFR Part 190 that have bben 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 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 THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405(c), is considered to be a timely request O and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

REV. O O co"^"c"E eeAx - unt' i i 8 3/4 11-7 3/89 ,

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES A ,

l 3/4.12.1 MONITORING PROGRAM 1

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 Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for 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 LLD is defined as an a oriori (before the fact) limit representing the capability of a ,

measurement system and not as an a posteriori (after the fact) limit for a '

particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found )j 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.

3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetatign (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/mz.

O COMANCHE PEAK - UNIT 1 I B 3/4 12-1 arv. o 3/89

RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 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 3 l

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

4 l

4 O ,

O COMANCHE PEAK - UNIT 1 I B 3/4 12-2 Rev. O 3/89 1

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

O '

SECTION 5.0 DESIGN FEATURES i

I 5-0

5.0 DESIGN FEATURES MAP DEFINING UNRESTRICTED AREAS AND EXCLUSION AREA B0UNDARY FOR RADI0 ACTIVE GASE0US AND LIOUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous ahti liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE B0UNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3.

The definition of UNRESTRICTED AREA used in implementing these Controls has been expanded over that in 10 CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the Exclusion-(fenced) Area Boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water 3 bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE B0UNDARY, 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.

I O

Os COMANCHE PEAK - UNIT 1 I 5-1 REV. O 3/89 w______________-_.

O R E

E R

E s) s.

r, A\r

\- A

. W g

\

/ 1 n

d; \

e s

a e / - P s

E

\

\ m u

/, ..c

.v i

\ !

s c / .n g w -

i a

\

g

\ a s

s e

e t.Is'-

g

\

g

.e$, '

~

/

K T.

R T A E P A R

~

gp) f O

(-

3 g

\%

S E

4, m,

Dl O A C

I V

R E

S

/:$ps-E M m *

.d\ ~

D E / D e

a

,9 av.\'

T A w z

C f O I

R \

R T ' S : \ b.,

S S +

e ' E s '.\

i m C f

\T %*

l a C (

t A

[f,/ T \ [

N g$s

)

= e 1

)

T T 0 E e .

eS 2 G f

I h s Y L R t g

R 0 OL A ' wi n A PPA F H 6 od D E S E T C 9 1

lei b Bu l

=

N S U S U A EA 0 D E 1 I

e*

r4 t

== o m

O L L t E E I

a6 ne o 5 B R R eT t W s em e

J a

c, e ._

Y E f T O A f

kl c si n taia re a n

E T B NP W ht e t KS I

EW V EE SO S t e T n .

o .

s r u

p n .C . A K K A W e C C E T ee v e

L

- A A L A vd e . P T T E L t aht r

. re ngf

- S H

S R U H D C I

a lpe o. s

- T T I S v s t

UU C eop 0 OQ f

( hb o

- N S U T at e

EEE O

8EME AR e E- ~ w mlo.

O SECTION 6.0 O ADMINISTRATIVE CONTROLS O

I 6-0

MMINISTRATIVE CONTROLS

] ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.3 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality and shall include copies of reports of the preoperational Radiological Environmental Monitoring Program of the unit for at least two years prior to initial criticality.

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

The missing data shall be submitted as soon as possible in a supplementary 1 report. l 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 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 l Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as requierd by control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1,; discussion of i 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 j 4.12-1 was not achievable.

A single submittal may be inade for a multiple unit station.

l One map shall cover stations near the SITE B0UNDARY; a second shall o include the more distant stations.

REV. O COMANCHE PEAK - UNIT 1 I 6-18 3/89 l

l I

ADMINISTRATIVE CONTROLS 1

O

\m/ SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality. l 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 B thereof.

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, Type A, 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 summary of hourly meterological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint frequency distributions of wind speed, wind direction, fl and atmospheric stability.** This same report shall include an assessment of V 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. l All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. Historical average meterological conditions or the meterological 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 l shall be performed in accordance with the methodology and parameters in the l OFFSITE DOSE CALCULATION MANUAL (0DCM).

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

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

REV. O COMANCHE PEAK - UNIT 1 I 6-19 3/89 I

o

l' ADMINISTRATIVE CONTROLS l

( SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases a~dn other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

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

l A listing of new locations for dose calculations and/or environmental I

monitoring identified by the Land Use Census pursuant to Control 3.12.2.

The Semiannual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Controls 3.3.3.4 or 3.3.3.5, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the Control limits.

l 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the 00CM:

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

radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the SORC and the approval of the Manager, Plant Operations.

REV. 0 Q COMANCHE PEAK - UNIT 1 I 6-20 3/89 l

i ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) (continued)

c. Shall be submitted to the Commission in the form of a complete, legible 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. -

O I

i REV. O COMANCHE PEAK - UNIT 1 I 6-24 3/89 )

I

O PART II CALCULATIONAL METHODOLOGIES O

I O

SECTION 1.0 LIQUID EFFLUENTS O The Comanche Peak Steam Electric Station, Units 1 and 2, is located on the Squaw Creek Reservoir which serves as the point of supply and discharge for the plant circulaf.ing water. Liquid releases are made via the Circulating Water Discharge Canal. Discharge pathways for the liquid radwaste sources are j shown in Figure 1.1. Although no significant releases of radioactivity are l expected from the Station Service Water System, this effluent pathway is monitored as a precautionary measure.

The liquid effluent radiation monitors shown in Figure 1.1 are part of the plant Digital Radiation Monitoring System (DRMS) supplied by GA Technologies.

Since all DRMS rronitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uCi/ml). The conversion factor for detector output from counts per minute to uC1/ml is determined during the calibration of each monitor and is input into the data base for the monitor microprocessor.

O 1.1 GENERAL METHODOLOGY FOR DETERMINING LIOVID EFFLUENT MONITOR SETPOINTS Normal liquid releases from the radwaste system will be batch type releases and will originate from the laundry holdup tanks and waste monitor tanks and terminate in Squaw Creek Reservoir. To ensure such discharges do not exceed the limits of 10CFR20, Appendix 8, Table II, Column 2 at the release point to the unrestricted area, as specified in Radiological Effluent Control 3/4.11.1.1, an in-line radiation detector (XRE-5253) monitors discharges to the circulating water discharge ,

canal. XhV-5253 is the isolation valve controlled by detector XRE- 1 5253. The isolation valve shuts automatically if the detector alarms or is placed out of serv 1ce. The methodology for determining the j setpoint for detector XRE-5253 is given in the following sections. It l should be noted that the liquid effluent monitor setpoint values as determined using the methodology from the following sections will be regarded as upper bounds for.the actual setpoint adjustments. That is, setpoint adjustments are not required if the existing setpoint level corresponds to a lower value than the calculated value. Setpoints may

,q be established at values lower than the calculated values, if desired.

V II 1-1 Rev. 0 3/89

_ - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . I

Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within l the normal operating range of the monitor.

1.1.1 Isotooic Concentration of the Waste Tank Determine the isotopic concentration of the waste tank to be released:

Ic 1-rc +g (c, + c, + c, + cy) [Eq. 1-1)

Where: Ic 1

- Sum of the concentrations of each radionuclides, i, i

in the waste tank (uCi/ml)

Ic - Sum of the concentrations of each measured gamma-8 1 8 emitter, g, (uCi/ml) as required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

Ca - concentration of alpha emitters as measured in the 1

most recent monthly composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (Sample analyzed for gross alpha only)

Cs = concentration of 89S r and 90S r as measured in the most recently quarterly 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 monthly composite sample (uci/ml) required by Radiological Effluent Control 3/4.11.1.1, Tabl e 4.11-1.

Ce F - concentration of 55F e as measured in the most recent quarterly composite sample (uci/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

1.1.2 Maximum Effluent Flow Rate (f)

The effluent discharge rate is determined from the number of radwaste system pumps running and their capacity. The radwaste system pumps that can be utilized to discharge liquid effluents to the circulating '

water discharge canal consist of the following:

Laundry Holdup and Monitor Tank Pump - 100 gpm l'

' Waste Monitor Tank Pump #1 - 100 gpm O

II l-2 Rev. 0 3/89

.___________-____a

Waste Monitor Tank Pump #2 - 100 gpm g Normally, only one waste tank will be discharged at a time. XRE-5253

\ is an in-line process monitor which, due to physical flow restrictions, allows a maximum flow rate of 46 gpm. As a worst case condition, the effluent flow rate (f) will be determined based on the capacity of one tank being pumped (100 gpm). This built in safety factor of 2.2 ensures that the effluent flow rate is not being underestimated. This maximum effluent flow rate of 100gpm will be used in the calculation of dilution factor for 1]_1 liquid radwaste system batch discharges.

1.1.3 Dilution of Liauid Effluents Due to Circulating Water Flow (F)

Since liquid effluent from the radwaste treatment system is mixed with circulating water prior to being discharged to Squaw Creek Reservoir, the setpoint for detector XRE-5253 is a function of the circulating water flow rate. The maximum circulating water flow rate per plant is 1.1 million gpm. This is determined from the Ingersoll-Rand pump curves (Fig.1.3) which indicate a flow rate per pump of 275,000 gpm.

The actual circulating water dilution flow is given by:

A Q F(diluting flow) = (275,000 gpm/ pump) x (# of pumps) x SF [Eq. 1-2]

Where: SF - Safety Factor of (.9). This compensates for flow fluctuations from the rate predicted by the circulating water pump curves (Fig. 1.3).

1.1.4 Actual Dilution Factor (ADF)

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

ADF - (f + F)/f [Eq. 1-3]

Where: f - 100 gpm F - (275,000 gpm/ pump) x (# of pumps) x SF [Eq. 1-2]

O V

II l-3 Rev. 0 3/89 i

i l

NOTE: If radioactivity is detected in the Reservoir, an adjusted n, circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See section 1.1.6 for the calculation of F' (Eq. 1-6). j 1.1.5 Reauired Dilution Factor (RDF)

The required dilution factor ensures that the maximum permissible 1 concentrations expressed in 10CFR20, Appendix B, Table II, Column 2*,

and a total concentration of dissolved or entrained noble gases of 2 x 10 -4 uCi/ml are not exceeded during a discharge. l RDF = ( I (C /MPC })

i

- (I8(c /MPc s g) + (c,/MPc, + c,/MPc, + c /MPc, e

1

+ c7,/MPCp ,)) [Eq. 1-4]

Where: MPC i * - Maximum Permissible Concentration of Radionuclides i All other variables and subscripts are previously defined.

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

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

i O

II 1-4 Rev. 0 3/89 l

l 1.1.6 Vooer Setooint Limit for Detector XRE-5253 C [Eq. 1-5]

g = (ADF/RDF) x { C g Where: C1 w - The liquid waste effluent monitor alarm setpoint.

This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC-level releases (uCi/ml).

All other variables are as previously defined.

As a further consideration, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isotopes.

It is therefore necessary to account for recirculation of previously discharged radionuclides. This is accomplished as follows-l F' = F (1 - { (C{/MPC )) (Eq. 1-6]

l 1

Where: F' = Adjusted Circulating Water Flow Rate C'i - Concentration of radionuclides i in the Reservoir Q) (uCi/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 l structure as indicated by location SW6 on Table 3.1 and Figure 3-1 of this manual.

MPCi * = Maximum Permissible Concentration of Radionuclides i F = (275,000 gpm/ pump) x (# of pumps) x SF 1

NOTE: If C'j is less than LLD then F' = F and no adjusted flow rate need be considered in the calculation of ADF. The LLD values used for this determination shall be the LLD-values for water given in Radiological Effluent Control 3/4.12.1, Table 4.12-1.

see footnote on page II l-4 l

11 1-5 Rev. 0 3/89 l

l l _ ._ . _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ - _ _ -

1 When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be those referenced in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, Table Notation 2. Figure 1.2 is a representative energy l spectrum response for the RD-33 type detector used in XRE-5253. This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per j minute and microcuries per milliliter remains relatively constant. In fact between 137Cs and 60Co, the total change in sensitivity is approximately 7%. Because this is well within the accuracy of measurement, there is no need to change the software sensitivity for given varied effluent concentrations. However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required.

O v

I l

O II 1-6 Rev. 0 3/89

1.2 DOSE CALCULATION FOR LIOUID EFFLUENTS

(- For implementation of Radiological Effluent Control 3/4.11.1.2, the i dose commitment from the release of liquid effluents will be calculated at least once per 31 days and a cumulative summation of the total body'and organ dose commitments will be maintained for each calendar quarter and each calendar year. The cumulative dose over the desired time period (e.g., the sum of all doses due to releases during a 31 day period, calendar quarter, or a calendar year) will be calculated using the following equation:

D T

=ID k + ED(lake) , [Eq. 1-7) k m Where: DT = the dose commitment to the total body or any organ due to all releases during the desired time interval (mrem).

Dk = the dose commitment received by the total body or any organ during the duration of batch release k(mrem). The equation for calculating Dk is given in Section 1.2.1 (Eq. 1-8). '

D(lake)m - the dose commitment received by the total body or any organ during the desired time period, m, (normally m = 31 days) due to the buildup in the lake of previously discharged radionuclides. The equation for calculating D(lake)m is given in Section 1.2.2 (Eq. 1-11).

1.2.1 Calculation of Dose Due to a Batch Release The dose commitment to the total body or any organ due to a batch release will be calculated using the following equation:

D k

=IA gtt kC g kF (Eq. 1-8) 1 O

v II 1-7 Rev. 0 3/89

Where: tk - the time duration of the batch release k (hrs)

Cik - the isotopic concentration (uCi/ml) of radionuclides i found in the pre-release sample for batch release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample.

For 89S r, 90S r, 3g, 55 eF and alpha emitters, the last measured value will be used in the dose calculation.

Fk - the near field average dilution factor during 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 flow past the monitor into the circulating water.

Fk - averaae undiluted liauid effluent flow rate circulating water flow rate A - the site related ingestion dose commitment p it Q factor for the total body or any organ,T , for each identified gamma or beta emitter (mrem /hr per uCi/ml), A g is calculated as follows: '

Ah - 1.14x105 (U y/D, + U g BFg) DF {Eq. 1-10]

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

O II 1-8 Rev. 0 3/89

l l

DFj - adult dose conversion factor

()

w

' " " d' ""'" d "

Table E-11, Ref. 2 (mrem /pCi ingested)

Dw - Dilution factor from the near l field area within mile of I the release point to the potable water intake for the adult water consumption, 1.0 for CPSES. (unitiess) l Calculated values for A h are given in Table 1.1.

i 1.2.2 Calculation of Dose Due to Radionuclides Builduo in the Lake i The dose contribution due to buildup of previously discharged radionuclides in the lake must be considered in the committed !

dose calculation only if they are detected in the water of Squaw Creek Reservoir or in fish from Squaw Creek Reservoir.

V The contribution to the total dose due to this buildup is determined as follows:

D(lake)m = 1.14x10-4( I DF i (C'iwU w + C'igUg))t [Eq. 1-11]

1 Where: 1.14 x 10-4 = units conversion factor C'jw - concentration of radionuclides i in the i

reservoir as measured at the circulating f water intake structure shown as location SW6 on Table 3.1 and Figure 3.1 of this manual (pCi/1)

C'jr - concentration of radionuclides i in fish sampled from Squaw Creek Reservoir from location F1 on Table 3.1 and Figure 3.1 of this manual. (pci/kg) t - 744 hrs (31 days) or other time period of interest (hr)

All other variables are previously defined.

II 1-9 Rev. 0 3/89

I NOTE: .This calculation 'is only required if activity is detected in water and/or fish in excess of the l appropriate LLD values given in Radiological

Effluent Control 3/4.12.1, Table 4.12-1. If the i measured activity in water or fish is less than the required LLD values, the concentration for {

that particular pathway is assumed to be zero.

l l

l O

i i

O II 1-10 Rev. 0 3/89

1.3 DOSE PROJECTIONS FOR LIOVID EFFLUENTS nV Radiological Effluent Control 3/4.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit to 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 dose projection.

At least once every 31 days, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate l portions of the Liquid Radwaste Treatment System shall be used to I reduce radioactivity levels prior to release.

