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{{#Wiki_filter:Enclosure | {{#Wiki_filter:Enclosure 2 Comanche Peak Offsite Dose Calculation Manual (ODCM) | ||
COMANCHE PEAK STEAM ELECTRIC | COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL UNIT 1 AND UNIT2 TABLE OF CONTENTS Number/Title List of Tables List of Figures Cross-Reference to Technical Specifications and REC References Introduction PART I -RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 -USE AND APPLICATIONS SECTION 1.1 -DEFINITIONS SECTION 2.0 -NOT USED SECTIONS 3.0 AND 4.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 -Applicability 3/4.3.3.4 | ||
-Radioactive Liquid | -Radioactive Liquid Effluent Monitoring Instrumentation 3/4.3.3.5 | ||
-Radioactive Gaseous | -Radioactive Gaseous Effluent Monitoring Instrumentation 3/4.3.3.6 | ||
-Meteorological Monitoring Instrumentation 3/4.7.15 | -Meteorological Monitoring Instrumentation 3/4.7.15 -Sealed Source Contamination 3/4.11.1 -Liquid Effluents 3/4.11.1.1 | ||
-Sealed Source Contamination 3/4.11.1 | -Concentration Controls 3/4.11.1.2 | ||
-Liquid Effluents 3/4.11.1.1 | -Dose 3/4.11.1.3 | ||
-Concentration | -Liquid Radwaste Treatment System 3/4.11.1.4 | ||
- | -LVW Pond Resin Inventory 3/4.11.2 -Gaseous Effluents 3/4.11.2.1 | ||
-Liquid Radwaste Treatment | -Dose Rate 3/4.11.2.2 | ||
-LVW Pond Resin Inventory 3/4.11.2 | -Dose -Noble Gases 3/4.11.2.3 | ||
-Gaseous Effluents 3/4.11.2.1 | -Dose -Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form 3/4.11.2.4 | ||
-Dose | -Gaseous Radwaste Treatment System 3/4.11.4 -Total Dose 3/4.12.1 -Radiological Environmental Monitoring Program Paqe v vi vii x XI xi 11-0 11-1 I 2-0 I 3/4-0 I 3/4-1 I 3/4-2 I 3/4-8 I 3/4-14 I3/4-16 I3/4-18 13/4-18 13/4-23 13/4-24 13/4-25 13/4-27 I3/4-27 13/4-31 13/4-32 I 3/4-33 I 3/4-34 I 3/4-35 CPSES -UNITS 1 AND 2- ODCM Rev. 32 TABLE OF CONTENTS (continued) | ||
-Dose -Noble | Number/Title Page 3/4.12.2 -Land Use Census I 3/4-46 3/4.12.3 -Interlaboratory Comparison I 3/4-47 Program BASES I B 3/4-0 SECTION 5.0 -DESIGN FEATURES I 5-0 5.1.3 -Map Defining Controlled Areas, I 5-1 Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents SECTION 6.0 -ADMINISTRATIVE CONTROLS I 6-0 6.9.1.3 -Annual Radiological Environmental I 6-1 Operating Report 6.9.1.4 -Radioactive Effluent Release Report I 6-2 6.14 -Offsite Dose Calculation Manual I 6-3 (ODCM)PART II -CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS I1-1 1.1 10CFR20 and Radiological Effluent Control I1-1 3/4.11.1.1 Compliance 1.1.1 Isotopic Concentration of the 111-2 Waste Tank 1.1.2 Effluent Flow Rate (f) 111-2 1.1.3 Dilution of Liquid Effluents 11 1-3 1.1.4 Actual Dilution Factor (ADF) 111-4 1.1.5 Required Dilution Factor (RDF) 111-4 1.1.6 10CFR20 Compliance 111-5 1.2 Radiation Monitor Alarm Setpoints 111-5 1.2.1 Primary Liquid Effluent Monitor Il1-5 (XRE-5253) 1.2.2 Turbine Building Sump Effluent 111-6 Radiation Monitors (1RE-5100 and 2RE-51 00)1.2.3 Station Service Water Effluent Radiation 111-7 Monitors (1 RE-4269/4270 and 2RE-4269/4270) | ||
-Dose -Iodine-131, Iodine-133, | CPSES -UNITS 1 AND 2- ODCM ii Rev. 32 TABLE OF CONTENTS (continued) | ||
Number/Title Paqe 1.2.4 Auxiliary Building to LVW Pond 111-8 Radiation Monitor (XRE-5251A) 1.3 Dose Calculations for Liquid Effluents 111-8 1.3.1 Calculation of Dose Due to 111-9 Liquid Releases 1.3.2 Calculation of Dose Due to 111-10 Radionuclide Buildup in the Lake 1.4 Dose Projections for Liquid Effluents 11 1-12 1.5 Definitions of Common Liquid Effluent 111-12 Parameters 2.0 GASEOUS EFFLUENTS II 2-1 2.1 Radiological Effluent Control 112-2 3/4.11.2.1 Compliance 2.1.1 Dose Rates Due to Noble Gases 112-2 2.1.2 Dose Rates Due to Radioiodines, 112-4 Tritium, and Particulates 2.2 Gaseous Effluent Monitor Setpoints 112-4 2.2.1 Plant Vent Effluent Release Rate 112-5 Monitors (XRE-5570A/XRE-5570B) | |||
-Gaseous Radwaste Treatment | Effluent Release Rate Channels 2.2.2 Plant Vent Stack Noble Gas Activity II 2-6 Monitors (XRE-5570A/XRE-5570B and XRE-5567A/XRE-5567B) 2.2.3 Sampler Flow Rate Monitors II 2-6 (X-RFT-5570A-1/X-RFT-5570B-1) 2.2.4 Auxiliary Building Ventilation II 2-6 Exhaust Monitor (XRE-5701) 2.2.5 Containment Atmosphere Gaseous II 2-7 Monitors (1 RE-5503/2RE-5503) 2.3 Dose Calculations for Gaseous Effluents 112-8 2.3.1 Dose Due to Noble Gases 112-8 2.3.2 Dose Due to Radioiodines, Tritium, C-14, II 2-9 and Particulates 2.4 Dose Projections for Gaseous Effluents II 2-11 2.5 Dose Calculations to Support Other II 2-11 Requirements CPSES -UNITS 1 AND 2- ODCM iii Rev. 32 TABLE OF CONTENTS (continued) | ||
-Total | Number/Title 2.6 Meteorological Model 2.6.1 Dispersion Calculations 2.6.2 Deposition Calculations 2.7 Definitions of Gaseous Effluents Parameters 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 Sampling Locations 3.2 Interlaboratory Comparison Program APPENDICES A. Pathway Dose Rate Parameter B. Inhalation Pathway Dose Factor C. Ground Plane Pathway Dose Factor D. Grass-Cow-Milk Pathway Dose Factor E. Cow-Meat Pathway Dose Factor F. Vegetation Pathway Dose Factor G. Supplemental Guidance Statements | ||
-Radiological Environmental Monitoring | -Deleted Paqe 112-12 II 2-12 II 2-14 II 2-14 II 3-1 II 3-1 II 3-1 A-1 B-1 C-1 D-1 E-1 F-1 G-1 CPSES -UNITS 1 AND 2- ODCM iv Rev. 32 TABLE OF CONTENTS LIST OF TABLES Table No. Title Page PART I -RADIOLOGICAL EFFLUENT CONTROLS 1.1 ODCM Frequency Notation 11-5 1.2 Deleted. 11-6 3.3-7 Radioactive Liquid Effluent Monitoring Instrumentation I 3/4-3 4.3-3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements I 3/4-6 3.3-8 Radioactive Gaseous Effluent Monitoring Instrumentation I 3/4-9 4.3-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 13/4-12 3.3-9 Meteorological Monitoring Instrumentation I 3/4-15 4.11-1 Radioactive Liquid Waste Sampling And Analysis Program I 3/4-19 4.11-2 Radioactive Gaseous Waste Sampling and Analysis Program I 3/4-28 3.12-1 Radiological Environmental Monitoring Program 13/4-37 3.12-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples I 3/4-43 4.12-1 Detection Capabilities For Environmental Sample Analysis LLDs I 3/4-44 PART II -CALCULATIONAL METHODOLOGIES 1.1 Summary of Liquid Release Pathways 111-15 1.2 Site Related Ingestion Dose Commitment Factor Air 111-16 2.1 Summary of Gaseous Release Pathways II 2-18 2.2 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases II 2-19 2.3 Pathway Dose Rate Parameter (Pi) Il 2-20 2.4 Pathway Dose Factors II 2-21 2.5 Controlling Receptor Pathways and Locations, and Atmospheric Dispersion Parameters (for Dose Calculations Required by Radiological Effluent Control 3/4.11.2.3) | ||
Number/Title | II 2-42 3.1 Environmental Sampling Locations II 3-2 CPSES -UNITS 1 AND 2- ODCM V Rev. 27 TABLE OF CONTENTS LIST OF FIGURES Figure Title Page PART I -RADIOLOGICAL EFFLUENT CONTROLS 5.1-3 Controlled Area, Unrestricted Area and Site Boundary for Radioactive Gaseous and Liquid Effluents I 5-2 PART II -CALCULATIONAL METHODOLOGIES 1.1 Liquid Effluent Discharge Pathways 11 1-20 1.2 Circulating Water Pump Curves 11 1-21 1.3 Energy Response to Gamma Radiations for RD-33 Type Detector 11 1-22 2.1 Gaseous Waste Processing System II 2-43 2.2 Plume Depletion Effect for Ground-Level Releases II 2-44 2.3 Vertical Standard Deviation of Material in a Plume II 2-45 2.4 Relative Deposition for Ground-Level Releases II 2-46 2.5 Open Terrain Correction Factor II 2-47 3.1 Radiological Environmental Monitioring Locations II 3-3 CPSES -UNITS 1 AND 2- ODCM vi Rev. 27 CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC Number or Document Section Requirement ODCM Section PART I-RADIOLOGICAL EFFLUENT CONTROLS (REC)Tech Spec 4.1 Site Location/Map 5.1.3 and Fig. 5.1-3 Tech Spec 5.5.1 Offsite Dose Calculation Manual 6.14 (ODCM)Tech Spec 5.5.4.a Effluent monitoring instrumentation 3/4.3.3.4 and operability, surveillance, and 3/4.3.3.5 setpoint requirements Tech Spec 5.5.4.b Limit liquid effluent concentration 3/4.11.1.1 Tech Spec 5.5.4.c Effluent monitoring, sampling, and 3/4.11.1.1 and analysis requirements 3/4.11.2.1 Tech Spec 5.5.4.d Limit doses due to liquid effluents 3/4.11.1.2 Tech Spec 5.5.4.e Determine cumulative and projected 3/4.11.1.2, doses due to radioactive effluents 3/4.11.2.2. | ||
-Land Use Census I 3/4- | Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec REC REC 5.5.4.f 5.5.4.g 5.5.4.h 5.5.4.i 5.5.4.j 5.6.2 5.6.3 PART II -3/4.11.1.1 3/4.11.1.2 Effluent treatment systems operability requirements Limit gaseous effluent dose rate Limit noble gas air dose Limit gaseous effluent iodine and particulate dose Limit total dose Annual Radiological Environmental Operating Report Radioactive Effluent Release Report CALCULATIONAL METHODOLOGIES 3/4.11.2.3 3/4.11.1.3 and 3/4.11.2.4 3/4.11.1.3 and 3/4.11.2.4 3/4.11.2.1 3/4.11.2.2 3/4.11.2.3 3/4.11.4 6.9.1.3 6.9.1.4 1.1 1.3 Liquid effluent concentration Dose due to liquid effluents CPSES -UNITS 1 AND 2- ODCM vii Rev. 23 CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC (continued) | ||
-Interlaboratory Comparison I 3/4- | Document REC REC REC Number or Section 3/4.11.1.3 3/4.11.2.1.a 3/4.11.2.1 .b Requirement Dose projections for liquid releases Dose rate due to noble gases Dose rate due to iodine, tritium, and particulates with half-lives greater than eight days Air dose due to noble gases Doses due to iodine, tritium, and particulates with half-lives greater than eight days Dose projections for gaseous releases ODCM Section 1.4 2.1.1 2.1.2 2.3.1 2.3.2 2.4 REC REC 3/4.11.2.2 3/4.11.2.3 REC REC REC REC 3/4.11.2.4 3/4.11.4 3/4.12.1 3/4.12.2 REC REC 3/4.12.3 3.3.3.4 Total dose due to releases of radioactivity and direct radiation Description of radiological environmental sampling locations Dose calculations for identifying changes to environmental sampling locations Description of the Interlaboratory Comparison Program Radioactive liquid effluent monitoring channels alarm/trip setpoints* liquid waste monitor (XRE-5253) | ||
CPSES -UNITS 1 AND 2- | * turbine building sump monitors (1 RE-51 00 and 2RE-51 00)* service water monitors (1 RE-4269/4270 and 2RE-4269/4270) | ||
Number/Title | * auxiliary building to LVW Pond radiation monitor (XRE-5251A) 2.5 3.1 2.5 3.2 1.2.1 1.2.2 1.2.3 1.2.4 CPSES -UNITS 1 AND 2- ODCM viii Rev. 23 CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC (continued) | ||
Effluent Release Rate | Number or Section Document Requirement ODCM Section REC 3.3.3.5 Radioactive gaseous effluent monitoring channels alarm/trip setpoints" noble gas release rate monitors XRE-5570A and XRE-5570B (WGRM release rate channels)" noble gas activity monitors XRE-5570A and XRE-5570B (WRGM low range activity channel) XRE-5567A and XRE-5567B (noble gas channel)" waste gas holdup system monitor (auxiliary building vent monitor) XRE-5701* sampler flow rate monitor XFT-5570A2/B2 Radiation monitoring channels alarm/trip setpoint Containment atmosphere gaseous monitors (containment vent monitors) 1 RE-5503 and 2RE-5503 2.2.1 2.2.2 2.2.4 2.2.3 Tech Spec 3.3.6 2.2.5 Tech Spec REC Tech Spec REC Tech Spec REC 5.6.3 6.9.1.4 5.6.3 6.9.1.4 5.6.3 6.9.1.4 Assessment of radiation doses due 2.5 to liquid and gaseous effluents released during the previous year Assessment of doses to members of the public inside the site boundary Assessment of doses to the most likely exposed member of the public from reactor releases and direct radiation 2.5 2.5 CPSES -UNITS 1 AND 2- ODCM ix Rev. 23 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," TU Electric, Comanche Peak Steam Electric Station.4. "Final Safety Analysis Report," TU Electric, Comanche Peak Steam Electric Station.5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976).6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111, Rev. 1 (July 1977).7. Meteorology and Atomic Energy; Edited by Slade, D. H.; U. S. Department of Commerce (July 1968).8. "Technical Specifications," TU Electric, Comanche Peak Steam Electric Station.9. Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01), USNRC, January 31, 1989.10. CPSES Technical Evaluation No. RP-90-3077, "Calculation of Site Related Ingestion Dose Commitment Factors For Sb-122." 11. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," USNRC Regulatory Guide 1.109 (March 1976).12. Code of Federal Regulation, Title 10, Parts 20, 50, and 72.CPSES -UNITS 1 AND 2- ODCM X Rev. 31 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the CPSES Technical Specifications. | |||
Number/Title 2.6 Meteorological | Part I of the ODCM contains (1) the Radioactive Effluent Controls required by Technical Specification 5.5.4, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3, (3) Controls for Meteorological Monitoring Instrumentation and Sealed Source Leakage, and (4) Radiological Environmental Monitoring Controls. | ||
- | Part II of the ODCM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. | ||
11- | Liquid and Gaseous Radwaste Treatment System configurations are shown in Part II, Figures 1.1 and 2.1.The ODCM is maintained for use as a reference guide and training document on accepted methodologies and calculations. | ||
II 2- | Changes in the 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. TXU Power initiated changes to the ODCM will be implemented in accordance with Section 5.5.1 of the Technical Specifications. | ||
The ODCM follows the methodology and models suggested by NUREG-0133 (Ref. 1) and Regulatory Guide 1.109, Revision 1 (Ref. 2). Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementing the Radiological Effluent Control requirements. | |||
Tech | This simplified approach will result in a more conservative dose evaluation, but requires the least amount of time for establishing compliance with regulatory requirements. | ||
This manual is designed to provide necessary information in order to simplify the dose calculations. | |||
. | The dose calculations can be optionally expanded to several levels of effort. The complexity of the dose calculations can be expanded by several levels of effort, aiming toward a full calculation in accordance with Regulatory Guide 1.109. Future changes to the 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. | ||
* liquid waste monitor (XRE-5253) | A beneficial approach to implementing the Radiological Effluent Control Program and Regulatory Guide 1.21 (Radioactive Effluent Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses.CPSES -UNITS 1 AND 2- ODCM xi Rev. 23 PART I RADIOLOGICAL EFFLUENT CONTROLS CPSES -UNITS 1 AND 2- ODCM SECTION 1.0 USE AND APPLICATIONS CPSES -UNITS 1 AND 2- ODCM PART 1 1-0 Rev. 28 1.0 USE AND APPLICATIONS | ||
* turbine building sump monitors(1 RE-51 00 and 2RE-51 00)* service water monitors(1 RE-4269/4270 | |||
* auxiliary building to LVW | |||
Number | |||
" noble gas release rate | |||
" noble gas activity | |||
XRE-5567A | |||
XRE-5701* sampler flow rate | |||
: 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 ( | |||
TU Electric, Comanche Peak Steam Electric Station.4. "Final Safety Analysis Report," | |||
TU Electric, Comanche Peak Steam Electric Station.5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents | |||
TU Electric, Comanche Peak Steam Electric Station.9. Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications | |||
Part I of the ODCM contains (1) the Radioactive | |||
Part II of the ODCM describes the methodology | |||
Liquid and Gaseous Radwaste Treatment System configurations are shown | |||
Changes in the calculation methods or parameters will | |||
The ODCM follows the methodology and models suggested by NUREG-0133 (Ref. 1) | |||
This simplified approach will result in a | |||
This manual is designed to provide necessary information in order to simplify the | |||
The dose calculations can be optionally expanded to several levels of effort. | |||
A beneficial approach to implementing the Radiological Effluent Control Program and Regulatory Guide 1.21 (Radioactive Effluent Release Report) requirements is to use a computerized | |||
===1.1 DEFINITIONS=== | ===1.1 DEFINITIONS=== | ||
The defined terms of this section appear in capitalized type and are applicable throughout | The defined terms of this section appear in capitalized type and are applicable throughout these Controls.ACTION ACTION shall be that part of a Control that prescribes required actions to be taken under designated conditions within specified completion times.ANALOG CHANNEL OPERATIONAL TEST 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 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. | |||
The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, | The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. | ||
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output | Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping or total channel steps.CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. | ||
The CHANNEL CALIBRATION shall encompass all devices in | 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. | ||
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in | DIGITAL CHANNEL OPERATIONAL TEST A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions. | ||
The CHANNEL CALIBRATION may be performed by means of any series | DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same does when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or from Table E-7 of CPSES -UNITS 1 AND 2- ODCM PART I11-1 Rev. 28 DEFINITIONS Regulatory Guide 1.109, Revision 1, NRC, 1977, or from ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. | ||
This determination shall include, where possible, comparison of the | The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil", or using the dose conversion factors from Table B-1 of Regulatory Guide 1.109, Revision 1, NRC, 1977.FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.MEMBER(S) | ||
DIGITAL CHANNEL OPERATIONAL | OF THE PUBLIC MEMBER(S) | ||
DOSE EQUIVALENT 1- | OF THE PUBLIC means an individual in a CONTROLLED or UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 5.5.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3, respectively. | ||
The determination of DOSE EQUIVALENT 1- | OPERABLE -OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). | ||
or from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors | CPSES -UNITS 1 AND 2- ODCM PART 1 1-2 Rev. 28 DEFINITIONS PRIMARY PLANT VENTILATION SYSTEM A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed and installed to reduce gaseous radioiodine 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 particulates from the gaseous exhaust stream prior to the release to the environment. | ||
DOSE EQUIVALENT XE- | |||
If a specific noble gas nuclide is not detected, it should be assumed to be present at | |||
The determination of DOSE EQUIVALENT XE-133 shall | |||
OF THE | |||
OF THE PUBLIC means an individual in a CONTROLLED or UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which | |||
The ODCM shall also contain (1) | |||
OPERABLE | |||
-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, | |||
CPSES -UNITS 1 AND 2- | |||
Such a system is not considered to have any effect on noble gas effluents. | Such a system is not considered to have any effect on noble gas effluents. | ||
PURGE - | PURGE -PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement. | ||
RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3458 MWt through Cycle 13 for Unit I and through Cycle 11 for Unit 2. Starting with Cycles 14 and 12 of Units 1 and 2, respectively, RTP shall be 3612 MWt.REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 1 OCFR50.73. | |||
RATED THERMAL | SITE BOUNDARY The SITE BOUNDARY shall be that line as shown in Figure 5.1-3.SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. | ||
SITE | THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.UNRESTRICTED AREA An UNRESTRICTED AREA means any area beyond the SITE BOUNDARY.VENTING 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.CPSES -UNITS 1 AND 2- ODCM PART 1 1-3 Rev. 28 DEFINITIONS WASTE GAS HOLDUP SYSTEM 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 the purpose of reducing the total radioactivity prior to release to the environment. | ||
THERMAL | CONTROLLED AREA A CONTROLLED AREA means an area outside of a restricted area, as defined in 10 CFR 20.1003, but inside the SITE BOUNDARY, access to which can be limited by the licensee for any reason.CPSES -UNITS 1 AND 2- ODCM PART 1 1-4 Rev. 28 TABLE 1.1 ODCM FREQUENCY NOTATION NOTATION S D w M Q SA SR R S/U N.A.P FREQUENCY At least once per 12 hours.At least once per 24 hours.At least once per 7 days.At least once per 31 days At least once per 92 days.At least once per 184 days.At least once per 9 months.At least once per 18 months.Prior to each reactor startup.Not applicable. | ||
Completed prior to each release.CPSES -UNITS 1 AND 2- ODCM PART I11-5 Rev. 27 TABLE 1.2 This Table is Deleted.CPSES -UNITS 1 AND 2 -ODCM PART 1 1-6 Rev. 27 SECTION 2.ONOT USED CPSES -UNITS 1 AND 2 -ODCM PART 1 2-0 Rev. 23 SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS CPSES -UNITS 1 AND 2- ODCM PART I13/4-0 Rev. 33 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY The guidance provided for the use and application of LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY in Section 3.0, "LIMITING CONDITION FOR OPERATION (LCO)APPLICABILITY" of the Technical Specifications is applicable to the Controls contained in this manual, except as noted below.The guidance provided for the use and application of SURVEILLANCE REQUIREMENT (SR)APPLICABILITY in Section 3.0, "SURVEILLANCE REQUIREMENT (SR) APPLICABILITY" of the Technical Specifications is applicable to the Surveillance Requirements contained in this manual.For the purpose of the ODCM, the ODCM terms specified below should be considered synonymous with the listed Technical Specification term: ODCM Control ACTION Technical Specification LCO Required Action A cross reference between Section 3/4.0 of the Offsite Dose Calculation Manual (ODCM) and the applicable Section 3.0 of the Technical Specifications is as follows: ODCM Control: 3.0.1 Technical Specification Section LCO 3.0.1 3.0.2 N/A (see Note 1)N/A (see Note 1)N/A (see Note 1)N/A (see Note 1)N/A (see Note 1)ODCM Surveillance Requirement: | |||
LCO 3.0.2 LCO 3.0.3 LCO 3.0.4 LCO 3.0.5 LCO 3.0.6 LCO 3.0.7 Technical Specification Section 4.0.1 4.0.2 SR 3.0.1 SR 3.0.2 SR 3.0.3 SR 3.0.4 4.0.3 N/A (see Note 1)-NOTE 1 -The provisions of the cross referenced Technical Specification LCO/SR are not pertinent for use in the ODCM; therefore, the Technical Specification LCO/SR is not applicable (N/A).CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-1 Rev. 33 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.4 In accordance with CPSES TS 5.5.4.a, 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. | |||
Vent, used | The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).APPLICABILITY: | ||
CONTROLLED | 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. | ||
Completed prior to each release.CPSES -UNITS 1 AND 2- | : 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 Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.SURVEILLANCE REQUIREMENTS 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.CPSES -UNITS 1 AND 2- ODCM PART I13/4-2 Rev. 33 TABLE 3.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE INSTRUMENT | ||
LCO 3.0. | : 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluent Line (XRE-5253) | ||
The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with | : b. Turbine Building (Floor Drains) Sumps Effluent Lines (IRE-5100 | ||
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 | & 2RE-5100)c. Auxiliary Building to LVW Pond Liquid Effluent Line (XRE-5251A) | ||
: b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels | : 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a. Service Water System Effluent Lines (1RE-4269, IRE-4270, 2RE-4269 & 2RE-4270)3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line (XFT-5288) | ||
ACTION 1 1/sump i 1/train 1 30 31 31A 32 33 CPSES -UNITS 1 AND 2- ODCM PART I13/4-3 Rev. 33 TABLE 3.3-7 (Continued) | |||
: 1. Radioactivity Monitors Providing Alarm | ACTIONS STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a 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 OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/mi: | ||
: b. Turbine Building (Floor Drains) Sumps Effluent Lines(IRE-5100 | : a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT 1-131;or b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT 1-131. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.) | ||
& 2RE-5100) | ACTION 31A- With number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower-limit of detection of no more than 5 x 10-7 microCurie/ml at least once per 12 hours.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 (uRE-4509, uRE-4510,&uRE-451 1)* OPERABLE and indicating an activity of less than 1X10-4 micro Curie/ml, a grab sample is collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml at least every 31 days; or* "u" designates monitor for the applicable unit, e.g., 1 or 2.CPSES -UNITS 1 AND 2- ODCM PART13/4-4 Rev. 33 TABLE 3.3-7 (Continued) | ||
: 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of | |||
& 2RE-4270) | |||
ACTIONS STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the | |||
: a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT 1-131; | |||
ACTION 31A- With number of channels OPERABLE less than required by the | |||
&uRE-451 1)* OPERABLE and indicating an activity of less than 1X10- | |||
ACTIONS STATEMENTS (Continued) | ACTIONS STATEMENTS (Continued) | ||
: b. At least once per 12 hours, grab samples are collected and analyzed | : b. At least once per 12 hours, grab samples are collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.) | ||
(Refer to Notation 3 of Table 4.11-1 for | NOTE: Collection of grab samples is not required when there is no process flow at the monitor.ACTION 33- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases Via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. | ||
NOTE: Collection of grab samples is not required when there is no process flow at the monitor.ACTION 33- With the number of channels OPERABLE less than required by the | Pump performance curves generated in place may be used to estimate flow.CPSES -UNITS 1 AND 2- ODCM PART 13/4-5 Rev. 33 TABLE 4.3-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAL CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluent Line (XRE-5253) | ||
Pump performance curves generated in place may be used | D P R(4) N.A. Q(1)b. Turbine Building (Floor Drains) Sumps Effluent Lines (1 RE-5100 & 2RE-51 00) D M R(4) N.A. Q(2)c. Auxiliary Building to LVW Pond Liquid Effluent Line (XRE-5251 A) D M R(4) N.A. Q(2)2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a. Service Water System Effluent Lines (1RE-4269, IRE-4270, 2RE-4269 &2RE-4270) | ||
D P R(4) N.A. Q(1)b. Turbine Building (Floor Drains) | D M R(4) N.A. Q(3)3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line (XFT-5288) | ||
&2RE-4270) | D(5) N.A. R Q N.A.CPSES -UNITS I AND 2- ODCM PART I13/4-6 Rev. 33 TABLE 4.3-3 (Continued) | ||
D M R(4) N.A. Q(3)3. Flow Rate Measurement | 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, or Check Source Failure).(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the Alarm Setpoint; or b. Circuit failure (Channel Out of Service -Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).(4) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.(5) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made.CPSES -UNITS 1 AND 2- ODCM PART I13/4-7 Rev. 33 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.5 In accordance with CPSES TS 5.5.4.a, 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. | ||
D(5) N.A. R Q N.A.CPSES -UNITS I AND 2- | The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part II of the ODCM.APPLICABILITY: | ||
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 | 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 inoperable, or change the setpoint so it is acceptably conservative. | ||
(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic flow diversion of this pathway (from the Low Volume Waste Treatment System to | : b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8.Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.SURVEILLANCE REQUIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.CPSES -UNITS 1 AND 2- ODCM PART I13/4-8 Rev. 33 TABLE 3.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT' OPERABLE APPLICABILITY ACTION 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Release Rate Monitor -Providing Alarm and Automatic Termination of Release[XRE-5570A | ||
(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that | |||
(4) The initial CHANNEL CALIBRATION shall be performed using one or more of | |||
The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with | |||
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 | |||
: b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels | |||
& XRE-5570B (effluent release rate channel)] | & XRE-5570B (effluent release rate channel)] | ||
1/stack ** | 1/stack ** 34 2. PRIMARY PLANT VENTILATION | ||
: a. Noble Gas Release Rate Monitor[XRE-5570A | : a. Noble Gas Release Rate Monitor[XRE-5570A | ||
& XRE-5570B (effluent release rate channel)] | & XRE-5570B (effluent release rate channel)] | ||
1/stack | 1/stack 36 b. Iodine Sampler (WRGM sample skid) 1/stack 37 c. Particulate Sampler (WRGM sample skid) 1/stack 37 d. Sampler Flow Rate Monitor SMPL Flow I (X-RFT-5570A-1, X-RFT-5570B-1) 1/stack 35 CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-9 Rev. 33 TABLE 3.3-8 (Continued) | ||
TABLE NOTATIONS | TABLE NOTATIONS* At all times.** During Batch Radioactive Releases via this pathway.ACTION 34-ACTION 35-ACTION 36-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: a. The auxiliary building vent duct monitor (XRE-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.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is estimated at least once per 4 hours.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-5570B (low range activity) or XRE-5567A, XRE-5567B) is OPERABLE, and the plant vent flow rate is estimated at least once per 4 hours; or b. The Plant Vent Flow Monitor, PROC FLOW N (X-FT-5570A-1, X-FT-5570B-1), is OPERABLE, and an alternate Plant Vent Noble Gas Activity Monitor is OPERABLE (XRE-5567A, XRE-5567B) or grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours; or c. The plant vent flow rate is estimated at least once per 4 hours, and grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours; or d. if the number of channels OPERABLE is less than required by the"Minimum Channels OPERABLE" requirement due to loss of sample line, effluent releases via this pathway may continue for no more than 7 days, provided monitors on the other stack are OPERABLE and actions are initiated in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical. | ||
* At all times.** During Batch Radioactive Releases via this pathway.ACTION 34-ACTION 35-ACTION 36-With the number of channels OPERABLE less than required by the | CPSES- UNITS 1 AND 2- ODCM PART I13/4-10 Rev. 33 TABLE 3.3-8 (Continued) | ||
is OPERABLE, and an alternate Plant Vent Noble | TABLE NOTATIONS 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 that: a. samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2, or b. if the number of channels OPERABLE is less than required by the'minimum Channels OPERABLE" requirement due to loss of heat tracing, then declare the Iodine & Particulate samplers INOPERABLE. | ||
CPSES- UNITS 1 AND 2- | Restore the heat tracing within 7 days and declare the samplers OPERABLE or initiate action in accordance with the Corrective Action Program to restore the channel(s) to OPERABLE status as soon as practical; or c. if the number of channels OPERABLE is less than required by the"Minimum Channels OPERABLE" requirement due to loss of sample line, effluent releases via the affected pathway may continue for no more than 7 days, provided monitors on the other stack are OPERABLE and actions are initiated in accordance with the Corrective Action Program to restore the channel(s) to OPERABLE status as soon as practical. | ||
TABLE NOTATIONS ACTION 37- With the number of channels OPERABLE less than required by the | CPSES -UNITS 1 AND 2- ODCM P 3 PART I13/4-11 Rev. 33 TABLE 4.3-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL OPERATIONAL TEST DIGITAL CHANNEL OPERATIONAL TEST CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION INSTRUMENT | ||
: 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Release Rate Monitor Providing Alarm and Automatic Termination of Release[XRE-5570A, XRE-5570B (effluent release rate channel)]2. PRIMARY PLANT VENTILATION | |||
CPSES -UNITS 1 AND 2- ODCM P | : a. Noble Gas Release Rate Monitor[XRE-5570A, XRE-5570B (effluent release rate channel)]b. Iodine Sampler (WRGM sample skid)c. Particulate Sampler (WRGM Sample Skid)d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1, X-RFT-5570B-1) | ||
: 1. WASTE GAS HOLDUP | P P R(3)N.A.Q(1)D W(4)W(4)D R(3)N.A.N.A.N.A.N.A.N.A.R N.A.N.A.N.A.Q Q(2)N.A.N.A.N.A.CPSES -UNITS 1 AND 2- ODCM PART I13/4-12 Rev. 33 TABLE 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 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 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).(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.(4) The CHANNEL CHECK shall consist of visually verifying that the collection element (i.e., filter or cartridge. | |||
: a. Noble Gas Release Rate Monitor[XRE-5570A, XRE-5570B (effluent release rate channel)] | etc.) is in place for sampling.CPSES -UNITS 1 AND 2- ODCM PART I13/4-13 Rev. 33 INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE.APPLICABILITY: | ||
At all times.ACTION: a. With less than the minimum number of meteorological monitoring instrumentation channels OPERABLE for more than 7 days, initiate action in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical. | |||
SURVEILLANCE REQUIREMENTS 4.3.3.6 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE: a. At least once per 24 hours by performance of a CHANNEL CHECK; and b. At least once per 184 days by performance of a CHANNEL CALIBRATION except the wind speed and wind direction sensors which are replaced with calibrated sensors at least once per 12 months.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-14 Rev. 33 TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT CHANNEL 1. WIND SPEED a. X-S-4117 b. X-S-4118 c. X-S-4128*2. WIND DIRECTION a. X-Z-4115 b. X-Z-4116 c. X-Z-4126*3. AIR TEMPERATURE | |||
TABLE NOTATIONS | -AT a. X-T-4119 b. X-T-4120 LOCATION MINIMUM OPERABLE 1 of 3 Nominal Elev. 60 m.Nominal Elev. 10 m.Nominal Elev. 10 m.1 of 3 Nominal Elev. 60 m Nominal Elev. 10 m.Nominal Elev. 10 m.1 of 2 Nominal Elev. 60 m. and Nominal Elev. 10 m.Nominal Elev. 60 m. and Nominal Elev. 10 m.* Mounted on backup tower.CPSES- UNITS 1 AND 2- ODCM PART 1 3/4-15 Rev. 33 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. | ||
# Prior to any release from the WASTE GAS HOLDUP SYSTEM or containment | |||
(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control | |||
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of | |||
etc.) is in place for sampling. | |||
CPSES -UNITS 1 AND 2- | |||
APPLICABILITY: | APPLICABILITY: | ||
At all times.ACTION: With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either: 1. Decontaminate and repair the sealed source; or 2. Dispose of the sealed source in accordance with Commission Regulations. | |||
At all times.ACTION:With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:1. Decontaminate and repair the sealed source; | |||
SURVEILLANCE REQUIREMENTS 4.7.15.1 Test Requirements | SURVEILLANCE REQUIREMENTS 4.7.15.1 Test Requirements | ||
-Each sealed source shall be tested for leakage and/ | -Each sealed source shall be tested for leakage and/or contamination by: a. The licensee; or b. Other persons specifically authorized by the Commission or an Agreement State.The test method shall have a detection sensitivity of at least 0.005 microCurie per test sample.4.7.15.2 Test Frequencies | ||
-Each category of sealed sources (excluding startup sources | -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), | : 1) With a half-life greater than 30 days (excluding Hydrogen 3), and 2) In any form other than gas.b. Stored sources not in use -Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-16 Rev. 33 SURVEILLANCE REQUIREMENTS (Continued) | ||
: c. Startup sources and fission detectors | : c. Startup sources and fission detectors | ||
-Each sealed startup source and | -Each sealed startup source and fission detector shall be tested prior to installation or within 31 days prior to being subjected to core flux and following repair or maintenance to the source.4.7.15.3 Reports- A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microCurie of removable contamination. | ||
CPSES -UNITS 1 AND 2 - | CPSES -UNITS 1 AND 2 -ODCM PART I13/4-17 Rev. 33 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with CPSES TS 5.5.4.b and 5.5.4.c the concentration of radioactive material released in liquid effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microCurie/ml total activity.APPLICABILITY: | ||
APPLICABILITY: | At all times.ACTION: a. With the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Part II of the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.CPSES -UNITS 1 AND 2- ODCM PART I13/4-18 Rev. 33 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION0 1)TYPE FREQUENCY FREQUENCY ANALYSIS (p.Ci/ml)1A. Batch Waste Release (2) P P Principal Gamma 5.OE-07 Tanks to the Circulating Each Batch Each Batch Emitters (3)Water Discharge 1-131 1.OE-06 a. Waste Monitor Tanks Dissolved | ||
At all times.ACTION:a. With the concentration of radioactive material released in liquid effluents | & Ete1.E-05 b. Laundry Holdup& Gases (Gamma Emitters)Monitor Tanks M H-3 1.0E-05 c. Waste Water Composite (4) Gross Alpha 1.0E-07 Holdup Tanks (8) Q Sr-89, Sr-90 5.OE-08 d. Plant Effluent Composite (4) Fe-55 1.0E-06 Tanks lB. Batch Waste Release (2) P P Principal Gamma 5.OE-07 Tanks to the Waste Water Each Batch Each Batch Emitters (3)Management System a. Condensate Polisher 1-131 1.OE-06 Backwash Recovery Tanks (6,7)b. Waste Water H-3 1.OE-05 Holdup Tanks (6,8)c. Temporary holdup tanks (10)2A. Continuous Release(5) to Monthly Monthly Dissolved | ||
CPSES -UNITS 1 AND 2- | & Entrained (3) (11)the Circulating Water Grab (11) Grab (11) Gases (Gamma Emitters)Discharge Daily Grab Composite over Principal Gamma 5.0E.07(11) | ||
& Ete1.E-05 | : a. Low Volume Sample (9) pond discharge Emitters (3)Waste Pond plriod (43 Effluents period (4) 1-131 1.0E-06 H-3 1.OE-05 Gross Alpha 1.OE-07 Q Sr-89, Sr-90. 5.OE-08 Composite (4) Fe-55 1.OE-06 2B. Continuous Releases (5)to W W Principal Gamma 5.OE-07 the Waste Water Grab Sample Emitters (3)Management System a. Turbine Bldg.Sump No. 2 1-131 1.OE-.06 Effluents (6,7)b. Turbine Bldg.Sump No. 4 Effluents (6,7) H-3 1.OE-05 c. Auxiliary Bldg.Secondary Effluents (6,7)CPSES- UNITS 1 AND 2- ODCM PART I13/4-19 Rev. 33 TABLE 4.11-1 (Continued) | ||
TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation: | |||
Monitor Tanks M H-3 1.0E- | LLD = 4"66Sb E*V°2.22x 106 e Y | ||
& Entrained (3) (11)the Circulating Water Grab (11) Grab (11) Gases (Gamma Emitters) | * exp (-XAt)Where: LLD = "A priori" lower limit of detection (microCurie per unit mass or volume), sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = Counting efficiency (counts per disintegration), V = Sample size (units of mass or volume), 2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, X = Radioactive decay constant for the particular radionuclide (sec-1), and At = Elapsed time between the midpoint of sample collection and the time of counting(s). | ||
Discharge Daily Grab Composite over Principal Gamma 5.0E.07(11) | |||
: a. Low Volume Sample (9) pond discharge Emitters (3)Waste Pond plriod ( | |||
TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration | |||
LLD = 4" | |||
* exp (-XAt)Where:LLD = "A priori" lower limit of detection (microCurie per unit mass or volume),sb = Standard deviation of the background counting rate or of the counting rate | |||
V = Sample size (units of mass or volume),2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, X = Radioactive decay constant for the particular radionuclide (sec-1), | |||
Typical values of E, V, Y, and At should be used in the calculation. | Typical values of E, V, Y, and At should be used in the calculation. | ||
It should be recognized that the LLD is defined as an a priori (before the fact) | 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. | ||
(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to | (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in Part II of the ODCM to assure representative sampling.(3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: | ||
(3) The principal gamma emitters for which the LLD specification applies include | Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141 for fission and corrosion products, and Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-138 for dissolved or entrained gases. Ce-144 shall also be measured, but with an LLD of 5 x 10-6. This list does not mean that only these nuclides are to be considered. | ||
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, | Other gamma peaks that are identifiable, together with those of the above nuclides, shall CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-20 Rev. 33 TABLE 4.11-1 (Continued) | ||
TABLE NOTATIONS (Continued) also be analyzed and reported in the 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 representative of the liquids released.(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.(6) These waste streams shall be sampled and analyzed, in accordance with this table, if radioactive material is detected in the LVW Pond composite samples in concentrations that exceed 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2. This sampling shall continue until 2 consecutive samples from the waste stream show that the concentration of radioactive materials in the waste stream is less than or equal to 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2.(7) All flow from these waste streams shall be diverted to the Waste Water Holdup Tanks if activity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Sampling and analysis of the respective Tanks or sumps are not required when flow is diverted to the Waste Water Holdup Tanks.(8) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Otherwise, WWHTs may be discharged to the Low Volume Waste Pond. WWHT discharges to the Circulating Water Discharge Tunnel shall be sampled and analyzed per Item 1A.c of this table. WWHT discharges to the LVW Pond shall be sampled and analyzed per Item 1 B.b of this table.(9) Samples shall be taken at least once per 24 hours while the release is occurring. | |||
Other gamma peaks that are identifiable, together with those of the above nuclides, | To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.(10) Temporary holdup tanks used to support special plant activities (e.g., Steam Generator Secondary Cleaning) involving potentially radioactive systems may be transferred to the Waste Water Management System when sampled in accordance with this table and the special plant activity has been evaluated in accordance with the 50.59 process. This waste stream shall not be discharged to the Waste Water Management System if activity is present in the waste stream in concentrations that exceed 10 times the limits of 10CFR20, Appendix B, Table 2, Column 2.(11) Dissolved and entrained gases should be included in the analysis (including Kr-87, Kr-88, Xe-133, Xe-1 33m, Xe-1 35, and Xe-138). There are no LLD requirements for these gases in the LVW samples since the half life of the isotopes are relatively short with respect to the sample counting frequency. | ||
TABLE NOTATIONS (Continued) also be analyzed and reported in the Radioactive Effluent Release Report pursuant | Gases are also not expected to be found in the LVW due CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-21 Rev. 33 TABLE 4.11-1 (Continued) | ||
(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., | TABLE NOTATIONS (Continued) to delay times associated with water being transported to the LVW and the open exposure of the ponds which would aid in the degasification of the liquids. One sample should be obtained monthly from the Low Volume Waste in addition to the composite sample to analyze for these noble gases. The count time for the sample should be equal to the time required to establish LLD values for the noble gas isotopes (e.g., 2000 seconds or the same count time used for effluent liquid batch releases). | ||
To | CPSES -UNITS 1 AND 2- ODCM PART I13/4-22 Rev. 33 RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with CPSES TS 5.5.4.d and 5.5.4.e the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ; and b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.APPLICABILITY: | ||
At all times.ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit a report to the Commission within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This 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.SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative-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 Part II of the ODCM at least once per 31 days.CPSES -.UNITS 1 AND 2- ODCM PART 1 3/4-23 Rev. 33 RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with CPSES TS 5.5.4.f, the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to CONTROLLED AREAS and 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: | |||
There are no LLD requirements for these | 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 a report to the Commission within 30 days, pursuant to 10 CFR 50, Appendix I, that includes the following information: | ||
Gases are also not expected to be found in the LVW | : 1) Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3) Summary description of action(s) taken to prevent a recurrence. | ||
TABLE NOTATIONS (Continued) to delay times associated with water being transported to the LVW and the | SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to CONTROLLED AREAS and UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.CPSES -UNITS 1 AND 2- ODCM PART I13/4-24 Rev. 33 RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY CONTROLS 3.11.1.4 The quantity of radioactive material contained in resins transferred to the LVW Pond shall be limited by the following expression: | ||
One | 264 IA<v j c, excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life, where: Aj = Pond inventory limit for single radionuclide "j" (Curies), Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j" (microCuries/ml), V = Volume of resins in the pond (gallons), and 264 = Unit conversion factor (microCuries/Curie per millilitertgallon). | ||
CPSES -UNITS 1 AND 2- | |||
At all times.ACTION:a. With the calculated dose from the release of radioactive materials in | |||