O 1

l l

O II 1-11 Rev. 0 3/89 i l

(

y]/ TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/mD '

ISOTOPE B0NE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 C-14 3.15E+04 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 Na-24 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 P-32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.20E+06 Cr-51 0.00E+00 0.00E+00 1.49E+00 8.94E-01 3.29E-01 1.98E+00 3.76E+02 Mn-54 0.00E+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 >

Mn-56 0.00E+00 1.20E+02 2.12E+01 0.00E+00 1.52E+02 0.00E+00 3.82E+03 Fe-55 8.87E+02 6.13E+02 1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 Fe-59 1.40E+03 3.29E+03 1.26E+03 0.00E+00 0.00Z+00 9.19E+02 1.10E+04 ,

1 l Co-58 0.00E+00 1.51E+02 3.39E+02 0.00E+00 0.00E+00 0.00E+00 3.06E+03

~

Co-60 0.00E+00 4.34E+02 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.16E+03 Ni-63 4.19E+04 2.91E+03 1.41E+03 0.00E+00 0.00E+00 0.00E+00 6.07E+02 Ni-65 1.70E+02 2.21E+01 1.01E+01 0.00E+00 0.00E+00 0.00E+00 5.61E+02 Cu-64 0.00E+00 1.69E+01 7.93E+00 0.00E+00 4.26E+01 0.00E+00 1.44E+03 En-65 2.36E+04 7.50E+04 3.39E+04 0.00E+00 5.02E+04 0.00E+00 4.73E+04 Zn-69 5.02E+01 9.60E+01 6.67E+00 0.00E+00 6.24E+01 0.00E+00 1.44E+01 Br-83 0.00E+00 0.00E+00 4.38E+01 0.00E+00 0.00E+00 0.00E+00 6.30E+01 Br-84 0.00E+00 0.00E+00 5.67E+01 0.00E+00 0.00E+00 0.00E+00 4.45E-04 Br-85 0.00E+00 0.00E+00 2.33E+00 0.00E+00 0.00E+00 0.00E+00 1.09E-15 Rb-86 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.03E+04 Rb-88 0.00E+00 2.99E+02 1.59E+02 0.00E+00 0.00E+00 0.00E+00 4.00E-09 4 l

O N/

Rb-89 0.00E+00 1.98E+02 1.39E+02 0.00E+00 0.00E+00 0.00E+00 1.15E-11 I Sr-89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 II 1-12 Rev. O <

3/89 I

_ _ _ _ _ - _ _ _ -__U

, i I f' l l

-s TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml)

ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Sr-90 1.18E+06 0.00E+00 2.88E+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04 1

Sr-91 8.79E+02 0.00E+00 3.55E+01 '0.00E+00 0.00E+00' O.00E+00-4.19E+03 '

Sr-92 3.33E+02 0.00E+00 1.44E+01 0.00E+00 0.00E+00 0.00E+00 6.60E+03 1 1

Y-90 1.38E+00 0.00E+00 3.69E-02 0.00E+00 0.00E+00 0.00E+00 1.46E+04 ;

Y-91m 1.30E-02 0.00E+00 5.'04E-04 0.00E+00 0.00E+00 0.00E+00 3.82E-02 .I Y-91 2.02E+01 0.00E+00 5.392-01 0.00E+00 0.0"0E+00 0'.00E+00 1.11E+04 i

'Y-92 1.21E-01 0.00E+00 3.53E-03 0.00E+00 0.00E+00 0.00E+00 2.12E+03 Y-93 3.83E-01 0.00E+00 1.06E-02 0.00E+00 0.00E+00 0.00E+00 1.22E+04 ;i Zr-95 2.77E+00 8.88E-01 6.01E-01 -0.00E+00 1.39E+00 0.00E+00 2'.82E+03 Zr-97 1.53E-01 3.09E-02 1.41E-02 0.00E+00 4.67E-02 0.00E+00 9.57E+03 Nb-95 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 Mo-99 0.00E+00 4.62E+02 8.79E+01 0.00E+00 1.05E+03 0.00E+00 1.07E+03 Tc-99m 2.94E-02 8.32E-02 1.06E+00 0.00E+00. 1.26E+00 4.07E-02 4.92E+01 Tc-101 3.03E-02 4.36E-02 4.28E-01 0.00E+00 7.85E-01 2.23E-02 1.31E-13 Ru-103 1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+01 0.00E+00 2.31E+03 Ru-105 1.65E+00 0.00E+00 6.51E-01 0.00E+00 2.13E+01 0.00E+00 1.01E+03 Ru-106 2.95E+02 0.00E+00 3.73E+01 0.00E+00 5.69E+02' O.00E+00 1.91E+04 Ag-110m 1.42E+01 1.31E+01 7.80E+00 0.00E+00 2.58E+01 0.00E+00 5.36E+03 Te-125m 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.00E+00 1.11E+04 Te-127m 7.05E+03 2.52E+03. 8.59E+02 1.80E+03 2.86E+04 0.00E+00 2.36E+04 Te-127 1.14E+02 4.11E+01 2.48E+01 8.48E+01 4.66E+02 0.00E+00 9.03E+03 Te-129m 1.20E+04 4.47E+03 1.89E+03 4.11E+03 5.00E+04 0.00E+00 6.03E+04 l- Te-129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.00E+00 2.47E+01 11 1-13 Rev. 0 3/89 l

l l

(}

v TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml)

ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Te-131m 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.00E+00 8.74E+04 Te-131 2.05E+01 8.57E+00 6.47E+00 1.69E+01 8.98E+01 0.00E+00 2.90E+00 Te-132 2.62E+03 1.70E+03 1.59E+03 L 87E+03 1.63E+04 0.00E+00 8.02E+04 I-130 9.01E+01 2.66E+02 1,05E+02 2.25E+04 4.15E+02 0.00E+00 2.29E+02 I-131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 1-132 2.42E+01 6.47E+01 2.26E+01 2.26E+03 1.03E+02 0.00E+00 1.22E+01 I-133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.00E+00 2.64E+02 I-134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+01 0.00E+00 2.99E-02 I-135 5.28E+01 1.38E+02 5.10E+01 9.11E+03 2.22E+02 0.00E+00 1.56E+02

() Cs-134 3.03E+05 7.21E+05 5.89E+05 0.00E+00 2.33E+05 7.75E+04 1.26E+04 Cs-136 3.17E+04 1.25E+05 9.01E+04 0.00E+00 6.97E+04 9.55E+03 1.42E+04 Cs-137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 Cs-138 2 69E+02 5.31E+02 2.63E+02 0.00E+00 3.90E+02 3.85E+01 2.27E-03 Ba-139 9.00E+00 6.41E-03 2.64E-01 0.00E+00 5.99E-03 3.64E-03 1.60E+01 Ba-140 1.88E+03 2.37E+00 1.23E+02 0.00E+00 8.05E+01 1.35E+00 3.88E+03 Ba-141 4.37E+00 3.30E-03 1.48E-01 0.00E+00 3.07E-03 1.87E-03 2.00E-09 Ba-142 1.98E+00 2.03E-03 1.24E-01 0.00E+00 1.72E-03 1.15E-03 2.78E-18 La-140 3.58E-01 1.80E-01 4.76E-02 0.00E+00 0.00E+00 0.00E+00 1.32E+04 1 i

La-142 1.83E-02 7.55E-03 2.07E-03 0.00E+00 0.00E+00 0.00E+00 6.08E+01 Ce-141 8.01E-01 5.41E-01 6.15E-02 0.00E+00 2.52E-01 0.00E+00 2.07E+03 Ce-143 1.41E-01 1.04E+02 1.16E-02 0.00E+00 4.60E-02 0.00E+00 3.90E+03 Ce-144 4.18E+01 1.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04 i r

(m,)N Pr-143 1.32E+00 5.28E-01 6.52E-02 0.00E+00 3.05E-01 0.00E+00 5.77E+03 !

11 1-14 Rev. 0 l 3/89 i

_q TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per-uCi/ml)

ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI-Pr-144 4.31E-03 1.79E-03 2.19E-04 0.00E+00 1.01E-03 0.00E+00 6.19E-10 Nd-147 9.00E-01 1.04E+00 6.22E-02 0.00E+00 6.08E-01 0.00E+00 4.99E+03 W-187 3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E+00 8.34E+04

)

Np-239 1.28E-01 1.25E-02 6.91E-03 0.00E+00 3.91E-02 0.00E+00 2.57E+03

)

O O

II l-15 Rev 0 3/89 I

1.4 SERVICE WATER EFFlVENT RADIATION MONITORS 1RE-4269/4270 rw Concentration of radioactive material in the service water effluent line normally is expected to be insignificant. Therefore, the monitor alert alarm setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. To this end, the alarm setpoint will be initially established at three (3) times background until further data can be collected. If this effluent stream should become contaminated, radionuclides concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows: i

'l sw =(ICg)+M 8

[Eq. 1-12]

Where: Csw - the Service Water effluent monitor alarm setpoint.

Cg - the concentration of each measured gamma emitter ,g, observed in the effluent (uCi/ml) f DF-[(Cj/MPCj)-thedilutionfactorrequiredto ensure maximum permissible concentrations are not exceeded. l For this release pathway no additional dilution is available.

Therefore, if the calculated DF is greater than 1.0 any releases occurring via this pathway will result in a violation of Technical Specification 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 i methodology given in Section 1.2, with the near field average dilution factor, F k, equal to 1.0.

O V

II 1-16 Rev. 0 3/89 4

_ . _ _ _ _ _ _ _ . _ _ = _ . _ . - _ . _ _ . _ _ . __ _ - _

1.5 TURBINE BUILDING SUMP EFFLUENT RADIATION MONITOR 1RE-5100 p The purpose of the turbine building sump monitor (1RE-5100) is to

{

monitor turbine building sump discharges and divert this discharge from )

the Low Volume Retention Pond to the Waste Water Holdup Tanks if l radioactivity is detected. Because the only sources of water to the turbine building sump are from the secondary steam system, activity is expected only if a significant primary-to-secondary leak is present.

Since only turbine building sump water with no detectable radioactivity ,

(as defined in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1) is allowed to go to the Low Volume Waste Pond, the monitor setpoint l should be established as close to background as practical to prevent !

spurious alarms and ye't alarm should an inadvertent radioactive release occur. To this end, the setpoint will be initiaily established at three (3) titaes background until further data can be collected. Then, 1 if this setpoint is exceeded,1RE-5100 will direct valves 1RV-5100A and B to divert discharges from the turbine building sumps to the Waste l l

Water Holdup Tanks where the effluent can then be sampled and released l

in a batch mode to Squaw Creek Reservoir in accordance with Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. If a O re81eactive re, ease 4s made frem a waste weter he,8 9 tamx. 8 eses e e l

to this release shall be calculated in accordance with the methodology given in Section 1.2.

j O

II 1-17 Rev. 0 3/89

1 l

I 1.6 DEFINITIONS OF COMMON LIOUID EFFLUENT PARAMETERS

'9 SECTION OF TERM DEFINITION INITIAL USE ADF Actual Dilution Factor (unitiess). This is defined 1.1.4 as' the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.

A g The site related ingestion dose commitment factor 1.2.1 l to the total body or any organ, T , for each l identified gamma or beta emitter, i. l (mrem /hr per uCi/ml)

BFj Bioaccumulation factor for radionuclides, i, in fish 1.2.1 l from Reg. Guide 1.109. (pCi/kg per pCi/1)

Ca The concentration of alpha emitters in liquid waste 1.1.1 as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.

(uCi/ml)

CeF The concentration of 55Fe in liquid waste as 1.1.1 ;

measured in the analysis of the most recent t quarterly composite sample required by !

y Radiological Effluent Control 3/4.11.1.1,

) Table 4.11-1. (uCi/ml) {

i I

cg The concentration of each measured gamma emitter, g 1.1.1 l in the waste tank as measured in the analysis of the sample of each batch as required by 'l Radiological Effluent Control 3/4.11.1.1, Table 4.11-1 (uCi/ml)

Ci The concentrations of radionuclides, i, in the 1.1.1 waste tank. (uCi/ml)

C'i The concentration of radionuclides i in the 1.1.6 Reservoir as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Control 3/4.12.1, Table 3.12-1. This sample is taken at the Circulatory Water Intake Structure as indicated by location SW6 on Table 3.1 and Figure 3-1 of this manual. (uCi/ml)

C'jf The concentration of radionuclides i in fish 1.2.2 sampled from the reservoir from location F1 on Table 3.1 and Figure 3-1 of this manual (pCi/kg).

b)

%)

II l-18 Rev. 0 3/89

1

=

Cik The isotopic concentration of radionuclides i 1.2.1 bi

'V found in the pre-release sample for batch release k. Concentrations are determined .

i ghe gquid effluent sample.primarily For WSr, W from gamma isotopic anl H; Fe and alpha emitters, the last !

measured value will be used. (uCi/ml)

C'jw The concentration of radionuclides i in the 1.2.2 ;

reservoir as measured at the circulating water )

intake structure shown as location SW6 on i Table 3.1 and Figure 3-1 of this manual l (pCi/l). )

Cw 1 The liquid waste effluent monitor alarm setpoint. 1.1.6 This corresponds to the gamma concentration f in the undiluted waste stream which after j dilution would result in MPC-level releases. '

(uCi/ml)

Cs The concentration of 89S r and 90Sr in liquid 1.1.1 waste as measured in the analysis of the most l recent quarterly composite sample required by '

Radiological Effluent Control 3/4.11.1.1, Table 4.11-1 (uci/ml)

Csw The Service Water effluent monitor alarm setpoint. 1.4 i (uCi/ml)

Ct The concentration of 3H in liquid waste as 1.1.1 l

measured _in the analysis of the most recent i monthly composite sample required by !

Radiological Effluent Control 3/4.11.1.1, !

Table 4.11-1 (uCi/ml) j DFj Adult dose conversion factor for radionuclides, '

1.2.1 i, from Reg. Guide 1.109 (mrem /pCi ingested)

Dk The dose commitment received by the total body 1.2 or any organ during the duration of batch release k of liquid effluents. (mrem)

D(lake), The dose commitment received by the total body or 1.2 or any organ during a desired time period, m, I

due to the buildup in the lake of previously discharged radionuclides. (mrem)

DT The total dose commitment to the total body or any 1.2 organ due to all releases of liquid effluents during a desired time interval. (mrem) i O

II 1-19 Rev. 0 3/89

Dw Dilution factor, from the near field area within 1.2.1

( 1/4 mile of the releasae point to the potable water intake for adult water consumption, 1.0 for CPSES (unitiess) f Effluent' flow rate. (gpm) '

l.1.2 F Circulating water flow rate (or dilution flow rate). (gpm)

F' Adjusted circulating water flow rate to account for 1.1.4 buildup of radionuclides in the circulating water due to previous releases. (gpm)

Fk The near field average dilution factor during a 1.2.1 liquid effluent release (unitiess). This is I

defined as the ratio of the average undiluted liquid waste flow to the average circulating water flow during the release.

MPCa Maximum Permissible Concentration

of a mixture 1.1.5 of unidentified alpha emitters. (uCi/ml)

MPCF e Maximum Permissible Concentration

of 55F e. 1.1.5 (uCi/ml) {

fg MPC g Maximum Permissible Concentration

of each 1.1.5 Q identified gamma emitter, g. (uC1/ml)

MPCj Maximum Permissible Concentration

of 1.1.5 i radionuclides, i. (uCi/ml) l i

MPCs Maxgmum Permissible Concentration

of a mixture 1.1.5 of WSr and 9USr. (uti/ml)

MPCt Maximum Permissible Concentrat. ion

of 1.1.5 tritium (JH) (uCi/ml) ;

I SF Safety Factor of 0.9. This compensates for flow 1.1.3 fluctuations from the rate predicted by the circulating water pump curves.

MPCs are given in 10CFR20, Appendix 8, Table II, l Column 2. Values are given for each isotope in l both a soluble and insoluble form. The most l conservative (lowest) value for egch isotope should be used. A value of 2x10-* uCi/mi for dissolved or entrained noble gas shall be used.

O II l-20 Rev. 0 3/89

i RDF Required Dilution Factor (unitiess). This is 1.1.5 O defined as the dilution factor that ensures the maximum permissible isotopic concentrations expressed in 10CFR20, Appendix B, Table II, t

Column 2, are not exceed during a discharge.

tk 1.2.1 The time duration of batch release'k. (hours)

Uf Adult fish consumption. (kg/yr) 1.2.1 Uw Adult water consumption. (liters /yr) 1.2.1

-1 O

l l

l 1

O II l-21 Rev. 0 3/89

il il I 1Ijl S

I V

W C

fI fT Hyt 1

L F TTD.

1 0 AC E 2 2 L PA TC A

t p WOE "g Mte I tc lo ODT fs RY LAE OA O

t u u NP o O F_R D e 9 la LM _

A P n"ics GG i.

t. d na t

Lv " L J

u'h 8

- 2 4 O 2 S r 8" C F I

/ ne _

e .

o u :

Y n E e K i

e -

n n

l u -

o t r o v o e og t t w a r l e

te W h e n n

e

\t o t

t u

. ec u e i T 9

7 2

OC ar D > - _

4 *

"~E Z "E KE I t e k P- ee , E y

-" # a wne r g LM m" ;

Lv 4 t c k e II e in p1 dm 1

AP GG a c s In le. uk 5G e e _

W W R t Au n e sNe 3 S S

SA 1N N SA S

2IN

[

2y 2 ' '

t e -

~ - k e

e

- e 1 _

I I

A A H - T T A TR n "

IR NT U

T IT N

U k" a t

J A E w~ A n ee L t L" 2 r At GP A'

n L D *.

0 G nWTo tt G' '

_ J a 08 0 _ t C

0" C 34 2

3 8 Tl Q

se.s n 4

t ei n L wee - e e AM _

IS I 1 r k GP 4 ..teF - et Dn a 0G

a. e,sv es Lv

inWT t 00 i

t P e 3 C 34 C 2 s r a A 2

s e st EA -

t E s

- a e L -

a wT AM O x e p GP - O u 0 G i

t s d 00 Tg, s e no 0, 02 u wM 5 ~ a t k A. A.

2 e E E

~ ~ e 4 o , Ga p Lte

~ - o g

~

t s-i le n3 n e e e. A (e G s (gl I + 3 l ,lll li: gIi a

t og o i 50 E D N 83 n 1 a

S Y

A .

W > )

)

M h ) n e g 2 A A.

EE TH 1 MP PG M P )M 1 G p& LAe NT G0 GP t t te nn1 A r EA 1 0 G i n o e . GG U. P E o0 b 3 00 t aeB o N 5o I (l ( 36 D 3 S F E R ' eg ((

e"e n a op 1

n'-

t ,

FG U LL LL.

tb d AA , a t

,, bed .n ERAG I it B

a GG , wte s AA GG Tw """ h

(

DH F t

I 80 72 T W .e e8 O

t7 UC 91 S 9 QS I t 1 1 1 3 1 1 LD . .

45 oo ..

eo NN eN t

7mN rG - O wgo t

50 40 30 "a 20 - ~

T / .~%

) ,' *

%m ..