(1) the results of radiological analyses of | |||
At all times.ACTION:a. With radioactive liquid waste being discharged without treatment and in excess | |||
: 1) Explanation of why liquid radwaste was being discharged | |||
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to CONTROLLED AREAS | |||
4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE | |||
CPSES -UNITS 1 AND 2- | |||
264 IA<v j c,excluding | |||
Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for | |||
V = Volume of resins in the pond (gallons), | |||
APPLICABILITY: | APPLICABILITY: | ||
At all times.ACTION:a. With the quantity of radioactive material contained in resins in the LVW | At all times.ACTION: a. With the quantity of radioactive material contained in resins in the LVW Pond exceeding the above limit, immediately suspend all additions of resins to the pond.SURVEILLANCE REQUIREMENTS 4.11.1.4 Prior to transferring any batch of used powdex resin to the pond, the total inventory of radioactive materials in resins contained in the pond, including the batch to be transferred, shall be determined to be within the above limit. The inventory shall be determined based on analysis of a representative sample of the resin batch. Decay of radionuclides in previously discharged resins may be taken into account in determining inventory levels.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-25 Rev. 33 RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY SURVEILLANCE REQUIREMENTS (Continued) | ||
Additionally, each batch of resins transferred to the pond shall be limited by the expression: | Additionally, each batch of resins transferred to the pond shall be limited by the expression: | ||
7. | 7.J Qj-where: Qj Concentration of radioactive materials (microCuries/ml) in wet, drained slurry (used powdex resin) for radionuclide "j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life. | ||
The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-60.Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent quarterly composite analysis, Cj= 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j" (microCuries/milliliter). | |||
CPSES -UNITS 1 AND 2- ODCM PART I13/4-26 Rev. 33 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE 3.11.2.1 In accordance with CPSES TS 5.5.4.c and 5.5.4.g, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following: | |||
: a. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin; and b. For Iodine-1 31, for Iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/yr to any organ.APPLICABILITY: | |||
CPSES -UNITS 1 AND 2- | At all times.ACTION: a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limits(s). | ||
: a. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the | SURVEILLANCE REQUIREMENTS 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-2.4.11.2.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Part II of the ODCM to assure that the dose rates at or beyond the SITE BOUNDARY are maintained within the limits of Control 3.11.2.1.CPSES -UNITS 1 AND 2- ODCM PART I13/4-27 Rev. 33 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM SAMPLING ANALYSIS TYPE OF FREQUENCY FREQUENCY ACTIVITY ANALYSIS LOWER LIMIT OF DETECTION (LLD) (1)(pCif/ml)GASEOUS RELEASE TYPE 1 Waste Gas Storage P P Tank Each Tank Each Tank Grab Sample Principal Gamma Emitters(2) lx10"4 2. Containment Purge P P or Vent Each Release(3) | ||
At all times.ACTION:a. With the dose rate(s) exceeding the above limits, immediately restore the | |||
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed according to | |||
CPSES -UNITS 1 AND 2- | |||
GASEOUS RELEASE | |||
Each Release(3) | Each Release(3) | ||
Principal Gamma Emitters(2) lx10-Grab Sample M H-3 (oxide) 1x10- | Principal Gamma Emitters(2) lx10-Grab Sample M H-3 (oxide) 1x10-6 3. Plant Vent M(3), (4), (5) M(3) Principal Gamma Emitters(2) 1x10-4 Grab Sample H-3 (oxide) 1x10-6 Continuous(6) | ||
W(7)Radioiodine Adsorber 1-131 lx10- | W(7)Radioiodine Adsorber 1-131 lx10-1 2 Continuous(6) | ||
W(7)Particulate Sample Principal Gamma Emitters(2) lx10- | W(7)Particulate Sample Principal Gamma Emitters(2) lx10-1 1 Continuous(6) | ||
M Composite Par-ticulate Sample Gross Alpha 1x10-1 1 Continuous(6) | |||
Q Composite Par-ticulate Sample Sr-89, Sr-90 1x10-1 1 Continuous(6) | |||
Noble Gas **Beta or Gamma Noble Gas | Noble Gas **Beta or Gamma Noble Gas lxlO 6 Outside Buildings Grab sample W(8) Principle Gamma Emitters(2) lx10-11* Table notations next page**This sample is continuously analyzed by a radiation monitor CPSES- UNITS 1 AND 2- ODCM PART 1 3/4-28 Rev. 33 TABLE 4.11-2 (Continued) | ||
TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration | TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation: | ||
LLD = 4. | LLD = 4.66sb 6 E*V.°2.22x106 .Yexp(-XAt) | ||
.Yexp(-XAt) | Where: LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume), sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = Counting efficiency (counts per disintegration), V = Sample size (units of mass or volume), 2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, XL = Radioactive decay constant for the particular radionuclide (sec" 1), and At = Elapsed time between the midpoint of sample collection and the time of counting(s). | ||
Where:LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),sb = Standard deviation of the background counting rate or of the counting rate | |||
V = Sample size (units of mass or volume),2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, XL = Radioactive decay constant for the particular radionuclide (sec"1), | |||
Typical values of E, V, Y, and At should be used in the calculation. | Typical values of E, V, Y, and At should be used in the calculation. | ||
It should be recognized that the LLD is defined as an a priori (before the fact) | 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. | ||
(2) The principal gamma emitters for which the LLD specification applies include | (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: | ||
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in | Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, 1-131, Cs-1 34, Cs-1 37, Ce-141 and Ce-144 in iodine and particulate releases. | ||
This list does not mean that only | This list does not mean that only these nuclides are to be considered. | ||
In the case of release type 4, Outside Buildings, | In the case of release type 4, Outside Buildings, noble gases and iodine may not be sampled based on an evaluation of the source term. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the 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.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-29 Rev. 33 TABLE 4.11-2 (Continued) | ||
TABLE NOTATIONS (Continued) | TABLE NOTATIONS (Continued) | ||
(3) Sampling and analysis shall also be performed following | (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change _> 15% of RATED THERMAL POWER within a 1-hour period.This requirement does not apply if: (1) analysis of primary coolant activity performed pursuant to Technical Specification 3.4.16 shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3, and (2)noble gas monitoring shows that effluent activity has not increased more than a factor of 3.(4) Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded.(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from the sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change _> 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours of changing. | ||
When samples collected for 24 hours 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 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) noble gas monitoring shows that effluent activity has not increased more than a factor of 3.(8) Samples shall be changed at least once per seven (7) days and analysis shall be completed within 48 hours after changing, or after removal from the sampler. This requirement does not apply, if no activities are being conducted in the Outside Building that would generate radioactive effluent.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-30 Rev. 33 RADIOACTIVE EFFLUENTS DOSE -NOBLE GASES CONTROLS 3.11.2.2 In accordance with CPSES TS 5.5.4.e and 5.5.4.h, the air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following: | |||
(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from the sampler. | : a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation. | ||
Sampling shall also | |||
When | |||
CPSES -UNITS 1 AND 2- | |||
: 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; | |||
APPLICABILITY: | APPLICABILITY: | ||
At all times.ACTION:a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a report to the NRC | At all times.ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, 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.SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.CPSES -UNITS 1 AND 2 -ODCM PART 1 3/4-31 Rev. 33 RADIOACTIVE EFFLUENTS DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with CPSES TS 5.5.4.e and 5.5.4.i, the dose to a MEMBER OF THE PUBLIC from lodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following: | ||
: a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ; and b. During any calendar year: Less than or equal to 15 mrems to any organ.APPLICABILITY: | |||
At all times.ACTION: a. With the calculated dose from the release of Iodine-1 31, Iodine-1 33, 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 a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance with the above limits.SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-1 31, Iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.CPSES -UNITS 1 AND 2- ODCM PART I13/4-32 Rev. 33 RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with CPSES TS 5.5.4.f, the PRIMARY PLANT VENTILATION SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed: a. 0.2 mrad to air from gamma radiation, or b. 0.4 mrad to air from beta radiation, or c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.APPLICABILITY: | |||
At all times.ACTION: a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that includes the following information: | |||
: a. During any calendar quarter: | : 1) Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3) Summary description of action(s) taken to prevent a recurrence. | ||
Less than or equal to 7.5 mrems to any organ; | SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.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.CPSES -UNITS 1 AND 2- ODCM PART I13/4-33 Rev. 33 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with CPSES TS 5.5.4.j, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.APPLICABILITY: | ||
At all times.ACTION:a. With the calculated dose from the release of Iodine-1 31, Iodine-1 33, tritium, | At all times.ACTION: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 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, the Independent Spent Fuel Storage Installation (ISFSI), 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 a report to the NRC within 30 days, pursuant to 10 CFR 20.1301(d) and 10 CFR 20.2203(a)(4) 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 report, as defined in 10 CFR 20.2203(b), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. | |||
At all times.ACTION:a. With radioactive gaseous waste being discharged without treatment and in | 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 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.SURVEILLANCE REQUIREMENTS 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 Part II of the ODCM.4.11.4.2 Cumulative dose contributions from direct radiation from the units, the ISFSI, and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Part II of the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4.CPSES -UNITS 1 AND 2- ODCM PART I13/4-34 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.APPLICABILITY: | ||
: 1) Identification of any inoperable equipment or subsystems, and the | 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 NRC, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3, a description of the reason(s) for not conducting the program as required and the 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 a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. | |||
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the | When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) + concentration (2) +... >1.0 reporting level (1) reporting level (2)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. | ||
4.11.2.4.2 The installed PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS | This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3.The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.CPSES- UNITS 1 AND 2- ODCM PART I13/4-35 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued) | ||
CPSES -UNITS 1 AND 2- | : 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 days to the Radiological Environmental Monitoring Program. The specific locations from which samples were unavailable may then be deleted from the monitoring program. New sampling locations shall be listed in the results of the annual Land Use Census.SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1. The specific sample locations for the Radiological Environmental Monitoring Program shall be listed and maintained current in the results of the annual Land Use Census.CPSES -UNITS 1 AND 2- ODCM PART I13/4-36 Rev. 33 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS0) | ||
At all times.ACTION:a. With the calculated doses from the release of radioactive materials in liquid | EXPOSURE PATHWAY AND/OR SAMPLE SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 1. Direct Radiation(2) | ||
3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a., | Forty routine monitoring stations either with Quarterly two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY;An outer ring of stations, onein each meteorological sector in the 6- to 8-km range from the site; and Gamma dose quarterly 2. Airborne Radioiodine and Particulates The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.Samples from five locations: | ||
or 3.11.2.3b., | Three samples from close to the three SITE BOUNDARY locations, in different sectors, of the highest calculated annual average ground-level D/Q;Continuous sampler operation Radioiodine Canister: with sample collection weekly, 1-131 analysis weekly or more frequently if required by dust loading.Particulate Sampler: Gross beta radioactivity analysis following filter change;(4) and gamma isotopic analysis(5) of composite (by location quarterly). | ||
calculations shall be | CPSES- UNITS 1 AND 2- ODCM PART I13/4-37 Rev. 33 TABLE 3.12-1 (Continued) | ||
and from outside storage tanks to determine | RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS0 1)One sample from the vicinity of a community having the highest calculated annual average ground-level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.(3) | ||
If such is the case,prepare and submit a report to the NRC within 30 days, pursuant to 10 | SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 3. Waterborne | ||
shall include an analysis | : a. Surface Squaw Creek Reservoir(6) | ||
Lake Granbury Control-Brazos River upstream of Lake Granbury Samples from two sources if likely to be affected.(8) | |||
If the estimated dose(s)exceeds the above limits, and if the release condition resulting in violation of | Monthly composite of weekly grab samples.Monthly composite of weekly grab samples when Lake Granbury is receiving letdown from SCR. Otherwise, monthly grab sample.(7) | ||
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined | Monthly Quarterly Gamma isotopic analysis(5) monthly.Composite for tritium analysis quarterly. | ||
At all times.ACTION:a. With the Radiological Environmental Monitoring Program not being conducted | Gamma isotopic analysis(5)monthly.Composite for tritium analysis quarterly. | ||
: 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 | Gamma isotopic analysis(5) monthly.Composite for tritium analysis quarterly. | ||
Gamma isotopic(5) and tritium analysis quarterly. | |||
When more than one of the radionuclides | : b. Ground CPSES -UNITS 1 AND 2 -ODCM PART 1 3/4-38 Rev. 33 TABLE 3.12-1 (Continued) | ||
This report | RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1)EXPOSURE PATHWAY AND/OR SAMPLE 3. Waterborne (Continued) | ||
: c. Drinking d. Sediment from Shoreline SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS One sample from Squaw Creek Reservoir. | |||
: c. With milk or fresh leafy vegetable samples unavailable from one or more of | One sample from downstream area with existing or potential recreational value.Composite of weekly grab samples over 2-week period when 1-131 analysis is performed; monthly composite of weekly grab samples otherwise. | ||
The specific locations from which | |||
EXPOSURE | |||
Forty routine monitoring stations either with Quarterly two or more dosimeters or with one instrument for measuring and recording dose | |||
Samples from five locations: | |||
Three samples from close to the three | |||
with sample collection weekly, 1-131 analysis | |||
CPSES- UNITS 1 AND 2- | |||
RADIOLOGICAL ENVIRONMENTAL MONITORING | |||
SAMPLING | |||
: a. | |||
Lake | |||
Monthly composite of | |||
Gamma isotopic analysis( | |||
5)monthly.Composite for tritium | |||
Gamma isotopic analysis(5) monthly.Composite for tritium | |||
Gamma isotopic(5) and | |||
: b. | |||
RADIOLOGICAL ENVIRONMENTAL MONITORING | |||
1)EXPOSURE | |||
: c. | |||
One sample from downstream area | |||
Semiannually. | Semiannually. | ||
1-131 analysis of each composite sample when the dose calculated for the consumption of the | 1-131 analysis of each composite sample when the dose calculated for the consumption of the water is greater than 1 mrem per year(9). Gross beta and gamma isotopic analyses(5) monthly.Composite for tritium analysis quarterly. | ||
Gamma isotopic analysis(5) semiannually. | Gamma isotopic analysis(5) semiannually. | ||
: 4. Ingestion | : 4. Ingestion a. Milk Samples from milking animals in three locations within 5 km distance having the highest dose potential. | ||
If there are none, sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.(9) One sample from milking animals at a control location, 15 to 30 km distant and in the least prevalent wind direction.(3)Semimonthly when animals are Gamma isotopic(5) and 1-131 on pasture; monthly at other analysis semimonthly when times. animals are on pasture; monthly at other times.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-39 Rev. 33 TABLE 3.12-1 (Continued) | |||
If there | RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS0 1)EXPOSURE PATHWAY AND/OR SAMPLE 4. Ingestion (Continued) | ||
3)Semimonthly when animals are Gamma isotopic(5) and 1- | : b. Fish and Invertebrates SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS One sample of at least two recreationally Sample semiannually. | ||
RADIOLOGICAL ENVIRONMENTAL MONITORING | important species in vicinity of plant discharge area.One sample of same species in areas not influenced by plant discharge. | ||
: b. Fish | Gamma isotopic analysis(5) on edible portions semiannually | ||
important species in vicinity of plant discharge area.One sample of same species in areas | : c. Food Products*One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged. | ||
Gamma isotopic analysis( | |||
: c. Food Products* | |||
One sample of each principal class of | |||
At time of harvest(1 0)A sample of broad leaf vegetation grown Monthly, when available. | At time of harvest(1 0)A sample of broad leaf vegetation grown Monthly, when available. | ||
nearest each of two different offsite locations | nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed at all required locations. | ||
One sample of each of the similar broad leaf Monthly, when available. | One sample of each of the similar broad leaf Monthly, when available. | ||
vegetation grown 15 to 30 km distant in | vegetation grown 15 to 30 km distant in the least prevalent wind direction(3) if milk sampling is not performed at all required locations. | ||
Gamma isotopic analysis( | Gamma isotopic analysis(5)on edible portion following sample collection. | ||
5) | Gamma isotopic(5) and 1-131 analyses, monthly, when samples are collected Gamma isotopic(5) and 1-131 analyses, monthly, when samples are collected Reports from 3 additional airborne radioiodine sample locations may be supplemented for broad leaf vegetation samples.CPSES- UNITS 1 AND 2- ODCM PARTI13/440 Rev. 33 TABLE 3.12-1 (Continued) | ||
Gamma isotopic(5) and 1- | TABLE NOTATIONS (1) For each sample location required by Table 3.12-1, specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided in information maintained current in the results of the annual Land Use Census. 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.New sampling locations shall be listed in the results of the annual Land Use Census.(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 dosimeter is considered to be one phosphor or aluminum oxide chip (detector) or; two or more phosphors or aluminum oxide chips (detectors) in a packet are considered as two or more dosimeters. | |||
Film badges shall not be used as dosimeters for measuring direct radiation. | |||
TABLE NOTATIONS (1) For each sample location required by Table 3.12-1, specific parameters of distance | |||
If specimens | |||
It is recognized that, at times, it may not | |||
For the purposes of this table, a dosimeter is considered to be one | |||
Film badges shall | |||
(3) The purpose of this sample is to obtain background information. | (3) The purpose of this sample is to obtain background information. | ||
If it is not practical | 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. | ||
The control sample location at 12.3 miles in the southwest sector has been evaluated and found to be an acceptable substitute sampling location.(4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours 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.(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. | |||
The control | (7) Lake Granbury shall be sampled near the letdown discharge and at a distance beyond significant influence of the discharge. | ||
(4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 | (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. | ||
(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 | CPSES- UNITS 1 AND 2- ODCM PARTI13/441 Rev. 33 TABLE 3.12-1 (Continued) | ||
(7) Lake Granbury shall be sampled near the letdown discharge and at a distance | |||
(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 | |||
CPSES- UNITS 1 AND 2- | |||
TABLE NOTATIONS (Continued) | TABLE NOTATIONS (Continued) | ||
(9) The dose shall be calculated for the maximum organ and age group, using | (9) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in Part II of the ODCM.(10) If harvest occurs more than once a year, sampling shall be performed 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.CPSES- UNITS 1 AND 2- 0DCM PART 1 3/4-42 Rev. 33 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS ANALYSIS (pCi/1) (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet)H-3 20,000*Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-1 37 50 20 2,000 70 2,000 Ba-La-140 200 300 (*) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.(**) If no drinking water pathway exists, a value of 20 pCi/I may be used.CPSES -UNITS 1 AND 2 -ODCM PARTI13/443 Rev. 33 TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lower Limit of Detection (LLD)(3)AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/1) (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry)Gross Beta 4 0.01 H-3 2000*Mn-54 15 130 Fe-59 30 260 Co -58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15* If no drinking water pathway exists, a value of 3000 pCi/I may be used.** If no drinking water pathway exists, a value of 15 pCi/I may be used.CPSES- UNITS 1 AND 2- ODCM PART I13/4-44 Rev. 33 TABLE 4.12-1 (Continued) | ||
If harvest occurs continuously, sampling shall be monthly. | |||
Attention shall be paid to including samples of tuberous and root food products. | |||
CPSES- UNITS 1 AND 2- | |||
This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.(**) If no drinking water pathway exists, a value of 20 pCi/I may be used.CPSES -UNITS 1 AND 2 - | |||
TABLE NOTATIONS (1) The list does not mean that only these nuclides are to be considered. | TABLE NOTATIONS (1) The list does not mean that only these nuclides are to be considered. | ||
Other peaks | 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 TLD (Thermoluminescent Dosimeter) | ||
Badge used | Badge used for environmental measurements shall be in accordance with the recommendations of 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 a 5% probability of falsely concluding that a blank observation represents a "real" signal.LLD = 4"66Sb E V e Y | ||
* exp (-XAt) 2. | * exp (-XAt) 2.22 Where: LLD the "a priori" lower limit of detection (picoCurie per unit mass or volume), sb Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E Counting efficiency (counts per disintegration), V = Sample size (units of mass or volume), 2.22 = Number of disintegrations per minute per picoCurie, Y = Fractional radiochemical yield, when applicable,? = Radioactive decay constant for the particular radionuclide (sec-1), and At = Elapsed time between the midpoint of sample collection and the time of counting(s). | ||
V = Sample size (units of mass or volume),2.22 = Number of disintegrations per minute per picoCurie, Y = Fractional radiochemical yield, when applicable, | |||
? = Radioactive decay constant for the particular radionuclide (sec-1), | |||
Typical values of E, V, Y, and At should be used in the calculation. | Typical values of E, V, Y, and At should be used in the calculation. | ||
It should be recognized that the LLD is defined as an a orion (before the fact) | It should be recognized that the LLD is defined as an a orion (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. | ||
Analyses shall be performed in such a | 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 | 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.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-45 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 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 50m 2 (500 ft 2) producing broad leaf vegetation. | |||
In | |||
APPLICABILITY: | APPLICABILITY: | ||
At all times.ACTION:a. With a Land Use Census identifying a location(s) that yields a calculated dose | 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 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) within 30 days, to the Radiological Environmental Monitoring Program. The sampling locations having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. | ||
The sampling locations having the | New sampling locations shall be listed in the results of the annual Land Use Census.SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. | ||
via the same exposure | The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1, Item 4.c. shall be followed, including analysis of control samples.CPSES -UNITS I AND 2- ODCM PART 13/4-46 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by Table 3.12-1.APPLICABILITY: | ||
At all times.ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in Part II of 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.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-47 Rev. 33 BASES CPSES -UNITS I AND 2- ODCM PART I B 3/4-0 Rev. 31 INSTRUMENTATION BASES 3/4.3.3.4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. | |||
New sampling locations shall be listed in | The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II of the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 1 OCFR50.3/4.3.3.5 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. | ||
The results of the Land | The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II of the ODCM to ensure that the alarm/trip will occur prior to exceeding the dose rate limits of Control 3.11.2.1. | ||
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.3/4.3.3.6 METEOROLOGICAL MONITORING 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. | |||
At all times.ACTION:a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in Part II of the ODCM. | This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of the second proposed Revision 1 to Regulatory Guide 1.23, "Onsite Meteorological Programs," April 1986.The surveillance requirements of the meteorological instrumentation are consistent with the recommendations of the second proposed Revision 1 to Reg. Guide 1.23 except for the calibration requirements for the Wind Speed and Wind Direction sensors which are replaced with calibrated sensors at least once per each 12 months. The calibration interval starts when the sensor is installed provided the sensor has been vendor calibrated within two years, and the sensor has been in proper storage up to the time of installation. | ||
The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted | These controls have been shown to meet the accuracy and data recovery recommendations of the above reference version of Reg. Guide 1.23.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-1 Rev. 31 INSTRUMENTATION BASES 3/4.7.15 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 1 OCFR70.39(c) limits for plutonium. | ||
The Alarm/Trip Setpoints for these instruments shall | 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 mechanism. | ||
The OPERABILITY and use of this instrumentation is consistent with | CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-2 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be less than 10 times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. | ||
This capability is required | It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in CONTROLLED AREAS and UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) restrictions authorized by 10 CFR 20.1301(e). | ||
April 1986.The surveillance requirements of the meteorological instrumentation are consistent with | The concentration limit for the dissolved or entrained noble gases is based upon the assumption that XE-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This control does not affect the requirement to comply with the annual limitation of 10 CFR 20.1301 (a).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-300.3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, III.A and IV.A of 1OCFR50, 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 material in liquid effluents to CONTROLLED AREAS and 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 radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. | ||
These controls have | The dose calculation methodology and parameters in Part II of 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. | ||
This limitation will ensure | The equations specified in Part II of 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 1OCFR50, 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.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-3 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES This control applies to the release of radioactive materials in liquid effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. | ||
CPSES -UNITS 1 AND 2- | The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents. | ||
It provides operational flexibility for releasing liquid effluents | This control applies to the release of radioactive materials in liquid effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.1.4 LVW POND RESIN INVENTORY The inventory limits of the LVW Pond are based on limiting the consequences of an uncontrolled release of the pond resin inventory. | ||
The concentration limit | The expression in Control 3.11.1.4 assumes the pond inventory is uniformly mixed, and that the pond is located in a CONTROLLED AREA as defined in 10 CFR Part 20, and that the concentration limit in Note 4 to Appendix B of 10 CFR Part 20 applies. This expression limits the total quantity of radioactive materials in resins discharged to the LVW Pond to a value such that the average concentration in the resins, calculated over the total volume of resins in the pond, will not exceed the Effluent Concentration Limits specified in 10 CFR 20, Appendix B, Table 2, Column 2. Because Control 3.11.1.1 limits the concentration of liquid effluents from other pathways to the LVW Pond to 10 times the 10 CFR 20 Effluent Concentration values, also limiting the average concentration in resins to the Effluent Concentration values will assure that the average concentration in the pond from all sources, calculated over the total volume of the pond (liquid and resins), will not exceed the limits of Control 3.11.1.1.The batch limits for resins transferred to the LVW Pond assure that radioactive material in the slurry transferred to the Pond are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in Control 4.11.1.4 assures no batch of resins will be transferred to the Pond unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than 10% of the limits established in 10 CFR 20, Appendix B.The batch limit is arbitrarily established at 10% of the 10 CFR 20, Appendix B limits to minimize input of radioactive materials to the LVW Pond consistent with detection limits for the resin analysis. | ||
NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300. | The batch limit also provides assurance that the radioactive material released is within the inventory limitation of Control 3.11.1.4.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-4 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control, in conjunction with Controls 3.11.2.2 and 3.11.2.3, is provided to ensure that the dose at or beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 for MEMBERS OF THE PUBLIC. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year. | ||
3/4.11.1.2 | Because these dose rate limits are applied on an instantaneous basis and because of the overriding 10 CFR 50, Appendix I, cumulative dose limitations established in Controls 3.11.2.2 and 3.11.2.3, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR 20.1301(a). | ||
Also, for fresh water sites with drinking | For MEMBERS OF THE PUBLIC who may at times be in CONTROLLED AREAS within the SITE BOUNDARY, the occupancy factors for those MEMBERS 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 dose calculation methodology and parameters in Part II of the ODCM implement the requirements in Section III.A of Appendix | The methodology for calculating doses for such MEMBERS OF THE PUBLIC is provided in PART II of the ODCM.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 gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). 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-300.3/4.11.2.2 DOSE -NOBLE GASES This control is provided to implement the requirements of Sections lI.B, III.A and IV.A of 10CFR50, Appendix I. The control implements the guides set forth in Section 1.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 CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by 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 | The dose calculation methodology and parameters established in Part II of the ODCM for calculating the doses due to the actual release rates of the radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-5 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 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. The ODCM equations provided for determining the air doses at or beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. | ||
The requirement that the appropriate portions of this system be used when specified | This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM This control is provided to implement the requirements of Sections II.C, Ill.A, and IV.A of 10CFR50, Appendix I. The Controls are the guides set forth in Section IL.C 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 materials in gaseous effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. | ||
This control implements the requirements of 10 CFR 50.36a, | The calculational methodology and parameters specified in Part II of the ODCM for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion 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. | ||
This control applies to the release of radioactive materials in liquid effluents from each unit at | The release rate specification for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days is dependent upon the existing radionuclide pathways to man in the areas at or beyond the SITE BOUNDARY. | ||
The expression in Control 3.11.1.4 assumes the | The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals 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. The gaseous effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP 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. | ||
This expression limits the total quantity of radioactive materials in resins discharged | The requirement that the appropriate portions of these CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-6 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 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 IL.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. | ||
will not exceed the limits | This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-7 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(e). | ||
The batch limits for resins transferred to the LVW Pond assure that radioactive material in | The control requires the preparation and submittal of a report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the total 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 !, and if direct radiation doses from the units (including outside storage tanks, etc.)are kept small. The 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 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 radius of 8 km must be considered. | ||
The batch limit also provides assurance that the radioactive material released is | If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4) and 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. | ||
CPSES -UNITS 1 AND 2- | 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. | ||
Because these dose rate limits are applied on an instantaneous basis and because of | 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. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-8 Rev. 31 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant and ISFSI operation. | ||
For | This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable 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. | ||
The methodology for calculating doses for such MEMBERS OF THE PUBLIC | 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. | ||
NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300. | Following this period, program changes may be initiated based on operational experience. | ||
3/4.11.2.2 DOSE -NOBLE | 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. | ||
The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides | 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. | ||
The dose calculation methodology and parameters established | Detailed discussion of the LLD, and other detection limits, can be found in Currie, L. A., "Lower Limit of Detection: | ||
Revision 1, | 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 or beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program 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 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden.was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2.3/4.12.3 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 environmental sample matrices are performed as part of the quality CPSES- UNITS 1 AND 2- ODCM PART I B 3/4-9 Rev. 31 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES assurance 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.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-10 Rev. 31 SECTION 5.ODESIGN FEATURES CPSES -UNITS 1 AND 2- ODCM PART I15-0 Rev. 23 5.0 DESIGN FEATURES MAP DEFINING CONTROLLED AREAS, UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which allows identification of structures and release points as well as definition of CONTROLLED AREAS, UNRESTRICTED AREAS and the SITE BOUNDARY are shown in Figure 5.1-3.The UNRESTRICTED AREA, as shown in Figure 5.1-3, is that area beyond the SITE BOUNDARY. | ||
This control applies to the release of radioactive materials in gaseous effluents from each unit | |||
The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance | |||
The calculational methodology and parameters specified in Part II of the ODCM for calculating the doses due to the actual release rates of | |||
Revision 1, July 1977. | |||
The release rate specification for Iodine-131, Iodine-133, | |||
The requirement that the appropriate portions of | |||
This control applies to the release of radioactive materials in gaseous effluents from each unit | |||
The control requires the preparation and submittal | |||
!, and if direct radiation doses from the units (including outside storage tanks, etc.)are kept small. The report will describe a course of action that should result in the limitation | |||
If the dose to any MEMBER OF THE PUBLIC is estimated to exceed | |||
The variance only relates to the limits of 40 CFR Part 190, and does | |||
An individual is not considered a MEMBER OF THE | |||
This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations | |||
Guidance | |||
Following | |||
The required detection capabilities for environmental sample analyses are tabulated in terms | |||
It should be recognized | |||
Detailed discussion of the LLD, and other detection limits, can be found in Currie, L. A., " | |||
Definition and Elaboration of a Proposed Position for Radiological | |||
NUREG/CR-4007 (September 1984), and in the | |||
3/4.12.2 LAND USE | |||
and (2) a vegetation | |||
Access to this area is not limited or controlled by the licensee. | Access to this area is not limited or controlled by the licensee. | ||
This is consistent with the definition of UNRESTRICTED AREA given in 10 CFR 20.1003. | This is consistent with the definition of UNRESTRICTED AREA given in 10 CFR 20.1003. The SITE BOUNDARY coincides with the Exclusion (fenced) Area Boundary, as defined in 10 CFR 100.3(a). | ||
The SITE | For calculations performed pursuant to 10 CFR 50.36a, the concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable. | ||
Area Boundary, as defined in 10 CFR 100.3(a). | The CONTROLLED AREA, as shown in Figure 5.1-3, is that area that is inside the SITE BOUNDARY but is outside of any plant areas defined by the licensee as restricted areas, per the definition of restricted area in 10 CFR 20.1003. Access to the CONTROLLED AREA is limited or controlled by the licensee. | ||
This is consistent With the definition of CONTROLLED AREA given in 10 CFR 20.1003.CPSES -UNITS 1 AND 2- ODCM PART I15-1 Rev. 23 UmPINSTll ARE UNRESTRICTED AREA KEY---- SITE BOUNDARY M McMi STAX MIT MLNAMa PONT.N UWh. MSAA POWT EWTML 201)-The pa.,l wUI t.t.ka as I 2W chows grade. ml. Is 64'below U,.tops of lho Cantabnnwnt OuldIng..FIGURE 5.1-3CONTROLLED AREA, UNRESTRICTED AREA AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS CPSES -UNITS 1 AND 2 -ODCM PART I15-2 Rev. 23 SECTION 6.OADMINISTRATIVE CONTROLS CPSES -UNITS 1 AND 2- ODCM PART 1 6-0 Rev. 31 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*6.9.1.3 A Routine Annual Radiological Environmental Operating Report covering the operation of the units during the previous calendar year shall be submitted prior to May I of each year.The Annual Radiological Environmental Operating Report shall include summaries, interpretations, 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 the environment. | |||
The CONTROLLED AREA, as shown in Figure 5.1-3, is that area that is inside the | The report shall also include the results of the annual Land Use Census required by Control 3.12.2.The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations listed and maintained current in the results of the annual Land Use Census, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.The Annual Radiological Environmental Operating Report shall also include the following: | ||
Access to the CONTROLLED AREA is limited | 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 participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable. | ||
This is consistent With the definition of CONTROLLED AREA given | A single submittal may be made for both units.One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations. | ||
FIGURE 5.1-3CONTROLLED AREA, UNRESTRICTED AREA AND SITE | Maps are included in the results of the annual Land Use Census.CPSES -UNITS 1 AND 2- ODCM PART I16-1 Rev. 31 ADMINISTRATIVE CONTROLS RADIOACTIVE EFFLUENT RELEASE REPORT*6.9.1.4 A routine Radioactive Effluent Release Report covering the operation of the units during the previous year of operation shall be submitted prior to May 1 of each year. The period of the first report shall begin with the date of initial criticality. | ||
The Radioactive Effluent Release Report 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 report shall also include the results of the annual Land Use Census required by | The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** | ||
This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 8, October 1977.A single submittal may be made for both units. The submittal should combine those sections that are common to both units at the station.In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.CPSES -UNITS 1 AND 2- ODCM PART 1 6-2 Rev. 31 ADMINISTRATIVE CONTROLS RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) | |||
The missing data shall be submitted as soon as possible in a supplementary report.The Annual Radiological Environmental Operating Report shall also include the following: | The Radioactive Effluent Release Report shall include a list and description of unplanned releases, from the site to CONTROLLED AREAS and UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.The Radioactive Effluent Release Report shall include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2.The Radioactive Effluent Release Report 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 a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the Technical Specification limits.6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)Changes to the ODCM: a. Shall be documented and records of reviews performed shall be retained as required FSAR Section 17.2.17.1. | |||
A single submittal may be made for both units.One map shall cover stations near the SITE BOUNDARY; a second shall include | 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 20.1302, 40 CFR Part 190, 10 CFR 72.104, 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. | ||
Maps are included in the results of the annual Land | : b. Shall become effective after review and acceptance by the SORC and the approval of the Vice President of Nuclear Operations. | ||