/ [.'*% %

"' {

/ Cal l7 ,,-

10 1 9 i Go" t g a 7

6 5

0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 GAMMA PHOTON ENERGY, MeV ENEP,GY RESPONSE TO GA!MA RADIATIONS

, FOR RD-33 TYPE DETECTOR Figure 1.2 1The broken ooroon at to curve was generated from early isotococ cahorsoons vang a enamber at simitar geometry.

anna on one gamma per assintegrason.

\ l 11 1-23 Rev. 0 3/89

c i

i I I I I I [ l I I I I !

MM M

.h .7 [

a s .s , , ,

l . _ _ n l g g _c , w_,. ._. ..--.

4 . gg 7 :l --

g . _ . _ _ _ . .- ._. ._ _ _ . ._ _ .__ . _ , _

_. _ _ _ _ _ n

~ - -

-s . = -

t _p.

=

I. _-

s. _ _

n a : -

._ _ ~ .-- --

5 .~ !

a .

.- _r--- _

5 -

.-w

, _ _= 5 - - .

Qs _.

. _5 6

p_ _._

! a

._ __ - .___5 - = _=.. _ .-

Q -

d=.g.

n CE = '.

l

=a 2 - .

e.

z

~ z e .

Q z w e

g -

=_ -

l

= - - _-_ 1 -. -

_ J

= .w _--

g --= -#s *2%

3 ._

Z . - z ... .

. _ _ .._. _ x.. . . . . . _ . .._ --

. . =

X- ;

...V-_ A. . . .

_ _. ._- .- . =

a

__;_Y,,, _ . - - ._

.._-.=c _ .p_.g. ,.::. __. :__.

._n

. ._,7- _ _ . _ _.--

.f)-;. _ . ._ _ .._3 g_..

. . _ _ _ _ ..._. _. . . . . _ . . _ . . . . _ . . e -

~

_ d- _= .- ;-

s ._.- _

gg. + _

~

ce

"_\.---

gg.. -= _.; ._(--

_ = . _ .\.__._

-W_ - . .

+.g.a a .__

.-__--i l' .-__...__ . - _ - -

-- ; =_ ...a

m. n a . . _ . . . _ . _ . .

gag g ,,

_ __=

_=_: :.:.. :: _%. .,

C .E E g 3 3 e. e. e. e. o. e. e. e i g,

g t g i i 1 m m i-I a

t i f i a i

~~-

a*.

e e.

2

e. e 3 $ = e. S 2 a*3 Jae mi avsM mmJ.

eEI i i 8 f l ' ' ' ' ' ' '

II l-24 Rev. 0 3/89

O t o kn s

is o

p g un d H a di l a

me sg low t i s s

e

& T Hi t

a H yr 'er e Oak h no" r s yn k

C 3

ec y r

1 E

r a d w n o sa r dM" n

n u dn T L E

u h e P ud ( u N aS v a n a ,

N L e L a L r A

R - e t H

- a C la )3 t

s Wge N

)

1 ga r T[n I

L 2 A 5 J

r s

, E -

s Tinhc t

R D

2 5

R s a

a s -

luD E i

gI (M s ll ;- - c R v ir X n (

- u C b k a o - n L p gg1ll llglliIIlg!l IIl ggllI a s r m T ineuS d M t a

E aa r e T DWg r r H S r in o e y Y osled it n 5 a r oni d S l iu ok a n G

FRB Mnaner u a

N - h eTi m t l L I

s o e S a h W D t S4 o r E 1 t s l r s B o CER a r o )

Oh ' L l

ek n Wtoage M.

in 2 Ou a it E r s t

n t aa N 5 Re F nr a o ks e O

l sT 2 P D r g,b t N r > ' iok e pc r , i Mn s-n ee A 5 E o Dse e Ta E R

a s d g H E T o r vP t

s E s n ar C R S F l

oE a ( e- oo Ct S N (

X o W v I A l n A k W

F x R n a

D T

D I e g

U a Q

I r

o t

L S I

r

glg5l llgI ilIllillll lll l e t

o t a

in a s a l n

Domu r e m d t ou c r n

o nR e ce o C mleAga t a eez r e

ppsn r t h o an Wair mki S S D.

na ps ia a nr v e.

t t

o

- Ed n s e

d e t ni o ml lv

(-

- sC. D A a a v W r L e p okn E s u

t aa N d N lo l

m. rT o

l A c H

o e 3 etg

,tr.a s

ap M 7s 3

pe at a v s -

T S

H C

s la n

t s Wa. En R N ig e de lW I

a p A s W E t

sn ao

% R D d a

WC R O )

d i

H

)

1

(

U * ?< ,

NCD

SECTION 2.0 J GASE0US EFFLUENTS 2.1 GASE0US EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values as determined using the methodology in the following sections will be regarded as upper bounds for the actual setpoint adjustments., That is, setpoint adjustments are not-required if the existing setpoint level corresponds to a lower value than the calculated valua. 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 monitor reading associated with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and the setpoint recalculated.

At CPSES, all gaseous effluents are released to the atmosphere through the two common Plant Vent Stacks (Stacks A & B) (Figure 2.1). Due to I 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 result in a conservative ground-level release.

Each Plant Vent Stack is equipped with a Wide Range Gas Monitor (WRGM) and a Particulate, Iodine, and Noble Gas Monitor (PIG). These monitors are part of the plant Digital Radiation Monitoring System (DRMS) supplied by GA Technologies. Since all DRMS monitors provide a digital !

output, they may be calibrated to readout in the appropriate engineering units (i.e., uCi/ml). The conversion factor for detector output 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.

O II 2-1 Rev. 0 3/89

The WRGMs are designated as monitors XRE-5570A and XRE-55708 for Stacks l

A and B, respectively. Each WRGM consists of a low range (10-7 to 10-1 uCi/ml), mid range (10-4 to 102 uCi/ml), and high range (10-1 to 105 uCi/ml) noble gas activity detector. The WRGMs also have.an effluent release rate channel which uses inputs from the appropriate WRGM noble gas activity detectors and the plant vent stack i flow rate detectors (XFT-5570A1/B1) to provide an indication of noble l gas release rate in uCi/sec. Alarm setpoints are' established for the WRGM effluent release rate channel to fulfill the requirements of Radiological Effluent Control 3/4.3.3.5. Exceeding the WRGM effluent release rate channel high alarm setpoint also initiates automatic termination of Waste Gas Decay Tank releases.

The stack 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-5567B 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 required. Therefore, a methodology is provided for calculating the PIG noble gas monitor setpoints. '

Additionally, methodologies are provided for calculating setpoints for the PIG particulate and iodine channels, although these channels are not required by the Radiological Effluent Controls Program.

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

control function for termination of Waste Gas Decay Tank releases.

1RE-5503 monitors the Containment atmosphere and provides the only automatic control function for termination of Containment vents or purges.

I I

O I II 2-2 Rev. O l 3/89

2.1.1 Dose Rates Due to Noble Gases For implementation of Radiological Effluent Control 3/4.11.2.1.a, the dose rate to the total body and skin of an individual at the SITE B0UNDARY due to noble gases shall be calculated as follows:

A. Calculate the total body dose rate due to noble gases D = (X/Q) I KQ [Eq. 2-1]

(no, ole gases)

Where: Dt - the total body dose rate at the SITE B0UNDARY due to noble gases (mrem /yr)

(T/Q) - the highest annual average relative concentration at the SITE B0UNDARY (3.3 x 10-6 sec/m3 in th?

NNW sector at a distance of 1.29 miles from the plant *.)

NOTE: The annual average X7Q is also used in determining setpoints for containment purge or vent as required by Technical Specification 3.3.3.1.

Ki = total body dose factor due to gamma emissions -

from noble gas radionuclides i from Table 2.1 (mrem /yr per uCi/m3 )

Qi - the total release rate of radionuclides i from the plant vent stacks (uci/sec)

(See C below for calculation of Qi)

8. Calculate the skin dose rate due to noble gases D, = (X/Q) I (L1 + 1.1 M ) Q (Eq. 2-2]

(noble gases)

Where: Ds - the skin dose rate at the SITE BOUNDARY due to noble gases (mrem /yr)

Reference CPSES FSAR, Section 2.3.5.2.

O -

II 2-3 Rev. 0 3/89

Li - the skin dose factor due to beta emissions from noble gas radionuclides i from Table 2.1 (mrem /yr per uCi/m3) 1.1 - conversion factor of mrem skin dose per mrad air dose.

Mi - air dose factor due to gamma emissions from noble gas radionuclides i from Table 2.1 (mrad /yr per uCi/m3)

All other terms are as previously defined.

C. Calculation of the Qi term Qi is defined as the total release rate (uci/sec) of radionuclides i from the plant vent stacks. Qi is given by:

Qi*hXivFv [Eq. 2-3]

Where: Xi y - the concentration of radionuclides i present at each plant vent stack (uCi/cm3)

Fy - the flow rate at each plant vent stack (cm3/ sec) v - index over all plant vent stacks

{

The concentration of radionuclides i present at each plant I vent stack monitor due to all release sources (e.g., continuous and batch sources), Xjy, is calculated using Eq. 2-4. This calculation is performed for each plant vent stack using the-- 2 I

estimated concentration and flow rate for each individual stack.

Xi cFe+ (1/2)XiB FB Xiy =

Fe + (1/2) FB [Eq. 2-4]

Where: Xi c - The concentration of radionuclides i in the continuous release stream at each stack as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2 (uC1/cm3),

The samples are taken from each plant vent stack at the WRGM skid.

i

)

II 2-4 Rev. 0 i

3/89

Fc - The continuous flow rate contribution of each plant stack (cm3/ sec). These flow rates 3

(Q are measured directly in each plant vent stack (XFT-5570Al/81).

XiB - The concentration of radionuclides i in the ;

batch release as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. These samples are taken prior to release from the confinement to be released.

FB - The estimated flow rate contribution associated with the release of the batch source (cm3/sec) 1/2 - factor to account for distribution of the batch release to each plant vent stack, assuming uniform distribution of the batch release between both stacks.'(unitiess)

NOTE: If there_is no batch release source, FB and XiB are zero, and Xi y - X i c-The flow rate at each plant vent, Fy, is given by:

O Fy - Fc + (1/2) FB [Eq. 2-5]

NOTE: If there is no batch release source, FB is zero, l and Fy - Fc-2.1.2 Plant Vent Stack Noble Gas Activity Monitors XRE-5570A/B (low ranae noble aas activity) and XRE-5567A/B These channels may be used for establishing noble gas activity setpoints when no automatic control functions are required by Radiological Effluent Control 3/4.3.3.5. The alarm setpoint for these channels will be calculated using Eqs. 2-6 and 2-7. These calculations will be performed for each plant vent stack.

Kgy 500 x SF x AF = CV [Eq. 2-6}

D t t Cg = the lesser of <

X gy 3000 x SF x AF = GV [Eq. 2-7]

D, D, II 2-5 Rev. 0 3/89

Where: CG - The alarm setpoint for each plant vent noble gas activity monitor (uCi/cm3)

O Xcy - (noble gases) X i y

- the concentration of noble gases present at each plant vent stack due to the combined sources as calculated from the radionuclides 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 (uCi/cm3) .

(See Section 2.1.1.C for the determination of Xjv).

500 - the dose rate limit to the total body of an individual in an unrestricted area due to noble gases. (mrem /yr) 3000 - the dose rate limit to the skin of the body of an individual in an unrestricted area due to noble gases. (mrem /yr)

SF - Safety Factor of 0.5 applied to compensate for statistical fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks. (unitiess) l AF - Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitiess). This factor will limit the dose rate contribution from each stack to 1/2 the limit for the site.

1 II 2-6 Rev. 0 4 3/89

l 2.1.3 Elant Vent Effluent Release Rate and Samole Flow Rate Monitors !

4 A. Plant Vent Stack' Release Rate Monitors XRE-5570 A/B (Effluent Release Rate Channel)

The WRGM effluent release rate channels monitor the release rate of radioactive materials from each plant vent stack by combining inputs from the WRGM noble gas activity channel (uci/cm3) indication and a stack flow rate (cm3/sec) indication (XFT-5570A1/81) to yield an effluent release rate-(uCi/sec). i By establishing an alarm setpoint for this monitor, an increase in either noble gas' activity or stack. flow rate will cause an alarm trip. The WRGM effluent channel also provides an ;

automatic control function for termination of Waste Gas Decay Tank Releases. The setpoint for each plant vent effluent release rate monitor will be calculated as using Eq. 2-8. This calculation will be performed for each plant vent stack.

Cf-CG Fv [Eq. 2-8]

where: Cf - The setpoint for each plant vent stack effuent release rate monitor. (uCi/sec)

All other terms are previously defined.

B. Samoler Flow Rate Monitors XFT-5570A2/B2 The WRGMs are designed to sample isokinetically from the: plant vent stacks. . Isokinetic sample flow is maintained automatically by the monitor microprocessor. The sampler flow rate monitors are designed such that if there is a loss of sample flow, the stack monitor automatic control functions are initiated. The loss of sample flow alarm setpoints are established permanently in accordance with vendor specifications, i

O <

11 2-7 Rev. O.

3/89

2.1.4 Auxiliary Buildina Ventilation Exhaust Monitor XRE-5701 Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, ACTION 34, allows for the Auxiliary Building Ventilation Duct Monitor (XRE-5701) to be used as a backup to the WRGM for monitoring Waste Gas Decay Tank (WGDT) releases. XRE-5701 monitors WGDT releases by measuring activity in the Auxiliary Building Vent Duct and providing an automatic control function for termination of WGDT releases.

If required, the alarm setpoint for ME-5701 will be calculated using the following methodology. The alarm setpoint calculation is based on the following assumptions:

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

(2) the source contribution due to other sources in the auxiliary building are negligible relative to the source contribution due to the release of the waste gas decay tank.

The concentration at the auxiliary building vent monitor during a waste gas decay tank release is calculated as follows:

X,g=

g iGDT GDT

1ABV ABV [Eq. 2-9]

GDT + FABV From assumption (2) above, (XiGDT FGDT>> XiABV FABV).

this equation can be reduced to:

~

laux iGDT AT [Eq. 2-10]

aux Where: XiGDT - the concentration of noble gas radionuclides i (uC1/cm3) in the WGDT as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. This sample is taken prior to release from the WGDT.

FGDT - the flow rate contribution associated with the release of a WGDT (cm3/ sec)

I Q

NJ l II 2-8 Rev. 0 3/89

XiABV - the concentration of noble gas radionuclides i p (uCi/cm3 )'in the auxiliary building ventilation

() stream due to sources other than the waste gas decay tanks (see assumption (2), above)

FABV - the flow rate contribution associated with sources in the auxiliary building other than the waste gas decay tanks. This is the measured or estimated flow rate in the auxiliary building vent duct.

Faux - the total flow rate at the auxiliary building ventilation monitor during the release of a waste gas decay tank - FGDT + FABV Xi aux - the concentration of noble gas radionuclides i at the auxiliary building ventilation monitor during a waste gas decay tank release.

From Section 2.1.1, Item C, the release rate for radionuclides i at each plant vent stack may be given by:

Xi v Fy - X ic Fc + (1/2) XiB FB [Eq. 2-11]

For this case of a batch release of a waste gas decay tank, make the following substitution into this equation (see assumption (1),

above):

XiB F B - X iaux Faux [Eq. 2-12]

Therefore, Xi y Fy - X ic Fe + (1/2) X aux i Faux [Eq. 2-13]

Now, assuming that the source contribution from the auxiliary building vent (due to the release of the waste gas decay tank), X aux i Faux, is much greater than the source contribution due to all continuous sources to each plant vent stack, Xi cFe, then Xi y Fy is 4 approximately equal to 1/2 X aux i Faux.

O II 2-9 Rev. 0 3/89

l l

l p Xjv Fv - (1/2) X aux i Faux [Eq. 2-14]

b At the alarm setpoint concentration at each plant vent monitor, Xi v -

Cg.. Also, the Auxiliary Building Ventilation monitor alarm setpoint, Caux, corresponds to the noble gas concentration, Xi aux, that would result in the alarm setpoint concentration at each plant vent stack monitor. Since plant vent monitor alarm setpoints are calculated separately for each stack, the maximum of the two plant vent stack monitor alarm setpoints should be used in this calculation for Co.

Therefore, '

XG max Fy - (1/2) Caux Faux [Eq. 2-15] q Solving for Caux yields:

1 l

Caux - 2 C Gmax Fv [Eq. 2-16] j Faux .

1 Where: Caux - the Auxiliary Building ventilation exhaust monitor alarm setpoint (uCi/cm3)

CG max = maximum of the monitor setpoints for the two stacks.

All other variables are previously defined.

2.1.5 Containment Atmosohere Gaseous Monitor 1RE-5503 For implementation of Technical Specification 3/4.3.3.1, the alarm setpoint for the Containment Atmosphere Gaseous Monitor for Containment Ventilation Isolation will be calculated using the hilowing methodology. The alarm setpoint calculation is based on the following assumptions:

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

(2) the source contributions due to all other continuous sources to the plant vent are negligible relative to the source contribution from containment building purge or vent operation.

II 2-10 Rev. 0 3/89

From Section 2.1.1, Item C, the release rate for radionuclides i at each

{

plant vent stack may be given by: )

l O (

Xjy Fy - Xi c Fe + (1/2) XiB fB [Eq. 2-11]

For this case of a batch release due to a containment purge or vent operation, make the following substitution into this equation (see i assumption (1), above)

XiB FB - Xi cont fcont [Eq. 2-17] I Where: Xi cont - the concentration of noble gas radionuclides i j (uCi/cm3) in the containment release stream as !

sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. This sample ,

is taken prior to release from the Containment Building.