The Radioactive Effluent Release Report 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 | : 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 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. | ||
Revision 1, June 1974, with data summarized on a quarterly basis following | CPSES -UNITS 1 AND 2- ODCM PART 1 6-3 Rev. 31 PART IICALCULATIONAL METHODOLOGIES CPSES -UNITS 1 AND 2- ODCM Rev. 23 SECTION 1.OLIQUID EFFLUENTS The Comanche Peak Steam Electric Station (CPSES) is a 2-unit nuclear generating facility.Each unit is a 1150 MWe, 4-loop, Westinghouse PWR. The units share a common primary liquid radwaste processing system. CPSES is located on Squaw Creek Reservoir (SCR), which serves as the point of supply and discharge for the plant circulating water. Radioactive liquid effluent releases from the primary radwaste processing system are batch type releases, from the Plant Effluent Tanks (PET), Laundry Holdup & Monitor Tanks (LHMT) and Waste Monitor Tanks (WMT), discharged to SCR via the Circulating Water Discharge Tunnel. Potentially radioactive liquid effluent releases from secondary systems include a continuous release from the Turbine Building Sumps (TB Sump), the Unit 1 and Unit 2 Component Cooling Water Drain Tanks (CCWDT), Auxiliary Building Sumps 3 and 11, and the Unit 1 and Unit 2 Diesel Generator Sumps 1, 2, 3 and 4, and batch releases from the Condensate Polisher Backwash Recovery Tanks (CPBWRT). | ||
For solid wastes, the format for Table 3 in Appendix B shall | These secondary pathways from each unit are normally discharged to the common Low Volume Waste (LVW) Pond for chemical treatment. | ||
class of solid wastes (as defined by 10 CFR | The LVW Pond normally discharges to SCR via the circulating Water Discharge Tunnel. Alternatively, secondary waste streams may be routed to the common Waste Water Holdup Tanks (WWHT). The WWHTs may be released on a batch basis to the LVW Pond or to SCR via the Circulating Water Discharge Tunnel, depending on the levels of radioactivity present. Table 4.11-1 of Part I of this document requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Also, releases from the Station Service Water (SSW) System are monitored for radioactivity, although no significant releases of radioactivity are expected from this pathway.Sampling and analysis requirements for all release sources are given in Part I, Table 4.11-1. All batch release sources are isolated and thoroughly mixed by mechanical mixing or recirculating the tank contents, prior to sampling, to assure representative sampling. | ||
The Radioactive Effluent Release Report shall include an annual summary of | The recirculation or mixing times necessary to assure representative sampling shall be specified in station procedures. | ||
or in the form of joint frequency distributions of | A summary of all liquid effluent release sources, volumes, flow rates, and associated radiation monitors is shown in Table 1.1. A flow diagram of all liquid effluent discharge pathways is shown in Figure 1.1.The liquid effluent radiation monitors shown in Figure 1.1 are part of the plant Digital Radiation Monitoring System (DRMS) supplied by Sorrento Electronics (formerly General Atomics). | ||
This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the | Since the DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uCi/ml). The conversion factor for detector output from counts per minute to uCi/ml is determined in the calibration process and input into the database for the monitor microprocessor. | ||
1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL 314.11.1.1 COMPLIANCE To demonstrate compliance with 10 CFR 20.1301, ODCM Radiological Effluent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases, and to 2E-4 uCi/ml for dissolved or entrained noble gases. 10 CFR 20 compliance is checked for all discharges to SCR via the Circulating Water Discharge Tunnel listed in Table 1.1. Because the LVW Pond is located in a CONTROLLED AREA, discharges to the LVW Pond are also checked for 10 CFR 20 compliance. | |||
Historical average meteorological conditions | If radioactive materials are present in the LVW Pond CPSES -UNITS 1 AND 2- ODCM PART 1I11-1 Rev. 23 discharge in concentrations that exceed 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2, then all inputs to the LVW Pond are sampled and checked for compliance with 10 CFR 20. The following methodology is used to determine compliance with these limits.1.1.1 Isotopic Concentration of the Waste Tank Determine the isotopic concentration in waste stream to be released: 7_ Ci Y XCg + (Ca + Cs + Ct + CFe) [Eq. 1-1]i g Where: E Sum of the concentrations of each radionuclide, i, in the release Ci (uCi/mi),-Sum of the concentrations of each measured, gamma emitter, Cg g, (uCi/ml) as required by Radiological Effluent g Control 3/4.11.1.1, Table 4.11-1.Ca Concentration of alpha emitters as measured in the most recent composite sample (uCi/mi) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (Sample analyzed for gross alpha only), Cs Concentration of 8 9 Sr and 9 0 Sr as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, Ct Concentration of 3 H as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, and CFe Concentration of 5 5 Fe as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.1.1.2 Effluent Flow Rate (f)The maximum effluent discharge flow rates for each release source are shown in Table 1.1. For pre-release calculations, the maximum effluent flow rate is normally used.For post-release calculations, the average effluent flow rate during the release may be used. When the maximum effluent flow rate is used for pre-release calculations, no setpoint is required for the flow measuring device for the effluent release line. If a lower effluent flow rate is used in pre-release calculations, a flow measuring device setpoint shall be established to ensure that the ratio of the Required Dilution Factor (RDF) to the Actual Dilution Factor (ADF) is maintained less than or equal to 1.0, as discussed in Section 1.1.6. ADF and RDF are defined in Section 1.1.4 and 1.1.5, respectively. | ||
Acceptable methods | CPSES -UNITS 1 AND 2- ODCM PART I111-2 Rev. 23 1.1.3 Dilution of Liquid Effluents a. Discharges to SCR via Circulating Water Discharge Tunnel Since liquid effluents from the radwaste treatment system, Waste Water Holdup Tanks and the LVW Pond are mixed with Circulating water prior to being discharged to Squaw Creek Reservoir, compliance with 10 CFR 20 is a function of the Circulating water flow rate. The maximum Circulating water flow rate per plant is 1.1 million gpm. This is determined from the Ingersoll-Rand pump curves (Fig. 1.2) which indicate a flow rate per pump of 275,000 gpm. The actual Circulating water dilution flow is given by: F(diluting flow) = (275,000 gpm/pump) x (# of pumps) x 0.9[Eq. 1-2]Where: 0.9 = Safety Factor to compensate for flow fluctuations from the rate predicted by the Circulating water pump curves (Fig. 1.2).As an additional consideration, the available dilution flow for any release may be corrected to allow for simultaneous releases from the Radwaste Processing System, a Waste Water Holdup Tank, and/or the LVW Pond (i.e., a radwaste system tank, a Waste Water Holdup Tank, and the LVW Pond may be discharged simultaneously). | ||
The Radioactive Effluent Release Report shall include a list and description of unplanned | For simultaneous releases, the available dilution flow for any release is reduced by the required dilution flow for any other concurrent releases. | ||
Also, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isotopes. | |||
an explanation as | It is therefore necessary to account for recirculation of previously discharged radionuclides. | ||
This documentation shall contain:1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) | This is accomplished as follows: F'= F(1 -Zi(C'i/10ECLi)) | ||
: b. Shall become effective after review and acceptance by the SORC and | [Eq. 1-3]Where: F' = Adjusted Circulating Water Flow Rate C'i Maximum concentration of radionuclide i in Squaw Creek Reservoir (uCi/ml) as measured in the analysis of the monthly samples of the reservoir required by Radiological Effluent Control 3/4.12.1, Table 3.12.1. Sample locations are listed and maintained current in the results of the annual Land Use Census.ECLi Effluent Concentration Limit of radionuclide i, from 10CFR20, Appendix B, Table 2, Column 2 F = (275,000 gpm/pump) x (# or pumps) x 0.9 NOTE: If C'i 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.CPSES -UNITS 1 AND 2- ODCM.PART 11 1-3 Rev. 23 | ||
: c. Shall be submitted to the Commission in the form of a complete, legible copy | : b. Discharges to the LVW Pond Secondary release sources are discharged directly to the LVW Pond with no dilution (i.e., F=O).1.1.4 Actual Dilution Factor (ADF)ADF is the ratio of the effluent flow rate plus the Circulating water flow rate divided by the effluent flow rate.ADF = (f + F)/f [Eq. 1-4]Where: f = Effluent flow rate (gpm)F = Dilution flow rate (gpm)NOTE: If radioactivity is detected in the Reservoir, an adjusted Circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See Section 1.1.3 for the calculation of F' (Eq. 1-3). Also, if simultaneous releases are occurring, the available dilution flow shall be reduced by the required dilution flow for any other concurrent release.1.1.5 Required Dilution Factor (RDF)The required dilution factor ensures that the limits of Control 3/4.11.1.1 (i.e., 10 times the effluent concentrations expressed in 10CFR20, Appendix B, Table 2, Column 2, and a total concentration of dissolved or entrained noble gases of 2 x 10-4 uCi/ml) are not exceeded during a discharge. | ||
CPSES -UNITS 1 AND 2- | The required dilution factor includes a safety factor of 2 to provide a margin of assurance that the instantaneous concentration limits are not exceeded.RDF = (yi (Ci/10ECL 1)) x SF (Xg (Cg/10ECLg)+ (Ca/10ECLa+ | ||
Each unit is a 1150 MWe, 4-loop, Westinghouse PWR. The units share a common primary | |||
Auxiliary Building Sumps 3 and 11, and the Unit 1 and Unit 2 Diesel Generator Sumps 1, 2, 3 and 4, and batch releases from the Condensate Polisher Backwash | |||
These secondary pathways from each unit are normally discharged to | |||
The LVW Pond | |||
Table 4.11-1 of Part I of this | |||
The recirculation | |||
A summary of all liquid effluent release sources, | |||
The conversion factor for detector output from counts per | |||
1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL 314.11.1.1 COMPLIANCE To demonstrate compliance with 10 CFR 20.1301, ODCM Radiological | |||
If radioactive materials are present in the LVW | |||
7_ Ci Y XCg + (Ca + Cs + Ct + CFe) [Eq. 1-1]i | |||
-Sum of the concentrations of each measured, gamma emitter,Cg g, (uCi/ml) as required by Radiological | |||
CPSES -UNITS 1 AND 2- | |||
Also, the reservoir into which | |||
It | |||
This is accomplished as follows:F'= F(1 -Zi(C'i/10ECLi)) | |||
[Eq. 1-3]Where: F' = Adjusted Circulating Water Flow | |||
: b. Discharges to the LVW | |||
The required dilution factor includes a safety factor of 2 | |||
RDF = (yi (Ci/10ECL 1)) x SF(Xg (Cg/10ECLg)+ | |||
(Ca/10ECLa+ | |||
Cs/10ECLs | Cs/10ECLs | ||
+Ct/10ECLt+ | +Ct/10ECLt+ | ||
CFe/10ECLFe)) | CFe/10ECLFe)) | ||
x SF [Eq. 1-5]Where: ECLi Effluent Concentration Limit of radionuclide i, from 1OCFR20,Appendix B, Table 2, Column | x SF [Eq. 1-5]Where: ECLi Effluent Concentration Limit of radionuclide i, from 1OCFR20, Appendix B, Table 2, Column 2 SF = Safety Factor of 2.CPSES- UNITS I AND 2- ODCM PARTII11-4 Rev. 23 All other variables and subscripts are previously defined.NOTE: If RDF is less than 1, the release 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 C 0 w in Section 1.2.1.1.1.6 10 CFR 20 Compliance Compliance with 10 CFR 20 is demonstrated if the Actual Dilution Factor (ADF) is greater than the Required Dilution Factor (RDF), or: RDF ADF < 1.0 [Eq. 1-6]1.2 RADIATION MONITOR ALARM SETPOINTS 1.2.1 Primary Liquid Effluent Monitor XRE-5253 To ensure that releases from the primary radwaste processing system do not exceed 10 times the 10 CFR 20, Appendix B, Table 2, Column 2 limits at the point of release to the CONTROLLED AREA or UNRESTRICTED AREA, a radiation detector (XRE-5253) monitors discharges to the Circulating Water Discharge Tunnel. XRV-5253 is the discharge isolation valve controlled by XRE-5253. | |||
The isolation valve shuts automatically if the detector alarms on high radiation or a detector operation failure occurs. It should | The isolation valve shuts automatically if the detector alarms on high radiation or a detector operation failure occurs. It should be noted that the liquid effluent monitor setpoint values determined using the methodology from this section will be regarded as upper bounds for the actual setpoint adjustments. | ||
That is, setpoints may be established at values lower than the calculated values, | That is, setpoints may be established at values lower than the calculated values, if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.Since the radiation monitor XRE-5253 is a gamma sensitive device, the monitor setpoint value shall be set based on the gamma radionuclides present in the waste stream.Therefore, a Required Dilution Factor gamma (RDFg) must be determined before the setpoint can be calculated. | ||
RDFg = X (Cg/10ECLg) | RDFg = X (Cg/10ECLg) | ||
X SF [Eq. 1-6a]CPSES -UNITS 1 AND 2- | X SF [Eq. 1-6a]CPSES -UNITS 1 AND 2- ODCM PART I111-5 Rev. 23 Where: RDFg The required dilution factor (gamma) corresponding to the gamma concentration in the undiluted waste stream ensuring that 10 times the effluent concentration limits in 10CFR20, Appendix B, Table 2, Column 2 are not exceeded at the point of release during a discharge. | ||
If RDFg is less than 1, set | If RDFg is less than 1, set RDFg equal to 1.0.SF = A required safety factor of 2 is used to account for the presence of Tritium, composited Alpha emitters, Fe-55, Sr-89 and Sr-90 values which are undetectable by this monitor and are at or near equilibrium and/or not expected to change rapidly under most plant conditions and statistical errors of measurement. | ||
The monitor XRE-5253 setpoint is determined using the following calculation: | The monitor XRE-5253 setpoint is determined using the following calculation: | ||
C0w = (ADF/RDFg) | C0w = (ADF/RDFg) | ||
X 9gCg [Eq. 1-7]Where: Cw The liquid waste effluent monitor alarm setpoint. | X 9gCg [Eq. 1-7]Where: Cw The liquid waste effluent monitor alarm setpoint. | ||
This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in a release at the limits of Control 3.11.1.1.All other variables are as previously defined.When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be those referenced in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, Table Notation 2. Figure 1.3 is a representative energy spectrum response for the RD-33 type detector used in XRE-5253. | |||
All other variables are as previously defined.When considering the mixture of nuclides in the liquid effluent stream in terms of | This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant. | ||
In fact between 1 3 7 Cs and 6 0 Co, 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. | |||
This | However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required.1.2.2 Turbine Building Sump Effluent Radiation Monitor 1RE-5100 and 2RE-5100 The purpose of the turbine building sump monitor (1 RE-51 00 and 2RE-51 00) is to monitor turbine building sump discharges and divert this discharge from the Low Volume Waste Pond to the Waste Water Holdup Tanks if radioactivity is detected. | ||
In fact between | 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 detectable radioactivity is not normally present in the Turbine Building Sumps, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm, should an inadvertent radioactive release occur. To this end, the setpoint will be initially established at three (3) times background until further data can be collected. | ||
Then, if this setpoint is exceeded, the monitor will direct control valves to divert the turbine building sumps discharges from the LVW Pond to the Waste CPSES -UNITS 1 AND 2- ODCM PARTII11-6 Rev. 23 Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir, if required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. When radioactive materials are detected in the Turbine Building Sumps, a setpoint then may be established for 1 RE-51 00 or 2RE-51 00 using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond.1.2.3 Station Service Water (SSW) Effluent Radiation Monitors I RE-4269/4270 and 2RE-4269/4270 The concentration of byproduct radioactive materials released from plant operations to the station service water (SSW) effluent lines normally is expected to be insignificant. | |||
1.2.2 Turbine Building Sump Effluent Radiation Monitor 1RE-5100 and 2RE- | However, because the SSW effluent has no additional dilution prior to its release into Squaw Creek Reservoir, it is important that this stream's process radiation monitors be optimized to detect any potential radioactive release of CPSES radioactive materials which could leak via this pathway. Complicating this surveillance task, operational experience has shown that the SSW radiation monitors periodically detect natural radionuclides in the SSW effluent. | ||
Because | These natural radionuclides originate from washout of radon daughter products on plant surfaces following rainfall events. The detection of natural radionuclides in the SSW effluent is consistent with the normal expected function and operable status of the SSW radiation monitors. | ||
However, if a SSW radiation monitor setpoint is exceeded and an alarm is initiated (especially during or immediately after rainfall), then it is necessary to verify if the detected radioactivity is from natural radionuclides or from plant contamination by established assessment techniques. | |||
Then, if this setpoint is exceeded, the monitor will direct | Natural radionuclides may be verified when a SSW alert setpoint only is exceeded by sampling or by comparison to the Component Cooling Water (CCW) process radiation monitors since the source of CPSES byproduct radionuclides in the SSW would be from the CCW.Plant procedures and operating practices provide verification of detector alert or alarm conditions. | ||
The SSW effluent radiation monitors should have alert setpoints established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release of plant byproduct radioactive materials occur. To this end, the monitor's alert setpoint is normally established at three (3) times background. | |||
Complicating this surveillance task, operational experience has shown that the SSW radiation monitors periodically detect | Alert setpoint alarms should be verified in accordance with plant procedures. | ||
These natural radionuclides originate from washout | Those alert setpoint alarms attributable to natural radionuclides should not be considered to be a plant adverse condition (i.e., release of plant contamination) and should not result in the monitor being declared inoperable. | ||
The SSW effluent radiation monitor's alarm setpoint is set at a higher level threshold, based on operating experience, to prevent alarm by most natural radionuclide washout events. Events that result in a SSW effluent radiation monitor alarm setpoint alarm should be considered a plant adverse condition and be investigated in accordance with plant procedures and applicable Controls of Part I of the ODCM. If the SSW effluent stream becomes contaminated with plant byproduct radioactive materials, radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows: Csw Y= 9[Eq. 1-8]DF CPSES -UNITS 1 AND 2- ODCM PARTII11-7 Rev. 23 Where: Csw = Station Service Water effluent monitor alarm setpoint Cg = Concentration of each measured gamma emitter (g), observed in the effluent (uCi/ml)DF = Xi(Ci/10ECLj) | |||
then it is necessary to verify if the detected radioactivity is from | = Dilution factor required to ensure limits of Control 3/4.11.1.1 are not exceeded.As stated above, for the SSW effluent release pathway there is no additional dilution available. | ||
Natural radionuclides may be verified when a SSW alert setpoint only is exceeded | Therefore, if the calculated DF is greater than 1.0, any releases occurring via this pathway will result in a violation of Radiological Effluent Control 3/4.11.1.1. | ||
The SSW effluent radiation monitors should have alert setpoints established as close to background as practical to prevent spurious alarms and yet alarm should | If plant byproduct radioactivity is detected in the SSW effluent, doses due to releases shall be calculated in accordance with the methodology given in Section 1.3, with the near field average dilution factor, Fk, equal to 1.0.1.2.4 Auxiliary Building to LVW Pond Radiation Monitor XRE-5251A The purpose of the Auxiliary Building to LVW Pond monitor (XRE-5251A) is to monitor the Auxiliary Building Sumps 3 and 11, Unit 1 and Unit 2 Diesel Generator Sumps 1 and 2 and the Unit 1 and Unit 2 Component Cooling Water Drain Tanks continuous discharges and divert these discharges from the Pond to the Waste Water Holdup Tanks if radioactivity is detected. | ||
Since detectable radioactivity is not normally present in these discharges, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent radioactive release occur. To this end, the setpoint will be initially established at three (3) times background until further data can be collected. | |||
Those | Then, if this setpoint is exceeded, XRE-5251A will direct valves X-HV-WM182 and 183 to divert the discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir, if required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. When radioactive materials are detected in the discharges, a setpoint then may be established for XRE-5251A using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond.1.3 DOSE CALCULATIONS FOR LIQUID EFFLUENTS For implementation of Radiological Effluent Control 3/4.11.1.2, the dose commitment from the release of liquid effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose commitments will be maintained for each calendar quarter and each calendar year. Dose calculations will be performed for releases from the Plant Effluent Tanks, Waste Monitor Tanks, Laundry Holdup &Monitor Tanks, Waste Water Holdup Tanks, and the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir. | ||
The SSW effluent radiation monitor's alarm setpoint is set at a higher level threshold, based on operating experience, to prevent alarm by most natural radionuclide | Although the LVW Pond is located in a CONTROLLED AREA, dose calculations for discharges to the LVW Pond will not be performed because there are no real pathways for exposure to members of the public. Doses for these pathways will be calculated when the LVW Pond is discharged to Squaw Creek Reservoir. | ||
= Dilution factor required to ensure limits | The cumulative dose over the desired time period (e.g., the sum CPSES -UNITS 1 AND 2- ODCM PART II11-8 Rev. 23 of all doses due to releases during a 31 day period, calendar quarter, or a calendar year)will be calculated using the following equation: DT =7 Dk + E D(lake)m k m[Eq. 1-9]Where: DT = Dose commitment to the total body or any organ due to all releases during the desired time interval from all release sources (mrem).Dk = Dose commitment received by the total body or any organ during the duration of release k(mrem). The equation for calculating Dk is given in Section 1.3.1 (Eq. 1-10).D(lake)m = 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. | ||