Fcont - the flow rate contribution associated with the release of the containment atmosphere (cm3/sec)

O Therefore, I

Xi y Fy - Xi c fc + (1/2) X cont i Fcont [Eq. 2-18] I Now, assuming that the source contribution from the containment purge or vent, X icont Fcont, is much greater than the source contribution due to all continuous sources to each plant vent stack, Xi c Fc, then Xi y Fy is approximately equal to 1/2 Xi cont fcont-L Xi y Fy - (1/2) X cont i Fcont [Eq. 2-19]

4 O

U II 2-11 Rev. 0 3/89

At the alarm setpoint concentration at each plant vent monitor, Xi y =

q Cg. Also, the containment atmosphere gaseous monitor alarm setpoint, C/ Ccont, corresponds to the noble gas concentration, Xi cont, that would result in the alarm setpoint concentration at each plant vent stack monitor. Since plant vent monitor alarm setpoints are calculated separately for each stack, the maximum of the two plant vent stack monitor alarm setpoints should be used in this calculation for C G-Therefore, CG max Fy - (1/2) Ccont Fcont [Eq. 2-20]

Solving for Ccont yields:

Ccont . 2C Gmax Fv [Eq. 2-21]

Fcont Where: Ccont - the containment atmosphere gaseous monitor alarm setpoint (uCi/cm3)

CG max = maximum of the monitor setpoints for the two stacks.

O tj All other variables are previously defined.

2.1.6 Dose Rates Due to Radioiodines. Tritium, and Particulate Organ dose rates due to iodine-131 and iodine-133, tritium, and all l

radioactive materials in particulate form with half-lives greater i than eight days will be calculated to implement the requirements of Radiological Effluent Control 3/4.11.2.1.b as follows:

D0 =W I pq ii (Eq. 2-22]

IP&T Where: Do = the total organ dose rate due to iodine-131, iodine-133, particulate with half-lives greater than eight days, and tritium. (mrem /yr)

O II 2-12 Rev. 0 3/89

Pi - pathway dose rate parameter factor for radionuclides, i, I (for radioiodines, particulate, and tritium) for the l d inhalation pathway in mrem /yr per uCi/m3* (Table 2.2)

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

All other variables are previously defined.

2.1.7 Plant Vent Stack Iodine Monitors XRE-5575A/B The setpoint for the Plant Vent Stack Iodine Monitors should be established to ensure compliance with Radiological Effluent Control 3/4.11.2.lb. These setpoints are not required' by Radiological Effluent Control 3/4.3.3.5, Table 3.3-8. The methodology used performs dose rate calculations in accordance with Section 2.1.6 and compares them with the Radiological Effluent Control dose rate limit l of 1500 mrem /yr to any organ for compliance. An allocation factor (AF) and safety factor (SF) are also utilized for this determination. Additionally, the ratio of the dose rate due to only I-131 to the dose rate due to I-131 and I-133 is included as a factor in the determination since the stack iodine monitor utilizes a single channel analyzer set on the I-131 photopeak (i.e., only I-131 is detected, not all iodines). The equation for calculating the !

Iodine Monitor Setpoint for each stack, CI , is:

{

C 7

= X 7y 1500 x AF x SF I-13 = 3M G79) [D I-131 [Eq. 2-23]

U D D o

(*1 ) o Q7 ) I

The latest NRC guidance has deleted the requirement to determine P i for the ground plane and food pathways. In addition, the critical age group has been changed from infant to child. The methodology used for determining values of Pi is given in Appendix A. l O

L II 2-13 Rev. 0 3/89

i Whero: CI = The setpoint for each plant vent stack Iodine Monitor O (uCi/cm3)

I XIV = (iodines) X i v

.. - the concentration of radioiodines present at each plant vent stack due to'the combined sources as calculated from the radionuclides 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. (uCi/cm3)

(See Section 2.1.1.c for the determination'of Xi v). -l

! 1500 - the dose rate limit to any organ due to iodine-131, tritium and particulate with half-lives greater l than eight days (mrem /yr) 01131 = the organ dose rate due to I-131 calculated using Eq. 2-22 considering only I-131.

DI - the organ dose rate due to I-131 and I-133 calculated using Eq. 2-22 considering only I-131 3 and I-133.

All other variables are previously defined.

2.1.8 Plant Vent Stack Particulate Monitors XRE-5568A/B The setpoint for the Plant Vent Stack Particulate Monitors should be established to ensure compliance with Radiological Effluent Control l 3/4.11.2.1.b. The methodology used performs dose rate calculations in accordance with Section 2.1.6 and compares them with the technical specification dose rate limit of 1500 mrem /yr to any organ for compliance. An allocation factor (AF) and safety factor (SF) are also utilized for this determination. The equation for calculating the Particulate Monitor Setpoint for each stack, Cp, is:

Cp = X py 1500 x AF x SF = 375 (Xpy) (Eq. 2-24]

O o II 2-14 Rev. 0 3/89

3 Where: Cp - The setpoint for each plant vent stack-Particulate Monitor (uCi/cm3)'. i XPV " (particulate) X i y ,

- the concentration of particulate present at I each plant vent stack due to the combined sources 1 as calculated from the radionuclides concentrations determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Centrol 3/4.11.2.1, Table 4.11-2. (uC1/cm3).

All other variables are previously defined.

I l

l O ,

1 l

1 I

I O

G II 2-15 Rev. 0 3/89

TABLE 2.1 DOSE FACTORS FOR EXPOSITRE TO A SEMI-INFINITE CLOITD OF NOBLE GASES

Isotope y-Body *** (K) 8-Skin ***(L) y-Air **(M) 8-Air **(N)

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 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 i Xe-135m 3.12E+03 7.11E402 3.36E+03 7.39E+02 ,

Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 :

Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 !

Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l

O

Values taken from Reference 2, Table B-1

- mrad-m*

uC1-yr

- - mrem-m3 uC1-yr l l O II 2-16 Rev. 0 3/89 ;

i

2.2 GASEOUS EFFLUENT DOSE CALCULATIONS 2.2.1 Dose Due to Noble Gases

( For implementation of Radiological Effluent Control 3/4.11.2.2, i the cumulative air dose due to noble gases to areas at and beyond the SITE BOUNDARY will be calculated at least once per 31 i days and a cumulative summation of the air doses will be maintained for each calendar quarter and each calendar year. !

l The air dose over the desired time period will be calculated as '

follows: l DY = air dose due to gamma emissions from noble gas radionuclides (mrad) l Dy - 3.17 x 10-8 (jgr) I gases) Mj Q'j (Eq. 2-25]

Where: 3.17 x 10-8 = the fraction of a year represented by one second l Q'i = the cumulative release of radionuclides i during the period of interest. (uci)

)

(Q'i = Qj (uti/sec) x release duration

]'

(sec))

Q'i is based on the noble gas activities in 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.

D6 = air dose due to beta emissions from noble gas radionuclides (mrad)

D8-3.17x10-8(g) E g33,)Nj Q'i (Eq. 2-26]

Where: Nj = f.he air dose factor due to beta emissions from noble gas radionuclides i from Table 2.1 (mrad /yr per uCi/m3),

All other variables are previously defined.

l

(.-

II 2-17 Rev. 0 '

3/89

Note: If the methodology in this section is used in determining dose to an individual rather than air dose s due to noble gases, substitute Kj for Mj, (Lj +

1.1 Mj) for Nj, and the Annual Average X/Q values l from Table 2.7 for the highest annual average relative concentration (X/Q)attheSITEB0UNDARY.

2.2.2 Dose Due to Radioiodines. Tritium, and Particulate For implementation of Radiological Effluent Control 3/4.11.2.3, l the cumulative dose to each organ of an individual due to iodine-131, iodine-133, tritium, and particulate with half-lives greater than 8 days will be calculated at least once per l 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:

]

Op - dose due to all real pathways to organ, o, 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 (mrem).

D = I 3.17 x 10 -8 g, I RP gei (Eq. 2-271 P

PATHS [\ IP&T I I i

Where: W' - the dispersion parameter for estimating the dose 1 to an individual at the location where the combination l of existing pathways and receptor age groups indicates the maximum potential exposures. Locations of interest are listed in Tabla 2.5, W' - X/Q for the inhalation pathway in sec/m3 X/Q is the annual average relative concentration at the location of interest. Values for X/Q are listed in l Table 2.4. If desired, the highest individual receptor X/Q valve may be used, or O

LJ II 2-18 Rev. 0 3/89 l

R W' - D/Q for the food and groundplane pathways in m-2, D/Q is the annual average deposition at the location i

\ of interest. Values for D/Q are listed in Table 2.4.

If desired, the highest individual receptor D/Q value q may be used. l NOTE: For tritium, the dispersion parameter, W' is taken as the annual average X/Q values from Table 2.4 for i inhalation, food and ground plane pathways.

RPi ,a,o - dose factor for radionuclides i, pathway p, age group a and organ o, in mrem /yr per uCi/m3 for the inhalation pathway and m2(mrem /yr) per uCi/sec for food and groundplane pathways, except for tritium which is '

l mrem /yr per uCi/m3 for all pathways. The values for RPi ,a,o for each pathway, radionuclides, age group and organ are listed in Table 2.3*.

Q'i - cumulative release of radionuclides, i, during the ,

period of interest (uCi). Q'i is based on the activities measured in each plant vent stack from the

p. analyses of the particulate and iodine samples j required by Radiological Effluent Control 3/4.11.2.1,

]

Table 4.11-2.

]

l I&PT - Iodines, particulate with half-lives greater than l l

eight days, and tritium. These are the isotopes over which the summation function is to be performed.

PATHS - the real pathways of exposure to individuals at the locations of interest as indicated in Table 2.5.

The methodologies used for determining values of RPi ,a,o for each pathway are given in Appendices B through F.

II 2-19 Rev. 0 3/89

1

)

l 2.2.3 Dose Pro.iections for Gaseous Effluents l

, Radiological Effluent Control 3/4.11.2.4 requires that appropriate j subsystems of the Gaseous Radwaste Treatment Systems be used to reduce i releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE B0UNDARY would exceed, in a 31-day period, either:

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

The following calculational method is provided for performing this dose j projection. '

At least once every 31 days the gamma air dose, beta air dose and the maximum organ dose for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated

( unusual releases during the period for which the projection is made, k such as Waste Gas Decay Tank releases. If these projected doses exceed !

any of the values listed above, appropriate portions of the Gaseous Waste Processing System shall be used to reduce radioactivity levels prior to release.

2.2.4 Dnjie Calculations to Succort Other Requirements For the purpose of implementing the requirements of Radiological Effluent Control 6.9.1.4, the Semiannual Radioactive Effluent Release Report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents from the station during the !

previous 6 months of operation. This assessment shall be a summary of the doses determined in accordance with Section 1.2 for doses due to liquid effluents, Section 2.2.1 for air doses due to noble gases, and Section 2.2.2 for doses due to iodines, tritium., and particulate.

This same report shall also include an assessment of the radiation l O Rev. O II 2-20 3/89 i

doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the SITE B0UNDARY. This y' assessment shall be performed in accordance with the methodologies in Sections 1.2, 2.2.1, and 2.2.2, using either historical average or l concurrent dispersion and deposition parameters for the locations of interest, and taking into account occupancy factors. All assumptions j and factors used in the determination shall be included in the report. l For the purpose of implementing Radiological Effluent Control 3/4.12.2 dose calculations for the new locations identified in the land use census shall be performed using the methodology in Section 2.2.2, i 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 l use census changes, the critical location (i.e., the location where an I individual would be exposed to the highest dose) must be reevaluated for the nearest residence, the nearest milk animal, and the nearest i vegetable garden. Additionally, when a location is identified that g yields a calculated dose 20% greater than at a location where V environmental samples are currently being obtained, add the new location within 30 days to the Radiological Environmental Monitoring l locations described in Section 3.1 of this manual.

l l For the purpose of implementing Radiological Effluent Control 3/4.11.4, the total annual dose to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by summing the annual doses determined for a member of the public in accordance with the methodology of Sections 1.2, 2.2.1, and 2.2.2 and the direct radiation dose contributions from the units and from outside storage tanks to the particular member of the public.

This assessment must be performed in the event calculated doses

from the effluent releases exceed twice the limits of Controls 3/4.11.1.2, 3/4.11.2.2, or 3/4.11.2.3. This assessment will be l included in the Semi-annual Radioactive Effluent Release Report to be I

submitted 60 days after January 1 of the year after the assessment was required. Otherwise, no assessments are required.

O U

Rev. 0 II 2-21 3/89

1 I

For the evaluation of doses to real individuals from liquid releases, j p the same calculation methods as employed in sect' ion 1.2 will be used. j However, more encompassing and realistic assumptions will be made l 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 radionuclides concentrations. For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as employed in sections 2.2.1 and 2.2.2 will be used. In section 2.2.1, the total i body dose factor should be substituted for the gamma air dose factor (Mj) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the ;

meteorological conditions, and the consumption of food'. Data obtained from the latest land use census should be used to determine locations for evaluating doses. The results of the Radiological Environmental i Monitoring Program will be included in determining more realistic doses based on actual measured radionuclides concentrations.

The dose component due to direct radiation may be determined by I calculation or actual measurement (e.g., thermoluminescent dosimeters, micro-R meter, etc.). The calculation or actual measurement of direct I radiation shall be documented in the Special Report that must be j submitted if this determination is required. 1 l

l V

Rev. O II 2-22 3/89

i l

TABLE 2.2 PATHWAY DOSE RATE PARAMETER (Pi)* j

BASED ON THE INHAIATION PATHWAY FOR THE CHILD AGE GROUP l ORGAN DOSE FACTORS XUCLIDE l-....--... -..............-....--..-.......--...............--.--.... ,

l BONE LIVER T. BODY THYROID KIDNEY LUNC GI-LLI f

H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 2.60E+06 1.14E+05 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 ,

CR.51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 1 MN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 1 FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 1 I

FE.59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 CO.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB-86 0.00E+00 1.98E+05 1.14E+05 0,00E+00 0.00E+00 0.00E+00 7.99E+03 O ,

SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR.90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR.95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB 95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03c 6.14E+05 3.70E+04 RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03' 6.62E+05 4.48E+04 ,

~ ~~~~~ ~~ ~~ ~~ ~~ ~~ ~

kb.555 5$35kIbb b$bbkIbb 5$59kIb5 b$bbkhbb 5$55k$bh"~i$d3kIb7 5$59k+bb AG.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 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 1.92F*04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1 131 4.8' 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 )

............... .............................................................. j I.133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 l CS.134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 !

CS.136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 '4.18E+03 CS.137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 )

BA.140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 ;

CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 j 1

('~\ CE.144 6.77E+06 ' 12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 g ,) 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

.._.................................................Rev:-0"-***"'**** i II 2-23 3/89

l l

O)

\,,, TABLE 2.3 PATHWAY DOSE FACTORS AGE CROUP: ALL PATHWAY: GROUND PLANE l ORGAN DOSE FACTORS NUCLIDE l.-..... -...........-

l T. BODY SKIN H.3 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 CR-51 4.65E+06 5.50E+06 MN.54 1.39E+09 1.62E+09 FE-55 0.00E+00 0.00E+00 FE.59 2.73E+08 3.21E+08 Co.58 3 79E+08 4.44E+08 Co.60 2.15E+10 2.53E+10 NI-63 0.00E+00 0.00E+00 ZN-65 7.47E+08 8.59E+08 RB.86 8.97E+06 1.03E+07

,0 ...............................

SR-89 SR-90 2.16E+04 2.51E+04 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 RU.103 1.08E+08 1.26E+08 l RU.106 4.22E+08 5.06E+08 AG.110M 3.44E+09 4.01E+09 TE.125M 1.55E+06 2.13E+06 TE.127M 9.17E+04 1.08E+05 TE-129M 1.98E+07 2.31E+07 I.131 1.72E+07 2.09E+07 I.133 2.45E+06 2.98E+06 CS-134 6.86E+09 8.00E+09 CS-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 1.54C+07 CE.144 6.96E+07 8.05E+07 PR 143 0.00E+00 0.00E+00 f N~

ND.147 8.39E+06 1.01E+07 Rev. 0 II 2-24 3/89

I l

l i

O k_

s TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHVAY: GRASS. COW-MILK i

.............................................................................. I l ORGAN DOSE FACTORS WUCLIDE 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. 91 F.+09

.............................................................................. l CR.51 0.00E+00 0.00E+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 l MN.54 0.00E+00 8.40E+06 1.60E+06 0.00E+00 2.50E+06 0.00E+00 2.57E+07 FE.55 2.51E+07 1.73E+07 4.04E+06 0.00E+00 0.00E+00 9.66E+06 9.93E+06 FE.59 2.97E+07 6 M7Et97 2.67E+07 0.00E+00 0.00E+00 1.95E+07 2.32E+08 CO.58 0.001+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 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 ZR.95 9.41E+02 3.02E+02 2.04E+02 0.00E+00 4.74E+02 0.00E+00 9.57E+05 .

NB.95 8.24E+04 4.58E+04 2.46E+04 0.00E+00 4.53E+04 0.00E+00 2.78E+08 l 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+08 TE.129M 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.00E+00 3.02E+08 I-131 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.00E+00 1.12E+08 1-133 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.00E+00 6.04E+06 CS.134 5.64E+09 1.34E+10 1.10E+10 0.00E+00 4.34E+09 1.44E+09 2.35E+08 CS.136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.92E+07 1.18E+08 CS.137 7.37E+09 1.01E+10 6.60E+09 0.00E+00 3.42E+09 1.14E+09 1.95E+08 BA.140 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.94E+04 5.54E+07 CE.141 4.84E+03 3.27E+03 3.71E+02 0.00E+00 1.52E+03 0.00E+00 1.25E+07 CE.144 3.57E+05 1.49E+05 1.92E+04 0.00E+00 8.85E+04 0.00E+00 1.21E+08

{ 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

! Rev. 0 l

t II 2-25 3/89

\d TABLE 2.3 PATHWAY DOSE FACTORS AGE CROUP: TEEN PATHWAY: GRASS-COW-MILK l ORGAN DOSE FACTORS SUCLIDEl.........-.--.--.-....----.-.--.-----..--..---......................-

l BONE LIVER T. BODY THYROID KIDNEY LUNG CI . LI.I H-3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 P.32 3.15E+10 1.95E+09 1.22E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09 CR.51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 KN 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 FE-59 5.19E+07 1.21E+08 4.68E+07 0.00E+00 0.00E+00 3.82E+07 2.86E+08 CO-58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.10E+08 CO-60 0.00E+00 2.78E+07 6.27E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 NI-63 1.18E+10 8.36E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN.65 2.11E+09 7.32E+09 3.42E+09 0.00E+00 4.69E+09 0.00E+00 3.10E+09 FF3 86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.00E+00 0.00E+00 -7.00E+08 r SR 89 2.68E+09 0. 00E4-00 7.67E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08

\-"# SR.90 6.62E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 Y 91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06

.............................................................................. J ZR 95 1.65E+03 5.21E+02 3.56E+02 0.00E+00 7.65E+02 0.00E+00 1.20E+02 NB-95 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E+00 3.34E+08 RU.103 1.81E+03 0.00E+00 7.75E+02 0.00E+00 6.39E+03 0.00E+00 1.51E+05 RU.106 3.76E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06 AG.110M 9.64E+07 9.12E+07 5.55E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 TE.125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 0.00E+00 0.00E+00 8.87E+07 TE 127M 8.45E+07 3.00E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.11E+08 TE-129M 1.10E+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.00E+00 4.14E+08 I.131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 I.133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.00E+00 9.09E+06 CS.134 9.83E+09 2.31E+10 1.07E+10 0.00E+00 7.35E+09 2.81E+09 2.88E+08 CS.136 4.49E+08 1.77E+09 1.19E+09 0.00E+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.21E+09 0.00E+00 6.06E+09 2.36E+09 2.54E+08 BA-140 4.87E+07 5.97E+04 3.14E+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 CE.144 6.59E+05 2.73E+05 3.54E+04 0.00E+00 1.63E+05 0.00E+00 1.66E+08 ,

PR.143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 I w

ND.147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.12E+05 l Rev. O II 2-26 3/89

d TABLE 2.3 PATHWAY DOSE FACTORS ACE GROUP: CHILD PATHWAY: GRASS.CCW-MILK

)

l l ORGAN DOSE FACTORS i NUCLIDE l.....................................................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG CI.LLI 55'b[bbb+bb((5hkb5i[$h$b5(($hE$5(($hk$$$[$$$$$1[$hhA$$~

P.32 7.77E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09- .

CR 51 J 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 KN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.89E+06 0.00E+00 1.76E+07 FE.55 1.12E+08 5.94E+07 1.84E+07 0.00E+00 0.00E+00 3.36E+07 1.10E+07 FE.59 CO.58 1.20E+08 1.95E+08 9.70E+07 0.00E+00 0.00E+00 5.65E+07 2.03E+08 CO.60 0.00E+00 1.21E+07 3.72E+07 0.00E+00 0.00E+00 0.00E+00 7.08E+07 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 0.00E+00 0.00E+00 0.00E+00 1.07E+08 ZN-65 RB.86 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.00E+00 1.94E+09 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 0.00E+00 0.00E+00 0. 00E+00 2.57E+08 SR.90 1.12E+11 0.00E+00 2.84E+10 0.00E+00 0.00E+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 NB.95 3.84E+03 8.43E+02 7.51E+02 0.00E+00 1.21E+03 0.00E+00 8.80E+05 l RU-103 3.18E+05 1.24E+05 8.86E+04 0.00E+00 1.16E+05 0.00E+00 2.29E+08 !

4.29E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 0.00E+00 1.11E+05 )

RU.106 9.25E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 0.00E+00 1.44E+06 AG.110M 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE.125M 7.39E+07 2.00E+07 9.85E+06 2.07E+07 0.00E+00 0.00E+00 7.13E+07 TE.127M 2.08E+08 5.61E+07 2.47E+07 4.98E+07 5.94E+08 0.00E+00 1.69E+08 TE-129M 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 0.00E+00 3.31E+08 I.131 1.31E+09 1.31E+09 7.46E+08 4.34E+11 2.16E+09 0.00E+00 1.17E+08 I.133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.00E+00 8.58E+06 CS.134 2.27E+10 3.72E+10 7.85E+09 0.00E+00 1.15E+10 4.14E+09 2.01E+08 CS.136 1.01E+09 2.79E+09 1.80E+09 0.00E+00 1.49E+09 2.21E+08 9.80E+07 CS.137 3.23E+10 3.09E+10 4.56E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08 BA.140 1.18E+08 1.03E+05 6.86E+06 0.00E+00 3.35E+04 6.14E+04 5.96E+07 CE.141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.79E+03 0.00E+00 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 PR.143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 g ,,f ND.147 4.45E+02 3.61E+02 2.79E+01 0.00E+00 1.98E+02 0.00E+00 5.71E+05 Rev. 0 II 2-27 3/89

Q

_- TABLE 2.3 PATHVAY DOSE FACTORS AGE GROUP INFANT PATHWAY: GRASS.COV-MILK l ORGAN DOSE FACTORS XUCLIDE 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 MN-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 1.11Ev07 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 C0 60 0.00E+00 8.83E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 NI.63 3.50E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.08E+08 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 y ~5 ..............................................................................

(' " ' '/ 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 1.56E+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

'~

Tkikik5Ihhbhbb'~i$5bk$b8 $5bk$bi [$55b$bbi$b5khb9 b$bbk$bbi$hbEbb' 5

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 1.2JE+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08

/ PR.143 1.49E+03 5.56E+02 s7E+01 0.00E+00 2.07E+02 0.00E+00 7.84E+05 (T) ND-147 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 Rev. O II 2-28 3/89

TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHVAY: GRASS. COW. MEAT l ORGAN DOSE FACTORS NUCLIDE l.....................................................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 P-32 4.63E+09 2.88E+08 1.79E+08 0.00E+00 0.00E+00 0.00E+00 5.21E+08 CR 51 0.00E+00 0.00E+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN.54 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 FE.55 2.93E+08 2.03E+08 4.73E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 FE.59 2.66E+08 6.25E+08 2.39E+08 0.00E+00 0.00E+00 1.75E+08 2.08E+09 CO-58 0.00E+00 1.82E+07 4.09E'+07 0.00E+00 0.00E+00 0.00E+00 3.70E+GS CO-60 0.00E+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41E+09 NI.63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 ZN.65 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 0.00E+00 7.13E+08 RB.86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.59E+07 SR-89 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 SR.90 1.24E+10 0.00E+00 3.05E+09 0.00E+00 0.00E+00 0.00E+00 3.60E+08 Y-91 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.24E+08 ZR.95 1.87E+06 6.01E+05 4.07E+05 0.00E+00 9.43E+05 0.00E+00 1.90E+09 NB 95 2.30E+06 1.28E+06 6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 RU 103 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00 1.23E+10 RU.106 2.80E+09 0.00E+00 3.54E+08 0.00E+00 5.41E+09 0.00E+00 1.81E+11 AG.110M 6.68E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE.125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE.127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE.129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.00E+00 5.71E+09 I.131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 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' O.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 Rev. O Il 2-29 3/89

i (d) TABLE 2.3 PATHVAY DOSE FACTORS !

AGE GROUP: TEEN PATHWAY: GRASS. COW. MEAT l ORGAN DOSE FACTORS UUCLIDE l.....................................................................

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H.3 0.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 P-32 3.91E+09 2.42E+08 1.52E+08 0.00E+00 0.00E+00 0.00E+00 3.29E+08 CR.51 0.00E+00 0.00E+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 MN-54 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 0.00E+00 1.44E+07 FE-55 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.075+08 7.31E+07 l

.............................................................................. l l FE.59 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E+00 1.56E+08 1.17E+09 CO.58 l 0.00E+00 1.40E+07 3.24E+07 0.00E+00 0.00E+00 0.00E+00 1.94E+08 i CO.60 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 NI.63 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E+00 0.00E+00 1.71E+08 l ZN-65 2.50E+08 8.68E+08 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 l RB-86 0.00E+00 4.06E+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00 6.00E+07 j

-s .............................................................................. l 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 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 I

Y-91 9.54E+05 0.00E+00 2.56E+04 0.00E+00 0.00E+00 0.00E+00 3.91E+08 ZR-95 1.50E+06 4.73E+05 3.25E+05 0.00E+00 6.95E+05 0.00E+00 1.09E+09 NB.95 1.79E+06 9.95E+05 5.48E+05 0.00E+00 9.64E+05 0.00E+00 4.25E+09 RU.103 8.56E+07 0.00E+00 3.66E+07 0.00E+00 3.02E+08 0.00E+00 7.15E+09 RU.106 2.36E+09 0.00E+00 2.97E+08 0.00E+00 4.54E+09 0.00E+00 1.13E+11 i AC.110M 5.06E+06 4.78E+06 2.91E+06 0.00E+00 9.13E+06 0.00E+00 1.34E+09 l TE.125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 0.00E+00 0.00E+00 8.94E+08 TE.127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81E+09 0.00E+00 2.35E+09 TE.129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.00E+00 3.56E+09 l

1 131 8.93E+06 1.25E+07 6.72E+06 3.65E+09 2.15E+07 0.00E+00 2.47E+06 I-133 3.08E.01 5.22E-01 1.59E.01 7.29E+01 9.16E-01 0.00E+00 3.95E.01 CS.134 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS.136 9.43E+06 3.71E+07 2.49E+07 0.00E+00 2.02E+07 3.18E+06 2.99E+06 CS.137 7.24E+08 9.63E+08 3.35E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07 BA 140 2.39E+07 2.93E+04 1.54E+06 0.00E+00 9.94E+03 1.97E+04 3.69E+07 CE.141 1.18E+04 7.87E+03 9.05E+02 0,00E+00 3.71E+03 0.00E+00 2.25E+07 CE.144 1.23E+06 5.08E+05 6.60E+04 0.00E+00 3.03E+05 0.00E+00 3.09E+08 g-~g PR 143 1.76E+04 7.03E+03 8.76E+02 0.00E+00 4.08E+03 0.00E+00 5.79E+07 (s-s'j ND.147 6.23E+03 6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 Rev. O II 2-30 3/89

C

\

TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT

.............................................................................. j j ORCAN DOSE FACTORS I XUCLIDE l ----....------ ------- -- -- --------------.--- - -....---.-----....

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 l

P.32 7.38E+09 3.45E+08 2.85E+08 0.00E+00 0.00E+00 0.00E+00 2.04E+08 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 CO 58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 CO.60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 Nk 6h h hkk kb k$hhh bh h hkh bh b$bbkhbb b bbh bb b$bbh bb k bhh bh 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 s ..............................................................................

SR-89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 ;

SR-90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+08 Y-91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR 95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+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 5.96E+07 0.00E+00 3.90E+08 0.00E+00 4.01E+09 I RU.106 4.44E+09 0.00E+00 5.54E+08 0.00E+00 6.00E+09 0.00E400 6.91E+10 AC.110M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+08 TE-125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5.49E+08 TE 127M 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 0.00E+00 1.44E+09 TE-129M 1.79E+09 5.00E+08 2.78E+08- 5.77E+08 5.26E+09 0.00E+00 2.18E+09 I-131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.00E+00 1.48E+06

)

I.133 5.72E-01 7.08E.01 2.68E 01 1.31E+02 1.18E+00 0.00E+00 2.85E 01 l CS-134 9.23E+08 1.51E+09 3.19E+08 0.00E+00 4.69E+08 1.68E+08 8.16E+06 CS-136 1.63E+07 4.48E+07 2.90E+07 0.00E+00 2.39E+07 3.56E+06 1.57E+06 CS.137 1.33E+09 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.00E+06 BA.140 4.42E+07 3.87E+04 2.58E+06 0.00E+00 1.26E+04 2.31E+04 2.24E+07 CE.141 2.22E+04 1.11E+04 1.65E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE 144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1.89E+08

-s PR-143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00E+00 3.60E+07

\-- . ... . .. . ..[ .2 ..$ ..I ..[ .

Rev. 0 11 2-31 3/89

l l

l p

i

\. - TABLE 2.3 PATHWAY DOSE FACTORS ACE GROUP: INFANT PATHWAY: GRASS COW. MEAT l ORGAN DOSE FACTORS UUCLIDE l.-- ----- - ---------- - ----- -------.----..------------- --..---.. l l BONE LIVER T. BODY THYROID KIDNEY LUNG CI-LLI H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 NI.63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN.65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB.86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

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

( j 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 0.002+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 0.00E+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. 00 E+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 1 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 I.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 0.00E+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 (s_-\/ ND.147 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 Rev. 0 11 2-32 3/89

i l

TABLE 2. 3 PATHWAY DOSE FACTORS l

AGE GROUP: ADULT PATHWAY: GRASS. GOAT-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 MN-54 0.00E+00 1.01E+06 1.93E+05 0.00E+00 3.01E+05 0.00E+00 3.10E+06 FE 55 3.27E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 CO.58 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 CO-60 0.00E+00 1.97E+06 4.35E+06 0.00E+00 0.00E+00 0.00E+00 3.70E+07 NI-63 8.08E+0C 5.60E+07 2.71E+07 0.00E+00 0.00E+00 0.00E+00 1.17E+07 ZN-65 RB.86 1.65E+08 5.24E+08 2.37E+08 0.00E+00 3.51E+08 0.00E+00 3.30E+08 0.00E+00 3.12E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 6.14E+07 SR 89 SR-90 3.05E+09 0.00E+00 8.76E+07 0.00E+00 0.00E+00 0 00E+00 4.89E+08 Y.91 9.84E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0.00E+00 5.68E+05 ZR-95 NB.95 1.13E+02 3.63E+01 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 RU.103 9.92E+03 5.52E+03 2.97E+03 0.00E+00 5.45E+03 0.00E+00 3.35E+07 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 AG.110M 6.99E+06 6.47E+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE.125M 1.96E+06 7.09E+05 2.62E+05 5.89E+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 Rev. O II 2-33 3/89

f TABLI 2.3 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK l ORGAN DOSE FACTORS NUCLIDE l----.--------- -- - ----- ---- -------- --- - -- ---------- --- i l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI !

H3 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 P 32 3.78E+10 2.34E+09 1.46E+09 0.00E+00 0.00E+00 0.00E+00 3.18E+09 i