As stated above, for the SSW effluent release pathway there is no additional | The equation for calculating D(lake)m is given in Section 1.3.2 (Eq. 1-12).To demonstrate compliance with the dose limits of Control 3/4.11.1.2, the calculated cumulative dose (i.e., the total dose for both units) will be compared to two times the dose limits for a unit. In other words, the dose assigned to each unit will be one-half of the total doses from all releases from the site.1.3.1 Calculation of Dose Due to Liquid Releases The dose commitment to the total body or any organ due to a release will be calculated using the following equation: Dk IjAl tk Ci Fk[Eq. 1-10]Where: tk Cik Fk Time duration of the release k (hrs)Isotopic concentration (uCi/ml) of radionuclide i found in the release sample for release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For Sr-89, SR-90, H-3, Fe-55 and alpha emitters, the last measured value will be used in the dose calculation. | ||
Therefore, if the calculated DF is greater than 1.0, any releases occurring | 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 average flow into the Circulating water during the release.CPSES -UNITS 1 AND 2- ODCM PART 11 1-9 Rev. 23 Fk average undiluted liquid effluent flow rate circulating water flow rate Ai = Site related ingestion dose commitment factor for the toal body or any organ, t, for each identified gamma or beta emitter (mrem/hr per uCi/ml). Ai, is calculated as follows: .= 1.14x1:05 (Uw/Dw+ UfBFi) DF 1 [Eq. 1-11]Where: 1.14x10 5= unit conversion factor, pCi ml. yrs p.Ci. I. hrs Uw Adult water consumption from Squaw Creek Reservoir, 0 liters/yr for CPSES Uf = Adult fish consumption, 21 kg/yr BFj Bioaccumulation factor for radionuclide i, in fish from Table A-1, Ref. 2 (pCi/kg per pCi/I)DFj Adult dose conversion factor for radionuclide i, from Table E-1 1, Ref. 22 (mrem/pCi ingested)Dw = Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption; 1.0 for CPSES. (unitless) | ||
If | Calculated values for Ai, are given in Table 1.2.1.3.2 Calculation of Dose Due to Radionuclide Buildup in the Lake The dose contribution from significant pathways, due to buildup of previously discharged radionuclides in the lake, must be considered in the committed dose calculation only if radioactivity is detected in the water of Squaw Creek Reservoir or in fish from Squaw Creek Reservoir. | ||
Since detectable radioactivity is not normally present in | Based on the design calculations presented in the CPSES FSAR, Appendix 11A and documented in CPSES Engineering Calculation No. ME-CA-0000-3161, the significant pathways included in this calculation are fish consumption from Squaw Creek Reservoir and consumption of meat from cows drinking water from Squaw Creek. Additionally, consumption of milk from cows drinking water from Squaw Creek is included, but a CPSES site-specific consumption factor of 0 is normally used since there are no identified animals milked for human consumption along Squaw Creek. If animals milked for consumption are identified along Squaw Creek during the annual land use census, this pathway should be included in the dose calculation. | ||
Then, if this setpoint is exceeded, XRE-5251A will direct valves X-HV-WM182 and 183 to divert the discharges from | Also, water from Squaw Creek Reservoir or Squaw Creek is not used as a source of drinking water, so the drinking water pathway is not included in dose calculations. | ||
Although the LVW Pond | To further simplify the calculation, the dose due to consumption of meat and milk from cows drinking water from Squaw Creek is only calculated for tritium. CPSES Engineering CPSES -UNITS 1 AND 2- ODCM PART 11 1-10 Rev. 23 Calculation No. ME-CA-0000-3161 shows that tritium is the only isotope routinely released from CPSES that significantly contributes to the dose from these pathways (i.e., >95% of the total dose). The calculation does show a significant dose contribution from Ru-1 06 for the cow-meat pathway, but this isotope has not historically been observed in actual CPSES liquid effluent samples. The dose from the fish consumption pathway will be calculated for all measured isotopes.The contribution to the total dose due to the buildup of radionuclides in the reservoir is determined as follows: D(lake)m = 1.14xlO 1-4 [(Xi DFi C 0 f Uf)+DFt Ctw Qaw (UmilkFrt Umeat Fft)] x t [Eq. 1-12]Where: 1.14 x 10-4 = Units conversion factor (yr/hr).C'if = Concentration of radionuclide i in fish sampled from Squaw Creek Reservoir from location F1 as described in the most current CPSES Land Use Census (pCi/kg).DFt Adult ingestion dose conversion factor for tritium for the organ of interest from Table E-1 1, Ref. 2 (mrem/pCi). | ||
The cumulative dose over the desired time period (e.g., the | |||
DT =7 Dk + E D(lake) | |||
The equation | |||
= Dose commitment received by the total body or any | |||
The equation for calculating D(lake)m is given in Section 1.3.2(Eq. 1-12).To demonstrate compliance with the dose limits of Control 3/4.11.1.2, the calculated cumulative dose (i.e., the total dose for both units) will be compared to two times the | |||
Dk IjAl tk Ci Fk[Eq. 1-10]Where: | |||
Near field average dilution factor during a liquid effluent release.This is defined as the ratio of the average undiluted | |||
The average liquid effluent flow rate | |||
Ai, is calculated as follows: | |||
.= 1.14x1:05 (Uw/Dw+ UfBFi) | |||
Dw = Dilution factor from the near field area within one-quarter mile | |||
Calculated values for Ai, are given in Table 1.2.1.3.2 Calculation of Dose Due to Radionuclide Buildup in the | |||
Based on the design calculations presented in the CPSES FSAR,Appendix 11A and documented in CPSES Engineering Calculation No. ME-CA-0000-3161, the significant pathways included in this calculation are | |||
Also, water from Squaw Creek Reservoir or Squaw Creek is not used as | |||
To further simplify the calculation, the dose due to consumption of meat and milk | |||
CPSES Engineering CPSES -UNITS 1 AND 2- | |||
The dose from the fish consumption pathway will be calculated for all measured isotopes. | |||
The contribution to the total dose due to the buildup of radionuclides in the reservoir | |||
= 1. | |||
DFt Adult ingestion dose conversion factor for tritium for the organ | |||
C'tw Concentration of tritium in the reservoir. | C'tw Concentration of tritium in the reservoir. | ||
This value | This value shall correspond to the highest concentration measured at any Squaw Creek Reservoir sample location (pCi/I).Qaw = Consumption rate of contaminated water by a cow, 60 I/day from Table E-3, Ref. 2.Umilk Adult milk consumption rate. A CPSES site-specific usage factor of 0 is normally used unless milk cows are identified along Squaw Creek during the annual Land Use Census. If milk cows are identified, a value of 310 I/yr from Table E-5, Ref. 82, should be used.Fmt Stable element transfer coefficient for tritium that relates the daily intake rate of tritium by a cow to the concentration in milk, 1.OE-2 pCi/I per pCi/day from Table E-1, Rev. 2.CPSES -UNITS 1 AND 2- ODCM PART 11 1-11 Rev. 23 Umeat =-Adult meat consumption rate, 110 kg/yr from Table E-5, Ref. 2.Fft Stable element transfer coefficient for tritium that relates the daily intake rate of tritium by a cow to the concentration in meat, 1.2E-2 pCi/kg per pCi/day.t = Exposure time, hrs (8760 hrs = 1 year)All other variables are previously defined.NOTE: This calculation is only required if activity is detected in water and/or fish in excess of the appropriate LLD values given in Radiological Effluent Control 3/4.12.1, Table 4.12-1. If the measured activity in water or fish is less than the required LLD values, the concentration for that particular pathway is assumed to be zero.1.4 DOSE PROJECTIONS FOR LIQUID EFFLUENTS Radiological Effluent Control 3/4.11.1.3 requires that appropriate portions of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit to CONTROLLED AREAS and UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided for performing this dose projection. | ||
At least once every 31 days, the total dose from liquid releases for each unit for | At least once every 31 days, the total dose from liquid releases for each unit for the previous three months will be divided by the number of days in the three month period and multiplied by 31. Also, this dose projection may include the estimated dose for a unit due to any anticipated unusual releases during the period for which the projection is made. If the projected dose for a unit exceeds 0.06 mrem total body or 0.2 mrem for any organ, appropriate portions of the Liquid Radwaste Treatment System shall be used to reduce radioactivity levels prior to release.1.5 DEFINITIONS OF COMMON LIQUID EFFLUENT PARAMETERS TERM DEFINITION ADF Actual Dilution Factor (unitless). | ||
This is defined as the ratio of the | This is defined as the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.Ai, The site related ingestion dose commitment factor to the total body or any organ, t, for each identified gamma or beta emitter, i. (mRem/hr per uCi/ml)BFi Biaccumulation factor for radionuclide, i, in fish from Reg. Guide 1.109.(pCi/kg per pCi/I)Ca The concentration of alpha emitters in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)CPSES -UNITS 1 AND 2- ODCM PART 1I11-12 Rev. 23 TERM DEFINITION CFe The concentration of 5 5 Fe in liquid waste as measured in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)Cg The concentration of each measured gamma emitter, g, in the waste tank as measured in the analysis of the sample of each batch as required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)Ci The concentrations of radionuclide, i, in the waste tank. (uCi/ml)C'i The concentration of radionuclide i in the Reservoir as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Control 3/4.12.1, Table 3.12-1. This sample is taken at the Circulatory Water Intake Structure as indicated by location SW6 as described in the most current CPSES Land Use Census. (uCi/ml)C'if The concentration of radionuclide i in fish sampled from the reservoir from location F1 as described in the most current CPSES Land Use Census.(pCi/kg)Cik The isotopic concentration of radionuclide i found in the pre-release sample for batch release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For 8 9 Sr, 9 0 Sr, 3 H, 5 5 Fe and alpha emitters, the last measured value will be used. (uCi/ml)C'iw The maximum concentration of radionuclide i in SCR as measured in analysis of monthly samples of SCR.C 1 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 a release at the limits of Control 3.11.1.1. (uCi/ml)Cs The concentration of 8 9 Sr and 9 0 Sr in liquid waste as measured in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)Csw The Station Service Water effluent monitor alarm setpoint. (uCi/ml).Ct The concentration of 3 H in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)DFi Adult dose conversion factor for radionuclide, i, from Reg. Guide 1.109.(mrem/pCi ingested)Dk The dose commitment received by the total body or any organ during the duration of batch release k of liquid effluents. (mRem)D(lake)m The dose commitment received by the total body or any organ during a desired time period, m, due to the buildup in the lake of previously discharged radionuclides. (mRem)DT The total dose commitment to the total body or any organ due to all releases of liquid effluents during a desired time interval. (mRem)CPSES -UNITS 1 AND 2- ODCM PART 11 1-13 Rev. 23 TERM DEFINITION Dw Dilution factor, from the near field area within 1/4 mile of the release point to the potable water intake for adult water consumption, 1.0 for CPSES.(unitless) f Effluent flow rate. (gpm)F Circulating water flow rate (or dilution flow rate). (gpm)F' Adjusted Circulating water flow rate to account for buildup of radionuclides in the Circulating water due to previous releases. (gpm)Fk The near field average dilution factor during a liquid effluent release (unitless). | |||
This corresponds to | This is defined as the ratio of the average undiluted liquid waste flow to the average Circulating water flow during the release.ECLa Effluent Concentration Limit* of a mixture of unidentified alpha emitters.(uCi/ml)ECLFe Effluent Concentration Limit* of 5 5 Fe. (uCi/ml)ECLg Effluent Concentration Limit* of each identified gamma emitter, g.(uCi/ml)ECLi Effluent Concentration Limit* of radionuclide, i. (uCi/ml).ECLs Effluent Concentration Limit* of a mixture of 8 9 Sr and 9 0 Sr. (uCi/ml)ECLt Effluent Concentration Limit* of tritium (3 H). (uCi/ml).SF Safety Factor of 2. Used in the calculation of the Required Dilution Factor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are not exceeded.RDF Required Dilution Factor (unitless). | ||
(uCi/ml)Cs The concentration of | This is defined as the dilution factor that ensures that 10 times the effluent concentrations expressed in 10CFR20, Appendix B, Table 2, Column 2, are not exceeded at the point of release to CONTROLLED AREAS and UNRESTRICTED AREAS during a discharge. | ||
(uCi/ml). | tk The time duration of batch release k. (hours)Uf Adult fish consumption. (kg/yr)Uw Adult water consumption. (liters/yr) | ||
Ct The concentration of | Effluent Concentration limits (ECL) for liquids are given in 10CFR20, Appendix B, Table 2, Column 2. A value of 2x10-4 uCi/ml for dissolved or entrained noble gas shall be used.CPSES -UNITS 1 AND 2 -ODCM PART 11 1-14 Rev. 23 TABLE 1. | ||
Dk The dose commitment received by the total body or any organ during | |||
(mRem)D(lake)m The dose commitment received by the total body or any organ during | ==SUMMARY== | ||
(mRem)DT The total dose commitment to the total body or any organ due to | |||
(mRem)CPSES -UNITS 1 AND 2- | OF LIQUID RELEASE PATHWAYS 1. RELEASES TO SCR VIA THE CIRC WATER DISCHARGE Max FIl Release Source Release Type Rate (gp PET-1 Batch 101 PET-2 Batch 101 WMT-1 Batch 101 WMT-2 Batch 101 LHMT-1 Batch 10(LHMT-2 Batch 10'WWHT-1 Batch 30'WWHT-2 Batch 30 LVW Pond Continuous 160 2. RELEASES TO THE WASTE WATER MANAGEMENT SYSTEM OW 3m)M)0 0 0 0 0 0 0 0 0 Max Vol (gal)30000 30000 5340 5340 5875 5875 30500 30500 Monitor XRE-5253 XRE-5253 XRE-5253 XRE-5253 XRE-5253 XRE-5253 None None None Release Source CPBWRT-A CPBWRT-B WWHT-1 WWHT-2 TBSump2 (Unit1)TBSump4 (Unit2)AB Secondary* | ||
(gpm)Fk The near field average dilution factor during a liquid effluent release(unitless). | Temporary holdup tanks Release Type Batch Batch Batch Batch Continuous Continuous Continuous Max Flow Rate (gpm)1550 1550 200 200 300 300 380 Max Vol (gal)8500 17000 33100 33100 Monitor None None None None 1 RE-5100 2RE-51 00 XRE-5251A None Batch** Maximum flow and volume will be determined by temporary systems design.3. DIRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT) | ||
This is defined as the ratio of the average undiluted | Release Source Release Type Unit 1 SSW Train A Continuous Unit 1 SSW Train B Continuous Unit 2 SSW Train A Continuous Unit 2 SSW Train B Continuous AB Secondary Effluents contain the following sources: Max Flow Rate (gpm)17,000 17,000 17,000 17,000 Max Vol (gal)Monitor 1RE-4269 1 RE-4270 2RE-4269 2RE-4270 Auxiliary Building Sump 3 Auxiliary Building Sump 11 Diesel Generator Sump 1 (Unit 1)Diesel Generator Sump 2 (Unit 1)Diesel Generator Sump 1 (Unit 2)Diesel Generator Sump 2 (Unit 2)CCWDT (Unit 1)CCWDT (Unit 2)Max. Flow (opn)50 50 50 50 50 50 40 40 CPSES -UNITS 1 AND 2- ODCM PART 11 1-15 Rev. 23 TABLE 1.2SITE RELATED INGESTION DOSE COMMITMENT FACTOR Ai, ISOTOPE H-3 C-14 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-58 CO-60 NI-63 N 1-65 CU-64 ZN-65 ZN-69 BR-83 BR-84 BR-85 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 BONE 0.OOE+00 3.13E+04 4.07E+02 4.62E+07 0.00E+00 0.OOE+00 0.OOE+00 6.58E+02 1.04E+03 0.OOE+00 0.OOE+00 3.11 E+04 1.26E+02 0.OOE+00 2.32E+04 4.93E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.21 E+04 5.47E+05 4.07E+02 LIVER 2.26E-01 6.25E+03 4.07E+02 2.87E+06 0.OOE+00 4.38E+03 1.1OE+02 4.55E+02 2.44E+03 8.91E+01 2.56E+02 2.16E+03 1.64E+01 9.97E+00 7.37E+04 9.44E+01 0.OOE+00 0.OOE+00 0.OOE+00 1.01 E+05 2.94E+02 1.95E+02 0.OOE+00 0.00E+00 0.OOE+00 T-BODY 2.26E-01 6.25E+03 4.07E+02 1.79E+06 1.27E+00 8.35E+02 1.95E+01 1.06E+02 9.35E+02 2.OOE+02 5.65E+02 1.05E+03 7.49E+00 4.68E+00 3.33E+04 6.56E+00 4.05E+01 5.24E+01 2.15E+00 4.71 E+04 1.56E+02 1.37E+02 6.35E+02 1.33E+05 1.64E+01 THYROID 2.26E-01 6.25E+03 4.07E+02 0.OOE+00 7.62E-01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.O0E+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 KIDNEY 2.26E-01 6.25E+03 4.07E+02 0.OOE+00 2.80E-01 1.31 E+03 1.40E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.51E+01 4.93E+04 6.13E+01 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+0O O.OOE+0C O.OOE+OC LUNG 2.26E-01 6.25E+03 4.07E+02 0.OOE+00 1.69E+00 0.OOE+00 0.OOE+00 2.54E+02 6.82E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00) O.OOE+0C O.OOE+0C O.OOE+OC GI-LLI 2.26E-01 6.25E+03 4.07E+02 5.20E+06 3.20E+02 1.34E+04 3.51 E+03 2.61 E+02 8.16E+03 1.81 E+03 4.81 E+03 4.50E+02 4.16E+02 8.49E+02 4.65E+04 1.42E+01 5.82E+01 4.11 E-04 1.01 E-15 2.OOE+04 3.93E-09 1.13E-11 3.55E+03 1.58E+04 1 .94E+03 SR-92 1.54E+02 0.OOE+00 6.67E+00 0.OOE+00 O.OOE+00 0.OOE+00 3.06E+03 CPSES -UNITS 1 AND 2- ODCM PART II11-16 Rev. 23 TABLE 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR Ai, ISOTOPE Y-90 Y-91 M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M TC-101 RU-103 RU-1 05 RU-1 06 AG-A11M TE-125M TE-127M TE-127 TE-129M TE-129 TE-131M TE-1 31 TE-132 1-130 1-131 1-132 1-133 BONE 5.77E-01 5.44E-03 8.45E+00 5.06E-02 1.60E-01 2.40E-01 1.33E-02 4.46E+02 0.OOE+00 8.86E-03 9.13E-03 4.42E+00 3.69E-01 6.59E+01 8.81 E-01 2.57E+03 6.49E+03 1.05E+02 1.10E+04 3.01 E+01 1.66E+03 1.89E+01 2.41 E+03 2.72E+01 1.50E+02 7.29E+00 5.09E+01 LIVER 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 7.70E-02 2.68E-03 2.49E+02 1.03E+02 2.51 E-02 1.31 E-02 0.OOE+00 0.OOE+00 0.OOE+00 8.13E-01 9.29E+02 2.32E+03 3.78E+01 4.11E+03 1.13E+01 8.11E+02 7.88E+00 1.56E+03 8.02E+01 2.14E+02 1.95E+01 8.86E+01 T-BODY 1.54E-02 2.11 E-04 2.25E-01 1.48E-03 4.43E-03 5.21 E-02 1.22E-03 1.34E+02 1.96E+01 3.20E-01 1.29E-01 1.91 E+00 1.45E-01 8.33E+00 4.84E-01 3.44E+02 7.90E+02 2.28E+01 1.74E+03 7.32E+00 6.75E+02 5.95E+00 1.46E+03 3.17E+01 1.22E+02 6.81 E+00 2.70E+01 THYROID 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 7.72E+02 1.66E+03 7.80E+01 3.78E+03 2.31E+01 1.28E+03 1.55E+01 1.72E+03 6.78E+03 6.99E+04 6.81 E+02 1.30E+04 KIDNEY 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.21 E-01 4.05E-03 2.46E+02 2.35E+02 3.80E-01 2.37E-01 1.69E+01 4.76E+00 1.27E+02 1.60E+00 1.04E+04 2.63E+04 4.29E+02 4.60E+04 1.26E+02 8.21 E+03 8.26E+01 1.50E+04 1.25E+02 3.68E+02 3.10E+01 1.55E+02 LUNG 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-'00 0.OOE+00 1 .23E-02 6.72E-03 0.OOE+0O 0.OOE-I00 0.OOE+0Q 0.00E4-00 0.OOE-I0Q Q.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+0C* .OOE+OC* .OOE+OC 0.OOE+OC 0.OOE+OC 0.OOE+OC GI-LLI 6.11 E+03 1.60E-02 4.64E+03 8.87E+02 5.1OE+03 2.44E+02 8.30E+02 1.51 E+06 2.39E+02 1.48E+01 3.95E-14 5.16E+02 2.26E+02 4.27E+03 3.33E+02 1.02E+04 2.17E+04 8.31 E+03 5.54E+04 2.27E+01 8.04E+04 2.67E+00 7.38E+04 I 6.90E+01 I 5.64E+01 3.68E+00 7.96E+01 CPSES -UNITS 1 AND 2- ODCM PART II11-17 Rev. 23 TABLE 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR Ai, ISOTOPE 1-134 1-135 CS-1 34 CS-1 36 CS-1 37 CS-1 38 BA-1 39 BA-140 BA-141 BA-142 LA-1 40 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239*SB-122**SB-124**BR-82**SB-1 25**SB-1 26**SB-1 27**LA-141 BONE 3.80E+00 1.59E+01 2.98E+05 3.12E+04 3.81E+05 2.64E+02 9.29E-01 1.94E+02 4.51E-01 2.04E-01 1.50E-01 7.66E-03 2.24E-02 3.94E-03 1.17E+00 5.52E-01 1.80E-03 3.76E-01 2.95E+02 2.86E-02 4.42E+00 5.38E+01 0.OOE+00 4.27E+01 2.20E+01 4.94E+00 1.14E-02 LIVER 1.03E+01 4.16E+01 7.09E+05 1.23E+05 5.22E+05 5.22E+02 6.61 E-04 2.45E-01 3.41 E-04 2.09E-04 7.53E-02 3.16E-03 1.51E-02 2.91E+00 4.89E-01 2.21 E-01 7.49E-04 4.35E-01 2.48E+02 2.79E-03 8.71 E-02 1.01 E+00 0.OOE+00 4.58E-01 4.47E-01 1.80E-01 3.55E-03 T-BODY 3.71 E+00 1.54E+01 5.79E+05 8.86E+04 3.42E+05 2.59E+02 2.72E-02 1.27E+01 1.53E-02 1.28E-02 1.99E-02 8.66E-04 1.72E-03 3.24E-04 6.26E-02 2.73E-02 9.16E-05 2.60E-02 8.65E+01 1.54E-03 1.29E+00 2.12E+01 1.78E+02 8.58E+00 7.93E+00 1.90E+00 5.81 E-04 THYROID 1.79E+02 2.75E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.00E+00 6.01E-02 1.30E-01 O.OE+00 3.80E-02 1.35E-01 5.94E-02 KIDNEY 1.65E+01 6.69E+01 2.29E+05 6.85E+04 1.77E+05 3.83E+02 6.18E-04 8.30E-02 3.17E-04 1.77E-04 0.OOE+00 0.OOE+00 7.05E-03 1.29E-03 2.91 E-01 1.28E-01 4.23E-04 2.54E-01 0.OOE+00 8.74E-03 0.OOE+OC 0.OOE+OC O.OOE+OC O.OOE+OC 0.OOE+0C O.OOE+O(LUNG 0.00E+00 0.0OE+00 7.62E+04 9.39E+03 5.89E+04 3.78E+01 3.76E-04 1.39E-01 1.93E-04 1.19E-04 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00)0.OE+O0 O.OOE+OC) 2.30E+0C) 4.18E+01 O.OOE+OC 1.35E+0'2.93E+O(GI-LLI 9.01 E-03 4.70E+01 1.24E+04 1.40E+04 1.01 E+04 2.23E-03 1.65E+00 4.OOE+02 2.06E-1 0 2.87E-1 9 5.52E+03 2.54E+01 5.79E+01 1.09E+02 3.94E+02 2.41 E+03 2.59E-1 0 2.09E+03) 8.11 E+04) 5.74E+02 1 1.27E+03 1 .52E+03 2.05E+02 3.78E+02 I 1.80E+03) 1.13E+03 0.OOE+00 0.OOE+00 0.OOE+00 4.23E+02 CPSES -UNITS 1 AND 2 -ODCM PART II11-18 Rev. 23 The adult dose conversion factors, DFi, for Sb-122 are not published in Reference | ||
(uCi/ml)ECLFe Effluent Concentration Limit* of | : 2. The calculation of dose conversion factors and site-related ingestion dose commitment factors for Sb-1 22 is documented in Reference 10.The adult dose conversion factors, DFi, for Sb-124, Sb-1 25, Br-82, Sb-1 26, Sb-1 27 and La-141 are not published in Reference | ||
: 2. The site-related dose commitment factors for Sb-124, Sb-125, Br-82, Sb-126, Sb-127 and La-141 were calculated using the "Adult Ingestion Dose Factors" given in Table A-3 of Reference 11, and Equation 1-11 of Part II, Section 1.3.1 of this Manual.CPSES -UNITS 1 AND 2- ODCM PART 1I 1-19 Rev. 23 Inputs [I1SW~n Input Unit I SSW -Train A From Liquid Waste IUnit I SSW-Train B Processing S stem I nt2SW-Trln A 33.100 gal ea. XRE-5253 Unit 2 SSW-Train B 300 gpm ea.-- -------Waste Water ic Holdup Tanks N =ter (2 tanks) A: 8500 gal/1 550 gpm T I B: 17000 gal/1550 gpm I C.P.' " Backwash Temporary 1975 gal -- -Recovery Holdup Tanks30 .... ... .. ..... ... Tanks 300 A and B 1 RE-,5100 Unit 1 Turbine I,0Waste' Building Sump -1 i Water No. 2 Management 1975 gal Clarfier , 300 gpm Sump I 600 gpm Unit 2 Turbine 2RE-5100 Building Sump No.4 XRE-5251A I ~ AuxilliaryI Unit1 Unt 2Unit 1 Unit 2 Bilding Diesel Gen. Diesel Gen. CCW Drain CCW Drain Sumps SumpsSumpsTank Tank No.3 &11 135 gal ea. 135 gal ea. 2300 gal 2300 gal 135 gal ea.50 gpm ea. 50 gpm ea. 40 gpm 40 gpm 50 gpm ea.LIQUID EFFLUENT DISCHARGE PATHWAYS FIGURE 1.1 (Simplified diagram)KEY:_ Normal flow path---------- | |||
ECLs Effluent Concentration Limit* of a mixture of | Flow path f > ECL..... -Flow path If < ECL CPSES -UNITS 1 AND 2- ODCMA 2 PART 11 1-20 Rev. 23 C)FIGURE 1.2 MOEBOhISLt-RAND CURVE # XV-3552-4 o r 214.000 ErrOUas CIRCULATING WATER PUMP CURVES BANrmpS m iuarm 288 sv1 01 aE112141-~ IS 9F ri"1,1 " III ............. | ||
SF Safety Factor of 2. Used in the calculation of the Required Dilution Factor(RDF) for liquid releases to provide a margin of assurance that | .... ......... .... .... .... ................. | ||
RDF Required Dilution Factor (unitless). | |||
This is defined as the dilution | |||
tk The time duration of batch release k. (hours)Uf Adult fish consumption. | |||
(kg/yr)Uw Adult water consumption. | |||
(liters/yr) | |||
Effluent Concentration limits (ECL) for liquids are given in 10CFR20, Appendix B,Table 2, Column 2. A value of 2x10-4 uCi/ml for dissolved or entrained noble | |||
Temporary holdup | |||
Release Source Release | |||
: 2. | |||
: 2. The site-related dose commitment factors | |||
Flow path f > ECL..... -Flow path If < | |||
.... ......... | |||
.... .... .... ................. | |||
........... | ........... | ||
N, ":: 3,-.; .... .....Ifli ilýl~hIIIIjllIJIIjll!11111$'iIIIT 11 ffh~lh~ l ~l lllii I' lff l 1lJiJIlII~llf 34,-40~-A I | N, ":: 3,-.; .... .....Ifli ilýl~hIIIIjllIJIIjll!11111$'iIIIT 11 ffh~lh~ l ~l lllii I' lff l 1lJiJIlII~llf 34,-40~-A I i 0 .'Ivor1 i.o il £ ~ s~ ~ 1130arm2 I --r- -f 32 34 A-.------I I -CPSES -UNITS 1 AND 2 -ODCM PART II11-21 Rev. 23 c-! 20 8 7 5 0 01 0.4 0.6 0.8 1.0 1.2 1.4 GAMMA PHOTON ENERGY, MeV ENERGY RESPONSE TO GAI9Yk RADIATIONS FOR PD-33 TYPE DETECTOR Figure 1.3?The &Vokw por oft am curv gwa efa~ from mrly isfoto Ciibra~os utrV a chaImbwe of simil goomeiry.on otm golma we odw raw .CPSES -UNITS 1 AND 2- ODCM P2 PART 11 1-22 Rev. 23 SECTION 2.0 GASEOUS EFFLUENTS At CPSES, normal radioactive gaseous effluents are collected in a common exhaust air intake plenum, processed through charcoal and HEPA filters, and discharged to the atmosphere through the two common Plant Vent Stacks designated as Stack A and Stack B. Due to the fact that these release points are below the height of the nearest adjacent structure (i.e., containment building), all gaseous releases from these stacks are conservatively assumed to be entrained into the building wake and cavity regions, which results in a conservative ground-level release.Routine gaseous effluent releases may occur from the Unit 1 and Unit 2 Containment Buildings (purges and vents), Waste Gas Decay Tanks (WGDT), and the plant vent stacks (continuous ventilation). | ||
all gaseous releases from these stacks are conservatively assumed to be entrained into the building wake and cavity regions, which results in a conservative ground-level release.Routine gaseous effluent releases may occur from the Unit 1 and Unit 2 Containment Buildings (purges and vents), Waste Gas Decay Tanks (WGDT), and the plant vent stacks (continuous ventilation). | The normal ventilation exhaust via the plant vent stacks is considered a continuous release. Containment Building vents for pressure relief and WGDT discharges are treated as batch releases. | ||
The normal ventilation exhaust via the plant vent stacks is considered a continuous release. | Because Containment Building purges are only allowed during MODES 5 and 6 and because radioactivity is discharged rapidly from the containment atmosphere during purges, the first portion (i.e., the release period during which most containment atmospheric radioactivity is discharged) of a Containment Building purge is considered a batch release. The remainder of a purge is treated as a contribution to the continuous release already occurring through the plant vent stacks.Operating experience has shown that occasional releases may be required from Pressurizer Relief Tank (PRT) vents for depressurizing the RCS during outages, from Volume Control Tank (VCT) vents during maintenance on the Waste Gas Processing System, from the Containment Buildings during Integrated Leak Rate Tests (ILRT), and from secondary steam releases (potentially radioactive during periods of primary-to-secondary leaks). These releases occur infrequently and are treated as batch releases.Occasional operational requirements involve handling radioactive materials in buildings outside the permanent structures that may contribute to gaseous effluents. | ||
Containment Building vents for pressure relief and WGDT discharges are treated | Since these buildings are not connected to the PRIMARY PLANT VENTILATION SYSTEM, portable air sampling equipment may be used to determine effluent airborne radioactivity concentrations. | ||
Because Containment Building purges are only allowed during MODES 5 and | Offsite dose estimates will be based on the analysis of samples collected, estimated effluent flow rates and treated as a planned continuous or batch release. The effluent discharge point is not the plant stack and the distance to the site boundary may be adjusted, if the proximity to the site boundary would significantly affect the offsite dose estimates. | ||
The remainder | No automated monitoring or isolation equipment is provided, however, due to a limited source term, this pathway is expected to contribute a small fraction of the dose limits from gaseous effluents. | ||
Occasional operational requirements involve handling radioactive materials in buildings | A summary of all gaseous effluent release points, release sources, flow rates (if applicable) and associated radiation monitors is shown in Table 2.1. A flow diagram of all Gaseous Waste Processing System discharge pathways is shown in Figure 2.1.Each Plant Vent Stack is equipped with a Wide Range Gas Monitor (WRGM) and a Noble Gas Monitor. These monitors are part of the plant Digital Radiation Monitoring System (DRMS)supplied by Sorrento Electronics (formerly General Atomics). | ||
Since these buildings are | Since all DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uCi/ml). The conversion factor for detector output from counts per minute to uCi/ml is determined during the calibration of each individual monitor, and is input into the data base for the monitor microprocessor. | ||
Offsite dose estimates will be based on the analysis of samples collected, estimated effluent flow rates and treated as | The WRGMs are designated as monitors XRE-5570A and XRE-5570B for Stacks A and B, respectively. | ||
The effluent discharge point is not the plant stack and | Each WRGM consists of a low range (10-7 to 10-1 uCi/cc), mid range (10-4 to CPSES -UNITS 1 AND 2- ODCM PART II12-1 Rev. 33 102 uCi/cc), and high range (10-1 to 105 uCi/cc) noble gas activity detector. | ||
No automated monitoring or isolation equipment | 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 flow rate detectors (X-FT-557OA-1/B-1) to provide an indication of noble gas release rate in uCi/sec. Alarm setpoints are established for the WRGM effluent release rate channel to fulfill the requirements of Radiological Effluent Control 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 Noble Gas Monitors are designated as noble gas channels XRE-5567A and XRE-5567B for Stacks A and B, respectively. | |||
A summary of all gaseous effluent release points, release sources, flow rates (if applicable) | The stack noble gas channels may be used as a back-up to the WRGM when no automatic control functions are required. | ||
These monitors are part of the plant Digital Radiation Monitoring System (DRMS)supplied by Sorrento Electronics (formerly General Atomics). | Therefore, a methodology is provided for calculating the noble gas monitor setpoints. | ||
Since all DRMS monitors provide | 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 Monitors, 1 RE-5503 and 2RE-5503. | ||
The conversion factor for detector output from counts per minute to uCi/ml | 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. | ||
1 RE-5503 and 2RE-5503 monitor the Unit 1 and Unit 2 Containment atmospheres, respectively, and provide the only automatic control function for termination of Containment vents or purges.2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 COMPLIANCE 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 BOUNDARY due to noble gases released from the site shall be calculated as follows: a. Total Body Dose Rate Due to Noble Gases Dt= Dtv =_ (X/Q) K Qiv [Eq. 2-1]v v (noble gases)Where: Dt = Total body dose rate at the SITE BOUNDARY due to noble gases from all release sources (mRem/yr)Dtv = Total body dose rate at the SITE BOUNDARY due to noble gases from release source v (mRem/yr).(X/Q)= Highest annual average relative concentration at the SITE BOUNDARY (3.3 x 10-6 sec/m 3 in the NNW sector at a distance of 1.29 miles from the plant*)NOTE: The annual average X/Q is also used in determining setpoints for containment purge or vent as required by Technical Specification 3.3.6.CPSES -UNITS 1 AND 2- ODCM PART 11 2-2 Rev. 33 Ki Total body dose factor due to gamma emissions from noble gas radionuclide i from Table 2.2 (mRem/yr per uCi/m 3)4v Total release rate of noble gas radionuclide i from the release source v (uCi/sec) (See C below for calculation of Q 1 v)v = Index over all release sources Reference 4, Section 2.3.5.2.b. Skin Dose Rate Due To Noble Gases Ds= Dsv v= % (X/Q)V 7- (Li + 1.1 Ml)Qiv (noble gases)[Eq. 2-2]Where: Ds Skin dose rate at the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)Dsv Skin dose rate at the SITE BOUNDARY due to noble gases from release source v. (mRem/yr)Li Skin dose factor due to beta emissions from noble gas radionuclide i from Table 2.2 (mRem/yr per uCi/m 3)1.1 = Conversion factor of mRem skin dose per mRad air dose Mi = Air dose factor due to gamma emissions from noble gas radionuclide i from Table 2.2 (mRad/yr per uCi/m 3)All other terms are as previously defined.c. Release Rate Qj is defined as the total release rate (uCi/sec) of radionuclide i from all release sources. Qi is given by: Qi = , Qiv= _I XiVFV v v[Eq. 2-3]Where: Xiv Measured concentration of radionuclide i present in each release source v (uCi/cm 3)CPSES -UNITS 1 AND 2- ODCM PART 11l2-3 Rev. 33 Flow rate from each release source v (cm 3/sec)Qiv = Release rate of radionuclide i from release source v (uCi/sec)v = Index over all release sources 2.1.2 Dose Rates Due to Radioiodines, Tritium, and Particulates Organ dose rates due to iodine-1 31 and iodine-1 33, tritium, and all radioactive materials in particulate form with half-lives greater than eight days released from the site will be calculated to implement the requirements of Radiological Effluent Control 3/4.11.2.1 .b as follows: D o Dov (X/Q) I PAQ 1 [Eq. 2-4]v v IP&T Where: Do Total organ dose rate due to iodine-131, iodine-133, particulates with half-lives greater than eight days, and tritium from all release sources. (mrem/yr)Dov Organ dose rate due to iodine-1 31, iodine-1 33, particulates with half-lives greater than eight days, and tritium from release source v. (mrem/yr)Pi = Pathway dose rate parameter factor for radionuclide, i, (for radioiodines, particulates, and tritium) for the inhalation pathway in mRem/yr per uCi/m 3 (Table 2.3). The methodology used for determining values of Pi is given in Appendix A.IP&T = Iodine-131, iodine-133, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed. | |||
The WRGMs are designated as monitors XRE-5570A and XRE-5570B for Stacks A and B,respectively. | All other variables are previously defined.2.2 GASEOUS 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. | ||
Each WRGM consists of a low range (10-7 to 10-1 uCi/cc), | Setpoints may be established at values lower than the calculated values if desired.Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.If a calculated setpoint is less than the measured concentration associated with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and the setpoint recalculated. | ||
mid range (10-4 | CPSES -UNITS 1 AND 2- ODCM PARTI12-4 Rev. 33 2.2.1 Plant Vent Effluent Release Rate Monitors XRE-5570A and XRE-5570B Effluent Release Rate Channels The WRGM effluent release rate channels monitor the release rate of radioactive materials from each plant vent stack by combining inputs from the WRGM low range noble gas activity channel (uCi/cm 3) indication and a stack flow rate (cm 3/sec) indication (X-FT-5570A-1/B-1) to yield an effluent release rate (uCi/sec). | ||
and high range (10-1 to 105 uCi/cc) noble gas activity detector. | By establishing an alarm setpoint for this monitor, an increase in either the noble gas activity or stack flow rate will cause an alarm trip. The WRGM effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases. | ||
The WRGMs | The setpoint for each plant vent effluent release rate monitor will be calculated using the following methodology: | ||
Alarm setpoints are established for the | QSITE = the lessor of: 500 xS =125 QNG[E.27 NG= D-x SF = t[Eq. 2-7]QNG Dt Dt OR 3000 .QDNN QN6- s x SF = 750 [Eq. 2-6]Where: Qsite Total site noble gas release rate limit corresponding to a dose rate at or beyond the SITE BOUNDARY of 500 mrem/yr to the total body or 3000 mrem/yr to the skin. (uCi/sec)QNG (noble gases) Qi Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2.500 = Dose rate limit to the total body of an individual at or beyond the SITE BOUNDARY due to noble gases from all release sources.(mRem/yr)3000 = Dose rate limit to the skin of the body of an individual at or beyond the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)SF Safety Factor of 0.5 applied to compensate for statistical fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks (unitless) | ||
Exceeding the WRGM effluent release rate channel high alarm setpoint also initiates automatic termination of Waste Gas Decay Tank releases. | CPSES -UNITS 1 AND 2- ODCM PART 1I12-5 Rev. 33 Then the release rate setpoint for each stack monitor, Cf, in uCi/sec is determined as follows: Cf = Qsite" AF [Eq. 2-7]Where: AF Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitless). | ||
The stack Noble Gas Monitors are designated as noble gas channels XRE-5567A | This factor will limit the release rate contribution from each stack to 1/2 the limit for the site.2.2.2 Plant Vent Stack Noble Gas Activity Monitors XRE-5570A/XRE-5570B (WRGM low range noble gas activity channel) and XRE-5567A/XRE-5567B (noble gas channel)The WRGM low range noble gas activity channels provide noble gas concentration data to the effluent release rate channels, as discussed in Section 2.2.1 above. The monitor design does not include an alarm setpoint for this channel that provides an audible alarm if the setpoint is exceeded. | ||
The stack noble gas channels may be used as | Therefore, setpoint adjustments are not performed for these channels. | ||
Therefore, | Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, ACTION 36 allows for use of the stack noble gas monitors (XRE-5567A and XRE-5567B) as a backup for an inoperable WRGM effluent release rate channel when no automatic control function is required. | ||
Other monitors that may be used for effluent monitoring and control are the Auxiliary | The alarm setpoint for these channels, CG, in uCi/cm 3 is determined using the following methodology: | ||
XRE-5701 may be used to monitor Waste Gas Decay Tank releases | CG = Cf [Eq. 2-8]Where: Fpvs Maximum stack flow rate (cc/sec) corresponding to 115,000 cfm during normal operations and 130,000 cfm during containment purges.2.2.3 Sampler Flow Rate Monitors (X-RFT-5570A-1/B-1) | ||
1 RE-5503 and 2RE-5503 | |||
.a, the dose rate to the | |||
Dtv = Total body dose rate at the SITE BOUNDARY due | |||
(X/Q)= Highest annual average relative concentration at | |||
(See C below for calculation of | |||
(mRem/yr) | |||
Dsv Skin dose rate at the SITE BOUNDARY due to | |||
Li Skin dose factor due to beta emissions from noble | |||
Qi is given by:Qi = , Qiv= _I | |||
.b | |||
(mrem/yr) | |||
Dov Organ dose rate due to iodine-1 31, iodine-1 33, particulates | |||
Pi = Pathway dose rate parameter factor for radionuclide, i, ( | |||
These are the isotopes over which | |||
All other variables are previously defined.2.2 GASEOUS EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values, as determined using the methodology in | |||
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, | |||
CPSES -UNITS 1 AND 2- | |||
By establishing an | |||
The setpoint for each | |||
QSITE = the lessor of:500 xS =125 QNG[E. | |||
QNG (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 (unitless) | |||
CPSES -UNITS 1 AND 2- | |||
This factor will | |||
Therefore, setpoint adjustments are not performed for | |||
Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, ACTION 36 allows for | |||
The alarm setpoint for these channels, CG, in uCi/ | |||
CG = Cf [Eq. 2-8]Where: Fpvs Maximum stack flow rate (cc/sec) corresponding to 115,000 | |||
The WRGMs are designed to sample isokinetically from the plant vent stacks. Isokinetic sample flow is maintained automatically by the monitor microprocessor. | The WRGMs are designed to sample isokinetically from the plant vent stacks. Isokinetic sample flow is maintained automatically by the monitor microprocessor. | ||
The | 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. | The loss of sample flow alarm setpoints are established permanently in accordance with vendor specifications. | ||
2.2.4 Auxiliary Building Ventilation Exhaust Monitor (XRE-5701) | 2.2.4 Auxiliary Building 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 (ABV) Duct Monitor (XRE-5701) to be used as a backup for an inoperable WRGM for monitoring Waste Gas Decay Tank (WGDT) releases. | |||
XRE-5701 monitors WGDT releases by measuring activity | |||
.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) | .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 | DFLt,a,o = Ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, R.G. 1.109).All other parameters and values are as given above.NOTE: Goat-milk pathway factor, Rci,a,o will be computed using the cow-milk pathway factor equation. | ||
= Ingestion dose factor for tritium and organ, o, for each respective | Fm factor for goat-milk will be from Table E-2, R.G. 1.109. QF for goats is 6 kg/day from Table E-3, R.G. 1.109.CPSES -UNITS 1 AND 2- ODCM PART I I D-2 Rev. 32 APPENDIX D (CONTINUED) | ||
Fm factor for goat-milk will be from Table E-2, R.G. 1.109. QF for goats | |||
The concentration of C-14 in milk is based on the airborne concentration rather than deposition. | The concentration of C-14 in milk is based on the airborne concentration rather than deposition. | ||
Therefore, Rc. is based on (X/Q)RCc,a,o = k' k"' Fm QF UAp DFLc,a,o | Therefore, Rc. is based on (X/Q)RCc,a,o = k' k"' Fm QF UAp DFLc,a,o [0.11/0.16] (p) (f) [Eq. D-3]Where: k' = Units conversion factor pCi!/Ci (106)k,, = Units conversion factor gm/kg (103)Fm = Stable element transfer coefficient (Table E-1, R.G. 1.1 09)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109)DFLc,a,o = Ingestion dose conversion factor for C-14, organ o, and age group a, (Tables E-11 to E-14, R.G. 1.109) (mrem/pCi) 0.11 = Fraction of total plant mass consisting of natural carbon (R.G. 1.109)0.16 = Concentration of natural carbon in the atmosphere (gm/m 3) (R.G. 1.109)p = Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is established to be 0.31, based on 70% of C-14 releases being from wGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series. 421,"Management of Waste Containing Tritium and Carbon-14", 2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.NOTE: Goat-milk pathway factor, RCc,a,o will be computed using the cow-milk pathway factor equation. | ||
[0.11/0.16] | Fm factor for goat-milk will be from Table E-2, R.G. 1.109 QF for goats is 6 kg/day from Table E-3, R.G. 1.109.CPSES- UNITS 1 AND 2- ODCM PART 11 D-3 Rev. 32 APPENDIX E COW-MEAT PATHWAY DOSE FACTOR (RMi,a,o)M =k R i,a,o [(QF x UAp)/(Xl + x (Ff) x (r) x (DFLi 8 Q) x[((fp x fs)/Yp) + ((1 -fpfs)e- ith)/Ys] x e-Xitf [Eq. E-l]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, child, teenager, and adult age groups, respectively (R.G. 1.109)Ff = Stable element transfer coefficients, days/kg (Table E-1, R.G. 1.109)r = Fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, R.G. 1.109)DFLia,o = Ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)x'i = Decay constant for radionuclide i, sec" 1 XW= Decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-01 33)tf = 1.73 x 106 sec, Transport time from pasture to receptor (NUREG-0133) th = 7.78 x 106 sec, Transport time from crop to receptor (NUREG-0133) | ||
(p) (f) [Eq. D-3]Where:k' = Units conversion factor pCi!/Ci (106)k,, = Units conversion factor gm/kg (103)Fm = Stable element transfer coefficient (Table E-1, R.G. 1.1 09)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child,teenager, and adult age groups, respectively (R.G. 1.109)DFLc,a,o | YP = Agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG-0133) | ||
= Ingestion dose conversion factor for C-14, organ o, and age group a, ( | YS = Agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) fp = 1.0, Fraction of the year that the cow is on pasture fs = 1.0, Fraction of the cow feed that is pasture grass while the cow is on pasture.CPSES -UNITS 1 AND 2- ODCM PART 11 E-1 Rev. 32 APPENDIX E (CONTINUED) | ||
2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). | The concentration of tritium in meat is based on its airborne concentration rather than the deposition. | ||
Table 5-1.NOTE: Goat-milk pathway factor, RCc,a,o will be computed using the cow-milk | Therefore RMi is based on (X/Q): Rta,o = k' k"' Ff QF UAP (DFLtao) x 0.75 x (0.5/H),[Eq. | ||
Fm factor for goat-milk will be from Table E-2, R.G. 1.109 QF | E-2]Where: All terms are as defined above and in Appendix D.CPSES -UNITS 1 AND 2- ODCM PART 11 E-2 Rev. 32 APPENDIX E (CONTINUED) | ||
M = | |||
+ x (Ff) x (r) x ( | |||
x e-Xitf [Eq. E-l]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, child,teenager, and adult age groups, respectively (R.G. 1.109)Ff = Stable element transfer coefficients, days/kg (Table E-1, R.G. 1.109)r = Fraction of deposited activity retained in cow's feed grass, 0.2 | |||
YP = Agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2(NUREG-0133) | |||
YS = Agricultural productivity by unit area of stored feed, 2.0 kg/m2(NUREG-0133) fp = 1.0, Fraction of the year that the cow is on | |||
The concentration of tritium in meat is based on its airborne concentration rather than | |||
Therefore RMi is based on (X/Q):Rta,o = k' k"' Ff QF UAP (DFLtao) x 0.75 x (0.5/H),[Eq. | |||
E-2]Where:All terms are as defined above and in Appendix D.CPSES -UNITS 1 AND 2- | |||
The concentration of C-14 in meat is based on the airborne concentration rather than deposition. | The concentration of C-14 in meat is based on the airborne concentration rather than deposition. | ||
Therefore, RMc is based on (X/Q)RMc,a,o k' k"' FfQF UAp DFLc,a,o[0.11/0.16] | Therefore, RMc is based on (X/Q)RMc,a,o k' k"' FfQF UAp DFLc,a,o[0.11/0.16] (p) (f) [Eq. E-3]Where: k' = Units conversion factor pCi/pci (106)k, = Units conversion factor gm/kg (103)Ff = Stable element transfer coefficient (Table E-1, R.G. 1.109)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Consumption rate of cow meat for age group a (kg/yr) (R.G. 1.109)DFLca,o = Ingestion dose conversion factor for C-14, organ o, and age group a, (Tables E-11 to E-14, R.G. 1.109) (mrem/pCi) 0.11 = Fraction of total plant mass consisting of natural carbon (R.G. 1.109)0.16 = Concentration of natural carbon in the atmosphere (gm/m 3) (R.G. 1.109)p = Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is established to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series. 421,"Management of Waste Containing Tritium and Carbon-14", 2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.CPSES -UNITS 1 AND 2- ODCM PART 11 E-3 Rev. 32 APPENDIX F VEGETATION PATHWAY DOSE FACTOR (RVia,o)V L -Xt S X Ri,a,o = k' x [r/ (Yv(oi + kw))] x (DFkIa,0) x [(u A)fL e- i L + U A fg e-ith] [Eq. F-1]Where: k' = 106 picocurie/microcurie (pCi/uCi)UL A = Consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenager, or adult age groups, respectively (R.G. 1.109)usA = Consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively (R.G. 1.109)fL Fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 (NUREG-0133) fg = Fraction of the stored vegetation grown locally .76 (NUREG-0133) tL = Average time between harvest of leafy vegetation and its consumption, 8.6 x 10 4 seconds (Table E-15, R.G. 1.109 (24 hrs))th = 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))Yv = Vegetation areal density, 2.0 kg/m 2 (Table. E-15, 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. | ||