bk$bk b$bbk bb b$bbkhbb h$hhh bb b bbb bb [ b5khbh b$bbk bb k b[b bh MN-54 0.00E+00 1.68E+06 3.34E+05 0.00E+00 5.02E+05 0.00E+00 3.45E+06 FE 55 5.79E+05 4.11E+05 9.58E+04 0.00E+00 0.00E+00 2.61E+05 1.78E+05 FE-59 6.74E+05 1.57E+06 6.08E+05 0.00E+00 0.00E+00 4.96E+05 3.72E+06 l CO 58 0.00E+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 CO 60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 4.35E+07 NI-63 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.60E+07 ZN.65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 '.72E+08 RB.86 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0.00E+00 8.40E+07 SR.89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 SR.90 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 Y.91 1.90E+03 0.00E+00 5.09E+01 0.00E+00 0.00E+00 0.00E+00 7.78E+05

~~~~ ~~ '~ ~~ ~~ ~~

kR95$

i$95k$65 6$55bhb5 '5$3bb+bi b$bbkhbb 9555k$b[ b$bbbhbb 5$$5k$b5~

NB 95 1.69E+04 9.38E+03 5.16E+03 0.00E+00 9.09E+03 0.00E+00 4.01E+07 RU-103 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02 0.00E+00 1.82E+04

..........................................................c....................

RU.106 4.50E+03 0.00E+00 5.68E+02 0.00E+00 8.69E+03 0.00E+00 2.16E+05 AG.110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3.07E+09 TE 125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 0.00E+00 1.06E+07 TE 127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2,52E+07 TE-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 I.131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 1.79E+08 I-133 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07 CS.134 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 CS-136 1.35E+09 5.30E+09 3.56E+09 0.00E+00 2.89E+09 4.55E+08 4.27E+08 l

CS 137 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.07E+09 7.60E+08 l BA.140 5.84E+06 7.16E+03 3.76E+05 0.00E+00 2.43E+03 4.81E+03 9.01E+06 l CE.141 1.07E+03 7.12E+02 8.18E+01 0.00E+00 3.35E+02 0.00E+00 2.04E+06 CE.144 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 PR 143 3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 ND 147 2.18E+01 2.37E+01 1.42E+00 0.00E+00 1.39E+01 0.00E+00 8.54E+04 O. ..............................................................................

l Rev. O

\

II 2-34 3/89

I gel TABLE 2.3 l PATHWAY DOSE FACTORS ACE GROUP: CHILD PATHWAY: GRASS. GOAT-MILK l ORGAN DOSE FACTORS UUCLIDE 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 2.58E+09

.............................................................................. 1 CR.51 0.00E+00 0.00E+0J 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 l l

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+08 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 I RB-86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00 6.77E+07 fs ..............................................................................

t

'j 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 1.72E+05 AG.110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE.125M 8.86E+06 2 40E+06 1.18E+06 2.49E+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 I-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 " 7' *10 6.01E+08 CS.136 3.04E+09 8.36E+09 5.41E+09 0.00E+00 4.45E+09 6. 4E 8 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 8.61E+01 2.59E+01 4.27E+00 0.00E+00 1.40E+01 0.00E+00 9.29E+04

("')

t

\- j PR.143 ND.147 5.34E+01 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 Rev. O II 2-35 3/89

,-~

(

Ng TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS GOAT-MILK l ORGAN DOSE FACTORS UUCLIDE l------ -- ---- -------- -- - ------- - --- -------------------------

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 )

l P-32 1.92E+11 1.13E+10 7.44E+09 0.00E+00 0.00E+00 0.00E+00 2.60E+09 I CR-51 0.00E+00 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 MN 54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+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 NI-63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN-65 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+00 1.93E+09 RB-86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07

,r ..............................................................................

("-') SR-89 2.65E+10 0.00E+00 7.59E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+08 SR.90 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 Y.91 8.80E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.31E+05 ZR-95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 NB-95 7.13E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU-103 1.04E+03 0.00E+00 3.48E+02 0.00E+00 2.17E+03 0.00E+00 1.27E+04 RU.106 2.28E+04 0.00E+00 2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG.110M 4.63E+07 3.38E+07 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1.75E+09 TE 125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06 TE-127M 5.06E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE 129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 I.131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+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 l

.............................................................................. 1 CS.137 1.54E+11 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 l 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

.............................................................................. l CE.144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07

,f-~g 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 l N- / ..............................................................................

l Rev. 0 II 2-36 3/89 1

I

TABLE 2.3 PATHWAY DOSE FACTORS l

AGE GROUP: ADULT PATHWAY: VEGETATION i l CRGAN DOSE FACTORS UUCLIDE l---------------- ----. ----- ------ ---------------- --- -----------

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

.............................................................................. 1 H.3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 P-32 1.40E+09 8.69E+07 5.40E+07 0.00E+00 0.00E+00' O.00E+00 1.57E+08 CR-51 0.00E+00 0.00E+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN.54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 9.58E+08 FE-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 FE.59 1.26E+08 2.97E+08 1.14E+08 0.00E+00 0.00E+00 8.29E+07 9.89E+08 CO-58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 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

. IN-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 1.02E+08 0.00E+00 0.00E+00 0.00E+00 4.32E+07 0 ..............................................................................

SR 89 SR.90 Y.91 9.98E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00 0.00E+00 1.75E+10 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 1.82E+07 0.00E+00 5.57E+08 RU.106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 AG.110M 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 TE.125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 TE.127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.00E+00 1.17E+09 TE-129M 2.51E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.00E+00 1.26E+09 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+08 0.00E+00 3.05E+07 I.133 2.09E+06 3.63E+06 1.11E+06 5.34E+08 6.33E+06 0.00E+00 3.26E+06 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+08 BA.140 1.29E+08 1.62E+05 8.47E+06 0.00E+00 5.52E+04 9.29E+04 2.66E+08 CE.141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 0.00E+00 5.10E+08

.............................................................................. j CE-144 3.29E+07 1.38E+07 1.77E+06 0.00E+00 8.16E+06 0.00E+00 1.11E+10 i PR-143 6.25E+04 2.51E+04 3.10E+03 0.00E+00 1.45E+04 0.00E+00 2.74E+08 i O. ND 147 3.34E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08

)

Rev. O !

1 Il 2-37 3/89 l l

i l

1 fT; (s / TABLE 2. 3 i

PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: VEGETATION l ORGAN DOSE FACTORS NUCLIDE l--.-- -.- ---- -----------.---- -----------...----..--- -.- ---- --.. I l BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 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 1.34E+08 CR.51 0.00E+00 0.00E+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 KN-54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 FE.55 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.91E+08 CO 58 0.00E+00 4.36E+07 1.01F+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 CO-60 0.00E+00 .2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 NI-63 1.61E+10 1.13E+09 5.45E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+08 ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 RB 86 0.00E+00 2.73E+08 1.28E+08 0.00E+00 0.00E+00 0.00E+00 4.04E+07

( SR-89 1.52E+10 0.00E+00 4.34E+08 0.00E+00 0.00E&O0 0.00E+00 1.80E+09

' -~) SR-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 Y-91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 ZR-95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NB.95 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 RU.103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 RU-106 3.09E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 AG.110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 TE.127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE.129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 l I-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I I.133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS.134 7.10E+09 1.67E+10 7.75E+09 0.00E+00 5.31E+09 2.03E+09 2.08E+08 CS 136 4.39E+07 1.73E+08 1.16E+08 0.00E+00 9.41E+07 1.48E+07 1.39E+07

.............................................................................. 1 CS.137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 I BA-140 1.39E+08 1.71E+05 8.97E+06 0.00E+00 5.78E+04 1.15E+05 2.15E+08 )

CE.141 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 CE.144 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 p-s PR.143 6.99E+04 2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08

+ ND.147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08

\~-)i ............ ~ ................................................................

Rev. O II 2-38 3/89

I TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: VEGETATION l ORGAN DOSE FACTORS UUCLIDE l...- -.-----...---.- -.---- .-- ...--.--.----.------....----..--.....

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI l H3 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 bk$h[ b bbb+bb b$bbb bb k$5hbhbh b bhbhb [$hhkhbb k [hb bh h hbb bh MN 54 0.00E+00 6.65E+08 1.77E+08 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 FE-59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 0.00E+00 1.87E+08 6.71E+08 CO-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 !

CO.60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09

~ ~~ ~ ~~ ~

Nk$db 5$hhk+5h b$55khbh i$bdk+bh b$bbk$bb b$bbkhbb b$bbk$bb 5$5Ek+bh" ZN.65 8.12E+08 2.16E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 RB.86 0.00E+00 4.51E+08 2.77E+08 0.00E+00 0.00E+00 0.00E+00 2.90E+07 f',, SR.89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 SR.90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y.91 1.87E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.49E+09 IR-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+08 NB.95 4.11E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E+08 RU.103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU.106 /.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 AG 110M 3.21E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07 0.00E+00 2.58E+09 TE.125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08 Tk kbhk k$bbkhbb b$bbkhbb k$bhk bb b$k6k bb b$hhk b9 b[bbk bb k bhk b9 TE-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 0.00E+00 1.02E+09 I.131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 I-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.00E+00 1.76E+06 CS.134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 i CS.136 8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21E+08 1.81E407 8.00E+06 1

CS-137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 l 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

_ .............................................................................. 1 Rev. O II 2-39 3/89

l I

l l

l

['N sJ TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHVAY: VEGETATION l ORGAN DOSE FACTORS !

NUCLIDE l---- -.- -------- --- ------------ ------------------....-. --- -..-

l l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI l l

H3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l l

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

.............................................................................. 1 CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 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 NI.63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN.65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB.86 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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+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 0.00E+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 I.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 0.00E+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. O II 2-40 3/89

i l

g m- l TABLE 2. 3 PATHVAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: INHA1ATION l ORGAN DOSE FACTORS UUCLIDE 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-55 2.46E+04 1.70E+04 3.94E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 CO.58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 Co-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 i

................................................................................ l NI.63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 1.34E+04 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 7-m ...............................................................................

! ! 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+0L 1.77E+06 1.50E+05 i NB-95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 RU-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 AG.110M 1.08E+04 1.00E+04 5.94E+03 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 I.133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS-136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA.140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE.141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05

/~ x PR-143 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 l } ND 147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05

\~ ...............................................................................

Rev. O II 2-41 3/89

l b

(s / TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: INHALATION l ORGAN DOSE FACTORS I UUCLIDE l-.-- ----- -- -- - ---------------- ---------- -- ------- ------.....

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI H3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 P.32 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.28E+04 bRhk b bbk bb b bbh bb [ hhh bh h bbh bk b bhh bk h$kbh b4 b$bbhbb MN-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE 55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 CO.58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 CO.60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 NI.63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 RB-86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 l

SR.89 4.34E+0S 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 i t'-'j SR.90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y-91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 ZR.95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 NB.95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU.103 2.10E+03 0.00E+00 8.96E+02 0.00E+00 '/ .43E+03 7.83E+05 1.09E+05 i

kb.kb6 9 bbh bb b bbb bb 2bh bb b bbk bb k 9hk bh k 6kk bh 9 6bb b AG.110M 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 TE-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE.127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS.137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA 140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE 144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 cs f s 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. O II 2-42 3/89

TABLE 2.3 PATHWAY DOGE FACTORS AGE GROUP: CHILD PATHWAY: INHAIATION l ORGAN DOSE FACTORS UUCLIDE l.................................................................-...

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P.32 2.60E+06 1.14E+05 9.88E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 KN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 l FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03

FE.59 2.07E+04 3.34E+04 1.67E+04 0 00E+00 0.00E+00 1.27E+06 7.07E+04 l

CO.58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO.60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00Es00 7.07E+06 9.62E+04 NI.63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN.65 4.26E+04 1.13E+05 7.03E+04 0.00EF00 7.14E+04 9.95E+05 1.63E+04 RB.86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR 90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y.91 9 14E+05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR 95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 NB.95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU.106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1,84E+05 1.43E+07 4.29E+05 AC.110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 TE.125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 TE-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I.131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 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 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA 140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE.141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE.144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 PR 143 1.85E+04 5.55E+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 Rev. 0 II 2-43 3/89

}

l l

1 TABLE 2.3 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHVAY: INHALATION

............................................................................... i 1

l ORGAN DOSE FACTORS UUCLIDE l. ...... ................................................. ......... ,

l BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI i

............................................................................... q H.3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.4)E+02 6.47E+02 6.47E+02

{

P.32 2.03E+06 1.12E+05 7.74E+04 0.00E+00 0.00E+00 0.00E+00 1.61E+04 I CR 51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN.54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE.55 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 j

............................................................................... I FE.59 1.36E+04 2.35E+04 9.48E+03 0.00E400 0.00E+00 1.02E+06 2.48E+04 CO.58 0.00E&OO 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CO.60 0.00E600 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 Nk$hh b b9k bh h$bbk hk k [6k b b bbk bb b$bbk bb h b9k bh h dhk b3 J ZN.65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 l R3 86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03 I

[' SR.89 SR.90 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Y.91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 ZR.95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 NB.95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 RU.103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU.106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 AG.110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE.125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 TE.127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 TE.129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 I.131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E&OO 1.06E+03 I.133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS.134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS.136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS.137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA.140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE.141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 CE.144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 PR.143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 ND.147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3. 22E405 3.12E+04 O ...............................................................................

Rev. O II 2-44 3/89

TABLE 2.4 ATMOSPHERIC DISPERSION AND DEPLETION PARAMETERS

~ FOR RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3 CALCULATIONS i

** I Sector Miles X/Q D/Q l N 4.5 2.4E-07 1.0E-09 NNE 2.4 4.7E-07 2.3E-09 NE 2.4 3.2E-07 1.1E-09 ENE 2.6 2.2E-07 5.7E-10 E 3.5 1.5E-07 2.7E-10 ESE 2.3 3.7E-07 9.5E-10 SE 3.6 2.4E-07 7.0E-10 i

[b SSE 2.0 5.8E-07 3.2E-09 )

S 4.8 1.0E-07 3.6E-10 SSW 4.3 9.2E-08 2.9E-10 SW 3.5 1.2E-07 3.3E-10 WSW 1.5 6.9E-07 2.2E-09 W 1.7 6.5E-07 2.2E-09 f WNW 3.0 3.7E-07 1.0E-09 NW 5.0 2.2E-07 6.3E-10

)

NNW 3.4 4.9E-07 1.9E-09 i

sec/m3

,, ,2 A

> 1 V

I Rev. 0 II 2-45 3/89

________________-________O

i TABLE 2.5 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS (For Dose Calculations required by Radiological Ef fluent Control 3/4.11.2.3)

DISTANCE ,,

SECTOR (MILES) PATHWAY AGE GROUP N 4.5 Vegetation Child NNE 2.4 Vegetation Child f

NE 2.4 Vegetation Child ENE 2.6 Vegetation Child E 3.5 Vegetation Child ESE 2.3 Vegetation Child SE 3.6 Vegetation Child SSE 2.0 Vegetation Child O

V S 4.8 Cow / Milk Infant SSW 4.3 Vegetation Child SW 3.5 Vegetation Child WSW 1.5 Vegetation Child W l.7 Vegetation Child WNW 3.0 Vegetation Child gw* _ _ _

NNW 3.4 Vegetation Child

No pathway currently exists in this sector out to 5.0 miles.

- In addition to the pathway shown, the plume, inhalation, and ground plane pathways are present at each receptor location.

O Rev. O 11 2-46 3/89

2.3 METEOROLOGICAL MODEL

\ 2.3.1 Discersion Calculations Atmospheric dispersion for gaseous releases are calculated using a straight line flow Gaussian model similar to the Constant Mean Wind Direction model given in Regulatory Guide 1.111, Section C.1.c. The method given here is modified by including factors to account for plume depletion and effects of the open terrain.

The average relative concentration is given by the following l equation: l X

- - 2.0326 K I . 2-20 Q

j , k ( " # "3 E j l') j Where:

X/Q =

average concentration normalized by source strength (sec/m3),

V 2.032 -

(2/w )1/2 . (2 x /16)-1 6 - plume depletion factor at distance r for the l

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.

K -

terrain correction factor (Figure 2.5) njk -

the number of hours meteorological conditions are observed to be in a given wind direction, wind speed class, k, and atmospheric stability class, d.

N -

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

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

Rev. O II 2-47 3/89

r -

downwind distance from the release point to the , '

l p a. location of interest (meters).

Iijk = the average windspeed (midpoint of windspeed class, 'k) measured at the 10 meter level during stability class J. (meters /sec)

Ij(r) , - the vertical plume spread with a volumetric i

, correction for a release within the building wake cavity, at a distance, r, for stability class, j, l

expressed in meters.

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

l The equation for calculating Ej(r) is:

e '

(o 2 + 0.5 b 7,))

2 (Eq. 2-30]

3 E3 (r) = the lesser of <

O0 3 (Eq. 2-31]

s Where:

a 3

.= the vertical standard deviation of materials in the plume at distance, r, for atmospheric '

stability class, j, expressed in meters.

(Figure 2.3) ,

0.5 - the building shape factor.

b - the vertical height of the reactor containment structure (79.4 meters) t f

O Rev. O {

lI 2-48 .3/89-

l 2.3.2 Deoositipp Calculations o

The relative deposition per unit area is calculated as follows: 1 D, j g (Eq. 2-32]

Q 0.3927 r i

Where: !

D/Q = deposition per unit area normalized by source .

I strength (m-2)

Dg = relative deposition rate for a ground level release (m-1) (Figure 2.4) z =

the fraction of time the wind blows to the sector of interest. '

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

0.3927 =

the width in radians of a 22.50 sector. 1

{

Other variables are as previously defined. '

1 NOTE: All parameters are considered dimensionless unless other wise indicated.

1 O

Rev. O II 2-49 3/89-

l l

2.4 DEFINITIONS OF GASE0US EFFLUENTS PARAMETERS l Section of J_qrg Definition Initial Use AF = Allocation Factor of 0.5 applied to account 2.1.2 j for releases from both stacks simultaneously. )

This factor will limit the dose rate l contribution from each stack to 1/2 the limit for the site.

B = vertical height of the reactor containment 2.3.1 ]

structure. !

1 CG = the alarm setpoint for each plant vent stack ?.1.2 '

1 noble gas activity monitor (uCi/cm3)

CGrhax - maximum of the monitor setpoints for the two 2.1.4 '

stacks Cf - the alarm setpoint for each plant vent stack 2.1.3 !

effluent release rate monitor (uCi/sec) m caux - the Auxiliary Building Ventilation Exhaust 2.1.4 1 monitor alarm setpoint. (uCi/cm3) l ccont - the Containment Atmosphere Gaseous monitor 2.1.5 alarm setpoint. (uCi/cm3) ]

CI - the setpoint for each plant vent stack Iodine 2.1.7 '

Monitor. (uCi/cm3)

Cp - the setpoint for each plant vent stack 2.1.8 l particulate Monitor. (uCi/cm3)

Og - relative deposition rate for a ground-level 2.3.2 release (m-1)

Do - the total organ dose rate due to tritium, 2.1.6 iodines, and particulate in gaseous releases. (mrem /yr)

Dp - dose to any organ of an individual from 2.2.2 radioiodines, tritium and radionuclides in particulate from with half-lifes greater than eight days. (mrem) 1 Rev. 0 II 2-50 3/89

_________-_-A

Section of Term Definition O Ds - skin dose rate at the SITE BOUNDARY due to Jnitial Use-2.1.1 i

. noble gases. (mrem /yr)

Dt - total body dose rate at the SITE BOUNDARY 2.1.1 due to noble gases. (mrem /yr)

D8 = air dose due to beta emissions from noble 2.2.1 gases. (mrad) I Dy - air dose due to gamma emissions from noble 2.2.1 !

(mrad) !

D/Q - the annual average relative deposition at 2.2.2 I the location of tr.terest. (m-2) 6 - plume depletion factor at distance r for 2.3.1 l the appropriate stability class (radiciodines and particulate).

FB - the estimated flow rate contribution 2.1.1 associated with the release rate of the l batch. source. (cm3/sec)

FC - the continuous flow rate contribution of 2.1.1 each plant vent stack. (cm3/sec)

Fy - the flow rate at each plant vent stack. 2.1.1 (cm3/ sec).

FABV - the flow rate contribution associated with 2.1.4 the sources in the a'uxiliary building other than the waste gas decay tanks. (cm3/sec)

Faux - the total flow rate at the auxiliary 2.1.4 building ventilation monitor during the release of a Waste Gas Decay Tanks.

(cm3/ sec)

Fcont - the flow rate contribution associated with 2.1.5 the release of the Containment Atmosphere.

(cm3/sec)

FGDT = the flow rate contribution associated with 2.1.4 the release of a waste gas decay tank.

(cm3/ sec)

O ,

Rev. 0 II 2-51 3/89

Section of Igm Definition Initial Use OK Ki

- terrain recirculation factor. (Unitiess)

= total body dose factor due to gamma 2.3.1 2.1.1 I

. emissions from noble gas radionuclides i.

(mrem /yr per uCi/m3)

Li - skin dose factor due to beta emissions 2.1.1 from noble gas radionuclides i. ,

(mrem /yr per uCi/m3) i Mj - air dose factor due to gamma emissions 2.1.1 from noble gas radionuclides i.

(mrem /yr per uCi/m3)

Ni - air dose factor due to beta emissions 2.2.1 ;

from noble gas radionuclides 1.

(mrem /yr per uCi/m3) .

njk - number of hours meteorological conditions 2.3.1 are observed to be in a given wind direction, wind speed class k, and 3 atmospheric stability class J.

(V N - total hours of valid meteorological data. 2.3.1

{

Pi - dose parameter for radionuclides i, (other 2.1.6

{

than noble gases) for the inhalation j pathway, in mrem /yr per uCi/cm3 l Qj - total release rate of radionuclides i from 2.1.1 the Plant Vent Stacks. (uCi/sec)

Q'i - cumulative release of radionuclides i 2.2.1 during the period of interest. (uCi)

R - dose factor for radionuclides i, pathway 2.2.2 p, and age group a, and organ o. l (mrem /yr per uCi/m3 ) or (m2-mrem /yr per uCi/sec)

O Rev. 0 II 2-52 3/89

Section of Term Definition Initial Use r - distance.from the point of release to 2.3.1 the location of interest for dispersion calculations. (meters).

SF = Safety Factor of 0.5 applied to compensate 2.1.2 for statistical fluctuations, errors of

)

measurement, and non uniform distribution of release activity between the stacks. 1 Ij(r) - vertical plume spread with a volumetric 2.3.1 l correction for a release within the I building wake cavity, at a distance, r, for stability class, j, expressed in meters.

oj - vertical standard deviation of the plume 2.3.1 t concentration (in meters), at distance, r, for stability category J.

ujk - wind speed (midpoint of windspeed class k) 2.3.1 at ground level (m/sec) during atmosphere i stability class J.

W' - the dispersion parameter for estimating 2.2.2 l the dose to an 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 2.2.2 the location of interest. (sec/m3)

X/Q = the highest annual average relative 2.1.1 concentration at the SITE BOUNDARY.

(sec/m3)

(3.3 x 10-6 sec/m3 in the NNW sector)

XiB = the concentration of radionuclides i in the 2.1.1 )

batch release stream, (uCi/cm3) as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2.

Rev. O j 11 2-53 3/89

Section of !

Term Definition Initial Use Xc i - the concentration of radionuclides i in the 2.1.1 continuous release stream (uCi/cm3) at each stack as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, i Table 4.11-2 l

':i y

- the concentration of radionuclides i present 2.1.1 at each plant vent stack. (uCi/cm3)

XGV - the concentration of noble gases present at 2.1.2 each plant vent stack due to the combined sources as calculated from the radionuclides 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. (uCi/cm3)

Xy I - the concentration of radionuclides present 2.1.7 at each plant vent stack due to the combined sources 3. calculated from the radionuclides concentration determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1, -

Table 4.11-2. (uci/cm3)

XiABV - the concentration of noble gas radionuclides 2.1.4 ;

i in the auxiliary building ventilation stream due to sources other than the waste gas decay tanks. (uC1/cm3)

Xi aux - the concentration of noble gas radionuclides 2.1.4 i at the auxiliary building ventilation monitor during a waste gas decay tank release.

(uci/cm3)

O Rev. O II 2-54 3/89

Section of Term Definition Initial Use Xi cont - the concentration of noble gas radionuclides 2.1.5

.i in the containment relese stream as sampled in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. (uCi/cm3)

XiGDT - the concentration of noble gas radionuclides 2.1.4 i in the waste gas decay tank as sampled in accordance with Radiological Effluent l Control 3/4.11.2.1, Table 4.11-2. (uCi/cm3)

Xpy - the concentration of particulate present 2.1.8 I at each plant vent stack due to the combined sources as calculated from the radionuclides concentration determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. (uCi/cm3) l z - the fraction of time the wind blows to the 2.3.2 sector of interest 1.1 - conversion factor of mrem skin dose per 2.1.1 mrad air dose.

500 - the dose rate limit to the total body of 2.1.2 an individual in an unrestricted area due to noble gases. (mrem /yr) 3000 - the dose rate limit to the skin of the 2.1.2 body of an individual in an unrestricted area due to iodines, tritium, and particulate. (mrem /yr) 1500 - the dose rate limit to any organ due to 2.1.7 iodines, tritium, and particulate.

(mrem /yr)

Rev. O II 2-55 3/89

et ABU it ilk.

i I

gaa II

3 E 1: 1! *I 8

( -l I

. 4 .:

==

li4= 1 1 ig k$ 1i t i 5

it .

1 65 til

??- P -

! k*g*

i 60 il 3

000 '

T m

" gs .

1 - 5 "3 *l i

<j 3- -

u i i 5 l

w h

- i l1 4 4 3 >

= 2 ,

1 3 s E -

m -

i = n , s

% o c , 1 i

e g g

{- - - 1. ,,4 a f s

y

{~

El

s +'

2 Se a I $

4--- '"~ < - 7 4 - \

, i I! g .,

i i

$ V l d

1 1

at- ~

a I 3 E

,- i A

g

                        =                                        1

i9 = 1 g I 's kA ,e -- .

                                                                                                 ~                 .

e =

            <           t                                        I I                               1 O          B           ;

c { h S 1 II \

It 8 - e l a 4 S k> s m . g _5 -3 a 1 1

                                                  - Tv                  i 5

a

=

la i

i OOO g p ; - I {i

a

i. 1. 1 ' . ,, 3 e

ist 66 a "

t i u n s i ,i

           .:                     Ie                                                         n l      .I h                  I : :t a 3                    s                         .
                                                                    ~                               -

a 1 i i J'- t -- ..- s -- g + *}*5 e

                         ;t
                                                                    ~~

I I

*1 b i

                                                  -                                                -                       st              i f   i          gj      ,   < >j.
                                                 .                                                                          .g           -

t

                                                             -                                                             1, r .        ;

I. O Ik, I 3 $I3 Rev 0 11 2-56

0 0 0 2 O 0 N

                                \               0 0

1 ) s e s s A N C l a y N i l i b t a N S i t c r e h

p s S o R i n E t T A E l l A M A 0O 0 L ( s 1 I e s

                  \                               K

( E l a e e 2 s O R, 2 N N l e e r A e v u T L g S I

                                                        - i d     F D    n L    u O          N E

V A R G f o o r r T t E c e . M f f _ U E . L n 0 P i o t e 1 l p e N D

       '                                              e m        _

l u _ P - l 1 0 0 9 8 7 6 5 4 3 2 1 1 0 0 0 0 0 0 0 0 0

IzU Zi E zob mu.

O

                                          . o 70

f J 1000 , ,, ,

I 'I y

                                                        /                                      J                                        #                                         l
                                                                                                                                     /                                          j
                                                       /                                   /
                                                                                                                                                                                  \
                                                     /                               /                                            /

l /

                                                                                                                               /                        ,,
                                                                                                                                                                                 )

r r i ) / '

                                                                                                                                                     /                            \
                                                                                                                        /                     /

j f l / / A [ p , p [

                                  /
                                    /   _

a /

                                              /        /
                                                            /                                          s s

s s' s j r

                                /         /         /                                     j'                            f
                              /        f    n   /                          /                                  /                    /

g / / ? / '

                                                                                     /                                     /
     $                 / / /                    D//                                                        ,         f           f h           /// ! /k/                 [
                                                                            /                                        ,  /
      ,N
             !         [               p           p 0                            l            l, Gf G        10                                          ,
                /     /          /          /
             //              /         /
               /       /          /
             '/            /                                                                                                                                                    '
             /,        l
             /

1 1.0 10 100 0.1 PLUME TRAVEL DISTANCE (KILOMETERS) Vertical Standard Deviation of Material in a Plume (Letters denote Pasquill Stability Class) NOTE: THESE ARE STANDARD RELATIONSHIPS AND MAY HAVE TO BE MOOlFIED FOR CERTAIN TYPES OF TERRAIN AND/OR CLIMATIC I CONDITIONS (E.G., VALLEY, DESERT, OVER WATER). Figure 2.3 m Rev. O II 2-58 3/89 j l _ _ - _ -

j 104 , 1H N \ 4 N I 6

                                    %L z                                 N e                                   T  u
     $                                       hI                                                    '

w i N g j 104 % q ) x w l N Q $ ' U s NA E S j NL w Mg 104

1 l l 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) Relative Deposition for Ground Level Releases (All Atmospheric Stability Classes) Figure 2.4 Rev. 0 ( II 2-59 3/89 l

O 0 0 1

                                 >I
                    '                  9      r
                   ,                   1 t

o s c N a

                                          ) F S   n R   o 5 N                           E i t       _

l T c 2 e s it E M r r o er O C u m

            \                             L I

K ( n g i i a r F r O \ E C N A T e n e p . T O S I D 0 -_ I 1 1 0 0 4 0 1 1 1 0 8Vk z9 FOE 8 O W* a

78 wD*

SECTION 3.0 RADIOLOGICAL ENVIRONt- 'AL MONITORING 3.1 SAMPLING LOCATIONS Sampling locations as required in Radiological Effluent Control 3/4.12.1, Table 3.12-1 are described in Table 3.1 and shown on the map in Figure 3.1. NOTE: For the purpose of implementing Radiological Effluent Control 3/4.12.1 sampling locations will be modified as reauired to reflect the findings of the Land Use Census. Dose calculations used in making this determination will be performed as specified in Section 2.2.4. 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 monitored as special studies to e evaluate potential pathways of exposure without adding such locations to the monitoring program given in Table 3.1. 3.2 R4TERLABORATORY COMPARIS0N PROGRAM For the purpose of implementing Radiological Effluent Control 3/4.12.3, TV Electric has contracted Teledyne Isotopes Midwest Laboratory to perfortu the Interlaboratory Comparison Program. The program is operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to the participant laboratories. The purpose of the program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant I laboratories and specifies control limits. Results consistently higher l @ Rev. O II 3-1 3/89

or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. Teledyne O pr.rticipates in the environmental sample crosscheck program for milk j and water samples conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, ! Environmental Manitoring and Support Laboratory, Las Vegas, Nevada. The results of the program are included in the Annual Radiological-Environmental Operating Report. l l l l i O l i

l O Rev. O II 3-2 3/89

l t A (/) Table 3.1 Environmental Sampling Locations

                ~ Samp1'ing                        Location                          Sample Point              (Sector - Miles)                     Type                                                  i i

Al N-1.45 (Squaw Creek Park) A A2 N-9.4 (Granbury) A A3 E-3.5 (Children's Rome) A A4 SSE-4.5 (Glen Rose) A AS S/SSW-1.2 A A6 SW-12.3 (Control) A A7 SW/WSW-0.95 A A8 NW-1.0 A

    ,~                        R1                     N-1.45 (Squaw Creek Park)          R s_-

R2 N-4.4 R R3 N-6.5 R R4 N-9.4 (Granbury) R R5 NNE-1.1 R R6 NNE-5.65 R R7 NE-1.7 R R8 NE-4.8 R R9 ENE-2.5 R l R10 ENE-5.0 R R11 E-0.5 R I ( Rev. O II 3-3 3/89

(,rm) Table 3.1 (Continued)

\_,

Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Type R12 E-1.9 R R13 E-3.5 (Children's Home) R R14 E-4.2 R R15 ESE-1.4 R R16 ESE-4.7 R R17 SE-1.3 R R18 SE-3.85 R R19 SE-4.6 R R20 SSE-1.3 R /O Ns _/! R21 SSE-4.4 (Glen Rose) R R22 SSE-4.5 (Glen Rose) R R23 S-1.5 R R24 S-4.2 R R25 SSW-1.1 R R26 SSW-4.4 (State Park) R R27 SW-0.9 R ___ R28 SW-4.8 (Girl Scout Camp) R R29 SW-12.3 (Control) R R30 WSW-1.0 R R31 WSW-5.35 R w Rev. O II 3-4 3/89

                                                                                 .3 I

i 1 [ Table 3.1 L/ Environmt.ntal Sampling Locations

       - Sampling                 Location                         Sample Point              (Sector - Miles)                    Type R32                     WSW-7.0                            R R33                     W-1.0                               R R34                     W-2.0                              R R35                     W-5.5                               R R36                     WNW-1.0                            R l           R37                     WNW-5.0                            R R38                     WNW-6.7                            R R39                     NW-1.0                             R R40                     NW-5.7                             R O

k. R41 NW-9.9 (Tolar) R R42 NNW-1.35 R l

R43 NNW-4.6 R SW1 N-1.5 (Squaw Creek Reservoir Marina) SW l SW2 N-9.9 (Lake Granbury) SW/DW( } SW3 N-19.3 (Control-Brazos River) SW SW4 NE-7.4 (Lake Granbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW(3) > l SW6 NNW-0.1 (Squaw Creek Reservoir) SW/DW( (5) GW1 W-1.2 (NOSF potable water) GW l. (4 M f GW2 WSW-0.1 (Plant potable CW l _ water) ]

%)

Rev. O II 3-5 3/89 j i l l

V Table 3.1 (Continued) Environmental Sampling Locations

                                    ' Sampling                 Location                        Sample Point               (Sector - Miles)                    Type D)

GW3 SSE-4.6 (Glen Rose) GW ( 2 / , t 31 GW4 N-9.8 (Granbury) GW

\5)

GW5 N-1.45 (Squaw Creek Park) GW SSI NNE-1.0 (Squaw Creek Reservoir) SS SS2 N-9.9 (Lake Granbury) SS SS3 NE-7.4 (Lake Granbury) SS M1 SSE-2.2 M M2 not used(6) M n M3 not used(6) g k 0 M4 SW-13.5 (Control) M F1 ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F FP1 ENE-9.0 (Leonard Bros. Pecan Farm)FP FP2 E-4.2 (truck farm) FP 1 FP3 SW-13.5 (Control) FP l BL1 N-1.45 BL BL2 SW-1.0 BL BL3 SW-13.5 (Control) BL (1) Types: A - Air Sample, R - Direct Radiation, SW - Surface Water, GW - Ground Water, SS - Shoreline Sediment, M - Milk, f-] F -Fish; FP - Food Products; BL - Broad Leaf Vegetation. NY Rev. 0 II 3-6 3/89

  -(2)  The municipal water system for the City of Granbury is supplied by surface water from Lake Granbury (location SW2) and ground well water

\ (location GW4). Each of these input supplies for the Granbury municipal water system is sampled. These samples are not required for comp]iance with Radiological Effluent Control 3/4.12.1, Table 3.12-1, because they are not affected b" plant discharges. (3) This sample (location SW5) is representative of discharges from Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury. (4) The plant potable water is supplied by surface water from Squaw Creek Reservoir (location SW6) and ground well water (location GW2). Each of these input supplies for plant potable water is sampled. (5) Ground water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 and are therefore not required to be monitored for radioactivity to meet the requirements of the Radiological Environmental Monitoring Program specified in Radiological Effluent Control 3/4.12.1, . Table 3.12-1. ' Although not required for compliance with the Radiological Environmental Monitoring Program groundwater sampling locations are f included in the monitoring program to provide confirmation that ground water is not affected by plant discharges. (6) Due to the current availability of milk sampling locations, milk samples are taken at only two locations (i.e., one sample and one control). If additional milk sampling locations are identified in future land use census, this table will be revised to include up to a maximum of 3 samples and one control, as indicated in the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1, Table 3.12-1. i (7) Per the Radiological Environmental Monitoring Program given in Radiological Effluent Control 3/4.12.1, Table 3.12-1, broad leaf vegetation is required to be sampled only when milk sampling is not O L) ' Rev. O II 3-7 3/89 ___________m. _ _ _ _ _ _ - - - -

1 performed at all required locations. Broad leaf sampling will be performed at the specified locations if milk samples are unavailable O from any locu. ion. 1 s i i O 1 O Rev. O < II 3-8 3/89

                                           \[                     '[                                     k k r 1-Y                                                                         }.fb D*' Np-f N---w-                                                                                                                                       " < 'A ' A g                        ,

y'o , _ L-. i e '

                                                                                                                                                                                                                                                                                                                     "-h '.f' ' . ' . ~                                '~

94 x Q

N - 4h 't .Y /

R i '. p,jji[ D, D' ,g B f . 1

                                                     ,_    ea nxen co N                                                   [ .7                              jT '}j                                                                              -=

3 E.

 ,e < . T' 7 , __,    J
                                ~

no oo c o. N j 1- , -,. - y

%                      8' 4Q                           l                             u.             '                                          i t&T}gh
                                                                                                                                                                                   't i ,                                                        p/ rJ                        9
                                                                                                                                                                                                                                                                                                     %, '                                L           , (, ' i _ ' ' .                                 '

s - a ,by y,w i

                                                                                                                                                                                                                                                                                                                                                                                   \,\                  "
                                                     ~
                                                       ; $ y ,*,
                                                                                                   ,       -       r; 1 :.

u

                                                                                                                                               \ f} \ ~ ,\i l
                                                                                                                                                                                     'Y                \
                                                                                                                                                                                                               \

V

                                                                                                                                                                                                                                                      - r~b -
                                                                                                                                                                                                                                                                                                                                            \
                                                                                                                                                                                                                                                                                                                                              \        L;/-<J ,T(-
                                                                                           ~~_.                                                                            m. ., N_4 f .

h./ ,._ E.? h o pI f __ N\\'\; At s

                                                                                                                                                                                                                                                                  .m. l 7l' _                                                         '3y '~ ~,j       s.          ,,

Ir\

7 f , y gF -y (["

                                                  - *'I,0;,_l,4                                 s e &,..g \' ;~                                                                          G               y           f                     7h               T(dL 1i r g,- / , ,- ,4

r. <

r' - y r

- x' F '

3, _

                                                                                                              %. hdj f.. " s A\ -[ %

lb lo l Y' t h 'E.L 'v $, _ ,' T ' . /j!

                                                                                                                                                       ,l~~                                                                                            W                                                                                                        ('
                                                                                                ~
           ,                                                                 l'                                                                                                                                                                                                                                                    h'                                                       i
           $C) i% l V N D)td b;                                 .,                   ,'

s 'E/ 3, h '- [ ~ F $igW ;. a i_ y+ )

                                                                                                                                                                                                                                                                                                                                                       }-YghG r                 'Ng                        [

s pj hf ,

                                                                                  \ s x , L.. m -                                                                                                                                                            g\                                           ,

v{ v

                           ;'                  3 0                                            'l.                   '
                        / /t                                     .~

y, j T) lb / Nf Y .. y* h'w .. ' I r q' ' 4 - p

          .\s ; %
                                                             " ' J(.                      ,                  -

g f: -s .% .\

                                                                                                                                                                                                                                              's       5 9,._ . 4'
                                                                                                                                                                                                                                                                                      <4 '                                                               i y        '( ,
                                                                             ";,             I,     'c~           -      :.        s SV,                           v
                                                                                                                                 ~
                                                                                                                                                                                                                                              -                                                                                                                               ,                    sf i_y                                     s
                                                                                 .                            ,';                                       ,      3- ,\ .A                                                                                   -
                                                                                                                                                                                                                                                                    , v i ; ,, .

i

                                                                                                                                                                                                                                                                                                                               ~,,,p'_                    h         -cm,                        , il r  c f~~ g~-~ 9_x 4..G;*          -

s

                                                                                                                                's/      .

q , n- [ -\-

~>

8 n}1

L m m- g y ,,. y . d- r J ,- e , 44 " . . p. 4 ys +.y t ,, ; v

                                                                                                                                                                                                                                                                                                                                                               )' ,R 7 ,- q                                                      m              ,,,               g .us                                                  i.

m ; ( s i - _.x s. , , . , . , .> . - ,( s-

         ._ " L _ W'} ' $, m                                                                                                l- ; ,1 --                                                     ~~ Y f ~ ; --
                                                                                                                                                                                                                          ~
                                                                                                                                                                                                                                                                                                                            ~
           ? '; ~ygf ,' x 6% ..,4,
                                                                                         '                                R                                                                                       N +, ,
                                                                                                                                                                                                                                                            -d J                          ;                      a
                                                                                                                                                                                                                                                                                                                                . -?          ,,,,                                      l ,, d,
                                                                                                               'gl2{Ao                                                                   ; '                                                                                                                                                                         )o              .x t
                ,, .                                  , s.s              ?

q 5/ ,<

                                                                                                                                               >          ~
                                                                                                                                                         . '. g, ~ -.                           s N                     .9r                  r 4 e i

e, % . g'-

         '(,.                                r                                                              ~.,s                                                                                                                                                                                                                 - .i_ -                                                                  9cq 4                         .
                                                                                                                                                                                                                              ,                                                                                                                 .                                   )'vg

{

                !               \                                           l4     h                        .O

( \ p. , b ' ' o (t Y' y n ;p:A ,)( y ,,, 5' fy[e, C N / '

                                                                                                                                  /                                                            7                                                                                                                                                                               m',
        ,-                                        p).                                                      o r                                         x. -__..v 7 (\

eM %.,, . s

                                                                                                                                                                                                                                                                                                                                                                                                ,e i-Q                                                                                                                                                                                                                                                                                          y%
                             < -                                                                                                                                                                                                                                                                                            n
         /,.. g                                                   g y v, y.
                                                                                                                                   -ig.g,.                                              cp                                                                                  '

y

                                                                                                                                                                                                                                                                                                                                                                     ,      .m.

w. .

                     .kgl p'4-r/Vgu, a                       .s>
                                                                                                                       $ .-                           sa '"l4,e,sr                          .,        ' ~/.a ; \ :7 p. '? wm                                                                              % 4                    .
                                                                                                                                                                                                                                                                                                                                                            ^' m .?.

-j, w' y. .w g+a :w\. 1 I: ;

o% L e-( *p / -

                                                                                                                                                                                                                                                                                    \                                                                                                       -

y s f' u y 4 s. '.

                                                                                                  ~ c,                                 -

3 iA ,,, i .ps 1 ka , ',4 G,g fc

                                                            ,,..                                                       .: .R,                                                       /
                                                                                                                                                                                                                                                 *n                        :               ,                                    s                                                                 v

;, Mr (. 7, j x x

                                                                                                                              ,(',

n / -

p. , , ,

is - f i ..i y :P>< 1 . N,, n \ Ja ,, ,t /. y <___.__,_A___ 1%; x

1. i.Ti-1 t

                                                                                                    ] ', '. /
              ,g.( M es                                                                                                                                                                                                    t,,,                                                        i                                                                s        .r

n

                            \ d y ,' 3
                                                                                                                   +        =

4 s 3} ,_, , j, Q

                                                                                                                                                                \
                                                                                                                                                                                                                                       ,  -~ l' )\,.- \                                                                               g                                                           .

2 ._p.

                                                           > \c..a,A., , y!,

_# . g. . , . a ,_ (,k , 4, . w\

                                                                                                                                                                                                                                                                                                                                                            ..~ x" yu - < y/{.

_7

                                               ';' 4 4gjg-4'                                                       N V M. " /=-

s

                                                                                                                                                                                                '~                                               '
             / .; jf                                                                           r                                                                                                                                                                , o                         '\yh                                                                                q' f
               - i -          ,,,,,,

t

                                                              ' . i 'M ~

v, f.u / , % .6 2I Q',.>,.p( 41< y i' ll/- j Q /

y '.g ", p't , f '. '73 . h g,t ^ ,- N -

(, . ,

4

                                                                                               ,                                                  ,                                                                                                                       g                                                                .-                      ,
            /[ \
                                                                                                                                                                    ,                      h                 l l                                                                                                              Yh                                                     frh

e. ', t / , w'M ~-] ' L',

                                                                                                                         .'. , - ~ a                   s
                                                                                                                                                                           ^

4 59

                                                                                                                                                                                                               . -Q . !n:, * ' 6 12 .
                                                                                                                                                                                                                                                                          't                                   i ,,
                                                                                                                                                                                                                                                                                                                                                                                            ^7

i' ?

         ;                 { },% +L}y                                                                                                                       % '.% y f
                                                                                                                                                                                                                       - yf                  b f ~Y:Q.                                                            'V-%            g ~~R;                 L -.L:.y.                               _&

v . i' yG -- : - e cy , r \, L P% ( M,.t 7,p h ,.y

                              ' ' \.' L c,,,. ,/J                  i lh n [Q' [
                                                                                                  --,,g,L.-,'%

_, .h1. ' ..4 K

J S h p s d, \*i ,%V .- f'3, _

~'

Locations Greater than 2 Miles from the Station

  .n.,,

{pTM. - W l

  ,9 nfV<                U    $'             <

i,) l ^ h\Y: ,. - [ .pIM 3, l

  ~y ' hf'Y %).
     ,                                  s             6         s         ,

V,' s .x, -',

                                                                                                                                                                                  ', v                'l         s ,- 'N
                                                 ,4                3'),-                                          ,

m

4 . tf I f 't' f s I.

  's ,                                                                                            -
     ?

x,

                              % 'h .

T. a%;g)..,.-Q \ - n N ,.1 ,, 9

                           ,, ..,k>                                 M l

IAh 1'

   ^,e,                                                                                                      s                                                                                                                                   /

r'f..N .

                               ,                                %,                              J                                                                               -

y ' , t ..y '.

                                                                                  ~f                                                 L
                                                                    , , 'M. I                                                                                                                                                h\_ / '

TI K , , ,

p. , z.'

                                                '?                                                                                                                                                                                      ,'
                                                                   ; J n'U,                                                                                                                                                                         'n
                                                      & c.

f}

                              ,y                                                                                                               ,-                                               ,.

c vs '

>\

f' i d - l

              *         ',f. [s                   -
                                                                                                    .&                                    /                                                               .

l,

7-

                                                         '\'v                                 <

_X394 1 S .- ,

                                                                                                                                    /. ,    .-
                                                                                                                                                       =

m ,_ \ h

                                                                                                                                                     ~
                            '&                        -(r- L'b-
                                                                                                          .g                ,A                           '",        ^
                                                                                                                                                                                                   -~ M,'

3 r,c 't,9! s, A .g, *3 i N g x I A$ q x [ 1 a l.y i s 3 k t

~,,,2 h_ - 'N_.______-
_. d:1 y . ( # / M 'O ' i byk Locatiens Within 2 Miles of the Station
>NJh, 'y , f A, c%ri, -* ?
W g~ l
%7 s . j r~p i, r '. ~ -. > ,,, ; w.w / ',c to'f '&. ' -_ .3 f , 'l s y b 'f4, y;% G , p
c* v .
y' #, s a , g s =.*
,L. -, .w s
k- .. y ; .X-
,. s .. v ~'s3 _h d ' *J q Figure 3.1 ;IN$ M%... f -- L ;c ; a--
y f n ,- r, y MT' Radiological Environmental
' <, 3GA
_,
7 M nit ring Locations
, e y, L -u , 'y - "u s ~ . . ';. -,, v ' , e s APERTURE g- . < ~;-I~l] ^ CARD ipij ;%, ) < - 's .
d g; i Also AvaMalde On 1 s g. .j, t- wr- Aperture Card 7n I{e %. - y II 3-9 Rev. 0 3/89 DY .-.
APPENDIX A PATHWAY DOSE RATE PARAMETER O P (inhalation) = K' (BR) DFA [Eq. A-1] where: Pi - the pathway dose rate parameter for radionuclides, i, (other than noble gases) for the inhalation pathway, in mrem /yr per microcurie /m3 The dose factors are based on the critical individual organ for the child age group. k' - conversion factor, 106 pCi/ microcurie BR = 3700 m3/yr, breathing rate for child (Ref. 2, Table E-5) DFAj - the maximum organ inhalation dose factor for the child age group for the ith radionuclides (mrem /pCi). Values are taken from Table E-9, Reg. Guide 1.109 (Ref. 2) Resolution of the units yields: \ P (inhalation) = 3.7 x 109 DFAg (mrem /yr per uCi/us ) [Eq. A-2) The latest NRC Guidance has deleted the requirement to determine P i (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child. Rev. O II A-1 3/89 O
APPENDIX B I INHALATION PATHWAY DOSE FACTOR (R i,a,o) l { Rf,,,g = k' (BR) (DFA ) (mrem /yr per microcurie /m8 ) [Eq. B-1] where: k' - conversion factor, 106 pC1/ microcurie ! BR - breathing rate, 1400, 3700, 8000 m3/yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2, Table E-5) DFAi ,a,o - the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclides, in mrem /pci. The total body is considered as an organ in the selection of q DFAi ,a,0 Values are taken from Tables E-7 through E-10, ) Reg. Guide 1.109 (Ref.2) O l Rev. O II B-1 3/89 O
APPENDIX C i I GROUND PLAN PATHWAY DOSE FACTOR (R G j) { i
~
t R = k' k" (SF) DFG [(1-e i )/ A ) [Eq. C-1) where: k' = conversion factor, 106 pCi/ microcurie ! k" = Conversation factor, 8760 hr/yr A i - Decay constant for the ith radionuclides, sec -1 t = the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs) DFGi = the ground plane dose conversion factor for the ith radionuclides (mrem /hr per pCi/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Ref. 2). These values - apply to all age groups. O SF = 0.7, shielding factor, from Table E-15 Reg.. Guide 1.109 (Ref. 2) I l 1 i Rev. O II C-1 3/89 i O 1 1
APPENDIX D C GRASS C0W-MILK PATHWA'! DOSE FACTOR (R i,a,o)
- 1 R = k' [(Q p xU g) / ( ) +A y)] x (F ) x (r) x (DFL )x ~ -AU
[((f x f,)/ Y ) + ((1-f x f,) e i h)/Y,] e if [Eq. D-1] I where: k' - conversion factor, 106 picocurie / microcurie (pCi/uci) QF - cow consumption rate, 50 kg/ day, (R.G. 1.109) VAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for infant, child, teenager, and adult age groups, respectively (R.G.1.109) Yp - agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG-0133) Ys - agricultural productivity by unit area of stored feed, V 2.0 kg/m2, (NUREG 0133) i Fm - stable element trans'fer coefficient (Table E-1, R.G. ; 1.109) l r - fraction of deposited activity retained in cow's feed grass, 0.2 for particulate, 1.0 for radioiodine (Table E-15, R.G.1.109) DFli ,a,o - the ingestion dose factor for organ, o, and the ith radionuclides for each respective age group, a (Tables E-11 to E-14, R.G. 1.109) 1 - decay constant for the ith radionuclides, sec-1 i A, - decay constant for weathering, 5.73 x 10-7 sec -1 l (NUREG-0133) tr - 1.73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-15, R.G.1.109) Rev. O II D-1 3/89 0) c
l l l APPENDIX D (CONTINUED) l th = 7.78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, R.G.
.1.109) fp = 1.0, the fraction of the year that the cow is on pasture.
fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture. The concentration of tritium in milk is based on the airborne concentration ( rather than the deposition. Therefore, RC i is based on (X/Q): R = k'k F,QpUg DFL (.75 (.5/H)) (Eq. D-2] tM I where: k - 103 grams /kg V 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)
DFLt ,a,o - the ingestion dose factor for tritium and organ, o, ! for each respective age group, a (Tables E-11 to E-14, R.G. 1.109) l All other parameters and values are as given above. I i C NOTE: Goat-milk pathway factor, R i,a,o will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2 R.G.1.109. Rev. 0 II D-2 3/89 O
APPENDIX E O d COW-MEAT PATHWAY DOSE FACTORM (R j,,,g) R g = k' (QF xUg)/(Af . + A ,) x (Ff ) x (r) x (DFL )x (((! x f,)/Y p) + ((1 - f f,) e ~Ai *h)/Y,) x e-AE i f [Eq. E-1] where: k' - conversion factor, 106 picocurie / microcurie (pCi/uci)
.QF - cow consumption, rate, 50 kg/ day, (R.G. 1.109)
UAP = Receptor's meat consumption rate; 0, 41, 65, 110 ' kg/yr for infant, chi'id, teenager, and adult age groups, respectively (R.G. 1.109) l Ff - the stable element transfer coefficients, days /kg. (Table E-1, R.G.1.109) Or - fraction of deposited activity retained in cow's feed grass, 0.2 for particulate,1.0 for radiciodine
).
(Table E-15, R.G.1.109) l DFLi ,a,o - the ingestion dose factor for organ, o, and the ith radionuclides for each respective age group, a (Tables ) E-11 to E-14, R.G. 1.109) A i - decay constant for radionuclides i, sec-1 A, - decay constant for weathering, 5.73 x 10-7 sec -1 l (NUREG-0133) tf - 1.73 x 106 sec, the transport. time from pasture to receptor (NUREG-0133) th - 7.78 x 106 sec, the transport time from crop to receptor ! (NUREG-0133) Rev. 0 II E-1 3/89 O
l 1 APPENDIX E (CONTINUED) O I U Yp - agricultural productivity by unit area of pasture feed l grass, 0.7 kg/m2 (NUREG-0133). Ys . agricultural productivity by unit area of stored feed, 2.0 kg/m2, (NUREG 0133) fp - 1.0, the fraction of the year that the cow is on pasture. fs = 1.0, the fraction of the cow feed that is pasture grass I while the cow is on pasture. The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore RMi is based on (X/Q): I M = R (Eq. E-2) t a.o
F g pQ AP U (D Rt,,,o) x 0.75 x (0.5/H) where:
i l All terms are as defined above and in Appendix D. I I 1 l l a i Rev. O i II E-2 3/89
APPENDIX F G Y VEGETATION PATHWAY 00SE FACTOR (R j y ) R = k' x (r/ (Yy (A +g A ))) y x ( Mg ,,, o) X l A} L*
~
S
+U f e i*h] [Eq. F-1]
A g where: k' - 106 picocurie / microcurie (pCi/uti) UL A
- the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 f kg/yr for infant, child, teenager, or adult age groups respectively. (R.G. 1.109)
US A - the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively. (R.G. 1.109) f L = the fraction of the annual intake of fresh leafy ! vegetation grown locally, 1.0 (NUREG-0133) f g - the fraction of the stored vegetation grown locally .76 l i (NUREG-0133) t l - the average time between harvest of leafy vegetation and l its consumption, 8.6 x 104 seconds (Table E-15, R.G. l 1.109 (24 hrs)) l t h - the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds (Table E-15, R.G.1.109 (60 days)) Rev. O II F-1 3/89
a APPEtl0IX F (CONTIflVED) yh - the vegetation areal density, 2.0 kg/m2 (Table E-IS, R.G. 1.109) All other parameters are as previously defined.
]
The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, RV i is based on (X/Q) l R = k'k (U fL+U f]g (DFL ) (.75 (.5/H)) (Eq. F-2] where: i All terms are as defined above and in Appendix D. O 1 l l 9 Rev. 0 II F-2 3/89 (")
~_
- _ _ _ _ _ _ _ _. _ _ _ _ . . _ . . . - . - - . - _ _ - _ _ _ - _ _ _ . _m_______ _ _ . . -}}

ML20235R248

Text

Navigation menu

Search