(p) (f) [Eq. E-3]Where:k' = Units conversion factor pCi/pci (106)k, = Units conversion factor gm/kg (103)Ff = Stable element transfer coefficient (Table E-1, R.G. 1.109)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Consumption rate of cow meat for age group a (kg/yr) (R.G. 1.109)DFLca,o = Ingestion dose conversion factor for C-14, organ o, and age group a, ( | |||
2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). | |||
Table 5-1.CPSES -UNITS 1 AND 2- | |||
UL A = Consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant,child, teenager, or adult age groups, respectively (R.G. 1.109)usA = Consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant,child, teenager, or adult age groups respectively (R.G. 1.109)fL Fraction of the annual intake of fresh leafy vegetation grown locally, 1.0(NUREG-0133) fg = Fraction of the stored vegetation grown locally .76 (NUREG-0133) tL = Average time between harvest of leafy vegetation and its consumption, 8.6 x | |||
.5.18 x 106 seconds (Table E-15, R.G. 1.109 (60 days))Yv = Vegetation areal density, 2.0 kg/ | |||
Therefore, RVi is based on (X/Q)Rt,a,o = k' k.' [UA fL + UA fg] (DFLt,a,o) | Therefore, RVi is based on (X/Q)Rt,a,o = k' k.' [UA fL + UA fg] (DFLt,a,o) | ||
(.75 (.5/H)) [Eq. F-2]Where:All terms are as defined above and in Appendix D.CPSES -UNITS 1 AND 2- | (.75 (.5/H)) [Eq. F-2]Where: All terms are as defined above and in Appendix D.CPSES -UNITS 1 AND 2- ODCM PART 11 F-1 Rev. 32 APPENDIX F (CONTINUED) | ||
The concentration of C-14 in vegetation is based on the airborne concentration rather | The concentration of C-14 in vegetation is based on the airborne concentration rather than deposition. | ||
Therefore, RVi is based on (X/Q)RVc,a,o = k' k"' [ULA fL + USAfg] DFLc,a,o | Therefore, RVi is based on (X/Q)RVc,a,o = k' k"' [ULA fL + USAfg] DFLc,a,o [0.11/0.16] (p) (f) [Eq. F-3]Where: k' = Units conversion factor pCi/gci (106)k,. = Units conversion factor gm/kg (103)jL A = Comsumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenage, or adult age groups, respectively (R.G. 1.109) i us A = Consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenage, or adult age groups, respectively (R.G. 1.109) f fL Fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 (NUREG-0133) fg = Fraction of the stored vegetation grown locally .76 (NUREG-0133) | ||
[0.11/0.16] | DFLc,a,o = Ingestion dose conversion factor for C-14, organ o, and age group a, (Tables E-11 to E-14, R.G. 1.109) (mrem/pCi) 0.11 = Fraction of total plant mass consisting of natural carbon (R.G. 1.109)0.16 = Concentration of natural carbon in the atmosphere (gm/m 3) (R.G. 1.109)p = Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is established to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series. 421,"Management of Waste Containing Tritium and Carbon-14", 2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.CPSES -UNITS 1 AND 2- ODCM PART 11 F-2 Rev. 32 APPENDIX G SUPPLEMENTAL GUIDANCE STATEMENTS HAVE BEEN DELETED CPSES -UNITS 1 AND 2- ODCM PART 11 G-1 Rev. 23 CPSES/ODCM COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL (ODCM)EFFECTIVE LISTING FOR SECTIONS, TABLES, AND FIGURES BELOW IS A LEGEND FOR THE EFFECTIVE LISTING OF SECTIONS, TABLES, AND FIGURES: Revision 0 (TXX-89118) | ||
(p) (f) [Eq. F-3]Where:k' = Units conversion factor pCi/gci (106)k,. = Units conversion factor gm/kg (103)jL A = Comsumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant,child, teenage, or adult age groups, respectively (R.G. 1.109) | |||
DFLc,a,o | |||
= Ingestion dose conversion factor for C-14, organ o, and age group a, ( | |||
2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). | |||
Table 5-1.CPSES -UNITS 1 AND 2- | |||
Revision 1 (TXX-89595) | Revision 1 (TXX-89595) | ||
Revision 2 (TXX-8971 1)Revision | Revision 2 (TXX-8971 1)Revision 3 Revision 4 Revision 5 Revision 6 Revision 7 Revision 7A Revision 8 (Unit 2 Operations) | ||
Revision | Revision 9 Revision 10 Revision 11 Revision 12 Revision 13 Revision 14 Revision 15 Revision 16 Revision 17 Revision 18 Revision 19 Revision 20 Revision 21 Revision 22 Revision 23 Revision 24 Revision 25 Revision 26 Revision 27 Revision 28 Revision 29 Revision 30 Revision 31 Revision 32 Revision 33 Submitted to the NRC March 2, 1989 Submitted to the NRC August 25, 1989 Submitted to the NRC November 27, 1989 April 10, 1990 October 9, 1990 December 20, 1990 July 3, 1991 December 4, 1991 August 6, 1992 January 1, 1993 September 28, 1994 April 22, 1994 November 7, 1994 December 8, 1995 February 14, 1996 October 1, 1996 March 3, 1999 July 27, 1999 October 7, 1999 December 20, 1999 October 16, 2001 July 8, 2002 March 23, 2004 December 8, 2004 January 31, 2006 March 13, 2006 June 1, 2006 December 12, 2006 July 24, 2007 September 11, 2008 February 26, 2009 September 1, 2009 April 4, 2011 April 4, 2011 January 31, 2013 Table of Contents Cross-Reference References CPSES/ODCM Revision 32 Revision 23 Revision 31 EL-1 Revision 33 CPSES/ODCM PART I Section 1 Table 1.1 Table 1.2 Section 2 Section 3/4 Bases 3/4 Section 5 Figure 5.1-3 Section 6 PART II Section 1 Table 1.1 Table 1.2 Figure 1.1 Figure 1.2 Figure 1.3 Section 2 Table 2.1 Table 2.2 Table 2.3 Table 2.4 Table 2.5 Figure 2.1 Figure 2.2 Figure 2.3 Figure 2.4 Figure 2.5 Section 3 Table 3.1 Figure 3.1 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G CPSES/ODCM Revision 28 Revision 27 Revision 27 Revision 23 Revision 33 Revision 23 Revision 23 Revision 23 Revision 31 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 33 Revision 26 Revision 23 Revision 32 Revision 32 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 32 Revision 32 Revision 32 Revision 23 EL-2 Revision 33 cPSESIODCM Revision 33 Revision 33 Revision 33 EL-1 EL-2 EL-3 Revisionl 33 EL-3 CpSES/ODCM OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 23 LDCR-OD-2006-2 (CPSES-200600206) (RJK): Revision 23 updates the entire ODCM to reflect the following changes: The electronic files have been converted from Microsoft Word to Adobe Framemaker and published in Adobe Portable Document Format (PDF).The type of changes include changes such as:-Correction of spelling errors-Correction of inadvertent word processing errors from previous changes-Style guide changes (e.g., changing from a numbered bullet list to an alphabetized bullet list and vice versa, change numbering of footnote naming scheme)-Administrative change only and contain no technical changes.This change maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. | ||
(RJK):Revision 23 updates the entire ODCM to reflect the following changes:The electronic files have been converted from Microsoft Word to | The entire ODCM will be reissued as Revision 23. For the text and tables there will be no change bars in the page margins for editorial changes. The list of effective pages is being replaced with a list of effective section, tables, and figure Sections Revised: All Tables Revised: All Figures Revised: All REVISION 24 LDCR-OD-2005-1 (EVAL-2005-003863-02) (GLM): Revision 24 updates ODCM Section 3/4 to reflect the following changes:* Delete the requirement to submit a special report outlining the cause of the malfunction and the plans for restoring the channel(s) to operable status.* Adds the requirement to initiate actions in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical. | ||
The entire ODCM will be reissued as Revision | CPSES/ODCM DOC-1 OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 24 (continued) | ||
LDCR-OD-2005-1 (EVAL-2005-003863-02) (GLM) (continued): | |||
The list | The CPSES Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance. | ||
The minimum set of conditions required by law to be reported to the NRC are contained in the Code Of Federal Regulations (10CFR50.73, 10CFR50.72, 10CFR73, etc.). This ODCM special report is not required by the CFRs, and there is no regulatory basis for this special report. There is no Technical Specification action, regulation, license condition, order, or commitment that requires this ODCM special report. The meteorological monitoring system is governed by Regulatory Guide 1.23, "Onsite Meteorological Programs", and this Regulatory Guide contains no requirement for a special report to the NRC. Based on the above, this ODCM special report is only an administrative requirement and therefore it can be deleted.Sections Revised: 3/4 Tables Revised: None Figures Revised: None REVISION 25 LDCR-OD-2006-3 (EVAL-2006-000932-01) (RJK): Revision 25 updates ODCM Section 3/4 to reflect the following changes: The 7 day allowance for planned and/or scheduled channel maintenance (similar to the TS COMPLETION TIME) was removed in error by Revision 24 of the ODCM (LDCR-OD-2005-01). | |||
That revision intended only to remove the requirement to issue a Special Report to the NRC if the 7 days allowance was exceeded.This LDCR restores an acceptable outage duration for planned and/or scheduled work commensurate with the safety significance of this item.This change also maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. | |||
Sections Revised: 3/4 Tables Revised: None Figures Revised: None CPSES/ODCM DOC-2 OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 26 LDCR-OD-2006-5 (EVAL-2006-002463-01) (RJK): Engineering evaluation ME-CA-0000-5326 assessed the potential gaseous effluent release from a planned decontamination facility on site. The evaluation also provides for operational controls on any similar facility to limit the source term and assess the effluents. | |||
The proposed changes to the ODCM provide the framework to identify, control, and monitor any gaseous effluent pathway. The results of the monitoring are reported in the Radioactive Effluent Release Report, pursuant to ODCM Control 6.9.1.4.LDCR-OD-2006-6 (EVAL-2006-001766-01) (RJK): Revise Action Statement 37 (applicable to WRGM skid iodine and particulate channels)to add "If the number of channels OPERABLE is less than required by the "minimum Channels OPERABLE" requirement due to loss of heat tracing, then declare the Iodine &Particulate samplers INOPERABLE. | |||
(GLM):Revision 24 updates ODCM Section 3/4 to reflect the following changes:* Delete the requirement to submit a special report outlining the cause of | Restore the heat tracing within 7 days and declare the samplers OPERABLE or initiate action in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical." These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2, Type/Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways. | ||
CPSES/ODCM DOC-1 OFFSITE DOSE CALCULATION MANUAL -Description of | This 7 day period for entry into the CPSES Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance. | ||
LDCR-OD-2005-1 (EVAL-2005-003863-02) | REVISION 27 LDCR-OD-2006-1 (EVAL-2005-001822-07) (GLM): Revise definition of DOSE EQUIVALENT IODINE 131 and add new definition for DOSE EQUIVALENT XENON 133.LAR 06-001 revises TS 3.4.16 to eliminate E-bar and adopt DOSE EQUIVALENT XE-1 33 for monitoring RCS gross specific activity. | ||
(GLM) (continued): | |||
The CPSES Corrective Action Program is adequate to track the | |||
The minimum set | |||
and this Regulatory Guide contains no requirement for | |||
3/ | |||
(RJK):Revision 25 updates ODCM Section 3/4 to reflect the following changes:The 7 day allowance for planned and/or scheduled channel maintenance (similar to the TS COMPLETION TIME) was removed in error by | |||
That revision intended only | |||
This LDCR restores an acceptable outage duration for planned and/ | |||
Sections Revised: | |||
3/ | |||
(RJK):Engineering evaluation ME-CA-0000-5326 assessed the potential gaseous | |||
The proposed changes to the ODCM provide the framework to identify, control,and monitor any gaseous effluent pathway. | |||
The results of the monitoring are reported | |||
(RJK):Revise Action Statement 37 (applicable to WRGM skid iodine and particulate channels) to add "If the number of channels OPERABLE is less than required by the " | |||
Restore the heat tracing within 7 days and | |||
These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2,Type/Category E3 variables that provide backup information to estimate magnitude | |||
This 7 day period for entry into | |||
REVISION | |||
(GLM):Revise definition of DOSE EQUIVALENT IODINE 131 and add new definition for | |||
This change makes the ODCM definition consistent with the revised TS definition. | This change makes the ODCM definition consistent with the revised TS definition. | ||
REVISION | REVISION 28 LDCR-OD-2007-1 (EVAL-2006-003080-05) (JDS): Revise Definition of Rated Thermal Power to reflect 4.5% increase on Units 1 and 2 as issued by the NRC in Amendment 146 to the Operating Licenses and Technical Specifications. | ||
(JDS):Revise Definition of Rated Thermal Power to reflect 4.5% increase on Units 1 and 2 | CPSES/ODCM DOG-3 OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 29 LDCR-OD-2007-2 (EVAL-2007-002019-01) (SCD): Revise Table 3.3-8 ACTION and associated statements to clarify necessary actions in the event of a loss of heat tracing or sample lines to the WRGM sampling skid. These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2, Type/Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways. | ||
CPSES/ODCM DOG-3 OFFSITE DOSE CALCULATION MANUAL -Description of | This 7 day period for entry into the CPNPP Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance. | ||
(SCD):Revise Table 3.3-8 ACTION and associated statements to clarify necessary actions in | REVISION 30 LDCR-OD-2009-1 (EVAL-2008-002039-03) (SCD): LDCR OD-2009-001 (tracked by SMF EVAL-2008-002039-03) changes Note 2 of Table 3.12-1 and Note 2 of Table 4.12-1 from thermo luminescent dosimeters (TLDs) to Optically Stimulated Luminescence (OSL) Badges. Also replace "thermoluminescent dosimeter" with "optically stimulated luminescence (OSL) badge" in section 2.5. This change acknowledges the recent switch from TLDs to OSLs.REVISION 31 LDCR-OD-201 1-1 (EV-CR-2010-010410-37) (SCD): Dose limits at the site boundary require monitoring to demonstrate compliance with the limits of 10 CFR 72 as a result of direct radiation exposure emitted by the facility. | ||
This 7 day period for entry into the | The limits for the ISFSI are the same as the existing limits specified by 10 CFR 50 and therefore there are no changes to the monitoring criteria outlined in the ODCM.REVISION 32 LDCR-OD-2010-1 (EV-CR-2010-011250-1) (SCD): Revise the ODCM to incorporate the Carbon-14 isotope dose considerations into the CPNPP Radioactive Effluent Release Report in accordance with the new revision 2 of REGULATORY GUIDE 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste" This change is applicable to units 1 and 2.REVISION 33 LDCR-OD-2012-1 (EV-CR-2012-010400-2) (SCD): Administrative revision change references from OSL (Optically Stimulated Luminescence) to TLD (Thermoluminescent Dosimeter) | ||
REVISION | |||
(SCD):LDCR OD-2009-001 (tracked by SMF EVAL-2008-002039-03) changes Note 2 of | |||
(SCD):Dose limits at the site boundary require monitoring to demonstrate compliance with | |||
(SCD):Revise the ODCM to incorporate the Carbon-14 isotope dose considerations into | |||
(SCD):Administrative revision change references from OSL (Optically Stimulated Luminescence) to TLD (Thermoluminescent Dosimeter) | |||
CPSES/ODCM DOC-4}} | CPSES/ODCM DOC-4}} | ||
Revision as of 14:41, 9 July 2018
| ML14190A281 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/24/2014 |
| From: | Luminant Generation Co, Luminant Power |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CP-2001400443, TXX-14049 | |
| Download: ML14190A281 (180) | |
Text
Enclosure 2 Comanche Peak Offsite Dose Calculation Manual (ODCM)
COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL UNIT 1 AND UNIT2 TABLE OF CONTENTS Number/Title List of Tables List of Figures Cross-Reference to Technical Specifications and REC References Introduction PART I -RADIOLOGICAL EFFLUENT CONTROLS SECTION 1.0 -USE AND APPLICATIONS SECTION 1.1 -DEFINITIONS SECTION 2.0 -NOT USED SECTIONS 3.0 AND 4.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 -Applicability 3/4.3.3.4
-Radioactive Liquid Effluent Monitoring Instrumentation 3/4.3.3.5
-Radioactive Gaseous Effluent Monitoring Instrumentation 3/4.3.3.6
-Meteorological Monitoring Instrumentation 3/4.7.15 -Sealed Source Contamination 3/4.11.1 -Liquid Effluents 3/4.11.1.1
-Concentration Controls 3/4.11.1.2
-Dose 3/4.11.1.3
-Liquid Radwaste Treatment System 3/4.11.1.4
-LVW Pond Resin Inventory 3/4.11.2 -Gaseous Effluents 3/4.11.2.1
-Dose Rate 3/4.11.2.2
-Dose -Noble Gases 3/4.11.2.3
-Dose -Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form 3/4.11.2.4
-Gaseous Radwaste Treatment System 3/4.11.4 -Total Dose 3/4.12.1 -Radiological Environmental Monitoring Program Paqe v vi vii x XI xi 11-0 11-1 I 2-0 I 3/4-0 I 3/4-1 I 3/4-2 I 3/4-8 I 3/4-14 I3/4-16 I3/4-18 13/4-18 13/4-23 13/4-24 13/4-25 13/4-27 I3/4-27 13/4-31 13/4-32 I 3/4-33 I 3/4-34 I 3/4-35 CPSES -UNITS 1 AND 2- ODCM Rev. 32 TABLE OF CONTENTS (continued)
Number/Title Page 3/4.12.2 -Land Use Census I 3/4-46 3/4.12.3 -Interlaboratory Comparison I 3/4-47 Program BASES I B 3/4-0 SECTION 5.0 -DESIGN FEATURES I 5-0 5.1.3 -Map Defining Controlled Areas, I 5-1 Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents SECTION 6.0 -ADMINISTRATIVE CONTROLS I 6-0 6.9.1.3 -Annual Radiological Environmental I 6-1 Operating Report 6.9.1.4 -Radioactive Effluent Release Report I 6-2 6.14 -Offsite Dose Calculation Manual I 6-3 (ODCM)PART II -CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS I1-1 1.1 10CFR20 and Radiological Effluent Control I1-1 3/4.11.1.1 Compliance 1.1.1 Isotopic Concentration of the 111-2 Waste Tank 1.1.2 Effluent Flow Rate (f) 111-2 1.1.3 Dilution of Liquid Effluents 11 1-3 1.1.4 Actual Dilution Factor (ADF) 111-4 1.1.5 Required Dilution Factor (RDF) 111-4 1.1.6 10CFR20 Compliance 111-5 1.2 Radiation Monitor Alarm Setpoints 111-5 1.2.1 Primary Liquid Effluent Monitor Il1-5 (XRE-5253) 1.2.2 Turbine Building Sump Effluent 111-6 Radiation Monitors (1RE-5100 and 2RE-51 00)1.2.3 Station Service Water Effluent Radiation 111-7 Monitors (1 RE-4269/4270 and 2RE-4269/4270)
CPSES -UNITS 1 AND 2- ODCM ii Rev. 32 TABLE OF CONTENTS (continued)
Number/Title Paqe 1.2.4 Auxiliary Building to LVW Pond 111-8 Radiation Monitor (XRE-5251A) 1.3 Dose Calculations for Liquid Effluents 111-8 1.3.1 Calculation of Dose Due to 111-9 Liquid Releases 1.3.2 Calculation of Dose Due to 111-10 Radionuclide Buildup in the Lake 1.4 Dose Projections for Liquid Effluents 11 1-12 1.5 Definitions of Common Liquid Effluent 111-12 Parameters 2.0 GASEOUS EFFLUENTS II 2-1 2.1 Radiological Effluent Control 112-2 3/4.11.2.1 Compliance 2.1.1 Dose Rates Due to Noble Gases 112-2 2.1.2 Dose Rates Due to Radioiodines, 112-4 Tritium, and Particulates 2.2 Gaseous Effluent Monitor Setpoints 112-4 2.2.1 Plant Vent Effluent Release Rate 112-5 Monitors (XRE-5570A/XRE-5570B)
Effluent Release Rate Channels 2.2.2 Plant Vent Stack Noble Gas Activity II 2-6 Monitors (XRE-5570A/XRE-5570B and XRE-5567A/XRE-5567B) 2.2.3 Sampler Flow Rate Monitors II 2-6 (X-RFT-5570A-1/X-RFT-5570B-1) 2.2.4 Auxiliary Building Ventilation II 2-6 Exhaust Monitor (XRE-5701) 2.2.5 Containment Atmosphere Gaseous II 2-7 Monitors (1 RE-5503/2RE-5503) 2.3 Dose Calculations for Gaseous Effluents 112-8 2.3.1 Dose Due to Noble Gases 112-8 2.3.2 Dose Due to Radioiodines, Tritium, C-14, II 2-9 and Particulates 2.4 Dose Projections for Gaseous Effluents II 2-11 2.5 Dose Calculations to Support Other II 2-11 Requirements CPSES -UNITS 1 AND 2- ODCM iii Rev. 32 TABLE OF CONTENTS (continued)
Number/Title 2.6 Meteorological Model 2.6.1 Dispersion Calculations 2.6.2 Deposition Calculations 2.7 Definitions of Gaseous Effluents Parameters 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 Sampling Locations 3.2 Interlaboratory Comparison Program APPENDICES A. Pathway Dose Rate Parameter B. Inhalation Pathway Dose Factor C. Ground Plane Pathway Dose Factor D. Grass-Cow-Milk Pathway Dose Factor E. Cow-Meat Pathway Dose Factor F. Vegetation Pathway Dose Factor G. Supplemental Guidance Statements
-Deleted Paqe 112-12 II 2-12 II 2-14 II 2-14 II 3-1 II 3-1 II 3-1 A-1 B-1 C-1 D-1 E-1 F-1 G-1 CPSES -UNITS 1 AND 2- ODCM iv Rev. 32 TABLE OF CONTENTS LIST OF TABLES Table No. Title Page PART I -RADIOLOGICAL EFFLUENT CONTROLS 1.1 ODCM Frequency Notation 11-5 1.2 Deleted. 11-6 3.3-7 Radioactive Liquid Effluent Monitoring Instrumentation I 3/4-3 4.3-3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements I 3/4-6 3.3-8 Radioactive Gaseous Effluent Monitoring Instrumentation I 3/4-9 4.3-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 13/4-12 3.3-9 Meteorological Monitoring Instrumentation I 3/4-15 4.11-1 Radioactive Liquid Waste Sampling And Analysis Program I 3/4-19 4.11-2 Radioactive Gaseous Waste Sampling and Analysis Program I 3/4-28 3.12-1 Radiological Environmental Monitoring Program 13/4-37 3.12-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples I 3/4-43 4.12-1 Detection Capabilities For Environmental Sample Analysis LLDs I 3/4-44 PART II -CALCULATIONAL METHODOLOGIES 1.1 Summary of Liquid Release Pathways 111-15 1.2 Site Related Ingestion Dose Commitment Factor Air 111-16 2.1 Summary of Gaseous Release Pathways II 2-18 2.2 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases II 2-19 2.3 Pathway Dose Rate Parameter (Pi) Il 2-20 2.4 Pathway Dose Factors II 2-21 2.5 Controlling Receptor Pathways and Locations, and Atmospheric Dispersion Parameters (for Dose Calculations Required by Radiological Effluent Control 3/4.11.2.3)
II 2-42 3.1 Environmental Sampling Locations II 3-2 CPSES -UNITS 1 AND 2- ODCM V Rev. 27 TABLE OF CONTENTS LIST OF FIGURES Figure Title Page PART I -RADIOLOGICAL EFFLUENT CONTROLS 5.1-3 Controlled Area, Unrestricted Area and Site Boundary for Radioactive Gaseous and Liquid Effluents I 5-2 PART II -CALCULATIONAL METHODOLOGIES 1.1 Liquid Effluent Discharge Pathways 11 1-20 1.2 Circulating Water Pump Curves 11 1-21 1.3 Energy Response to Gamma Radiations for RD-33 Type Detector 11 1-22 2.1 Gaseous Waste Processing System II 2-43 2.2 Plume Depletion Effect for Ground-Level Releases II 2-44 2.3 Vertical Standard Deviation of Material in a Plume II 2-45 2.4 Relative Deposition for Ground-Level Releases II 2-46 2.5 Open Terrain Correction Factor II 2-47 3.1 Radiological Environmental Monitioring Locations II 3-3 CPSES -UNITS 1 AND 2- ODCM vi Rev. 27 CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC Number or Document Section Requirement ODCM Section PART I-RADIOLOGICAL EFFLUENT CONTROLS (REC)Tech Spec 4.1 Site Location/Map 5.1.3 and Fig. 5.1-3 Tech Spec 5.5.1 Offsite Dose Calculation Manual 6.14 (ODCM)Tech Spec 5.5.4.a Effluent monitoring instrumentation 3/4.3.3.4 and operability, surveillance, and 3/4.3.3.5 setpoint requirements Tech Spec 5.5.4.b Limit liquid effluent concentration 3/4.11.1.1 Tech Spec 5.5.4.c Effluent monitoring, sampling, and 3/4.11.1.1 and analysis requirements 3/4.11.2.1 Tech Spec 5.5.4.d Limit doses due to liquid effluents 3/4.11.1.2 Tech Spec 5.5.4.e Determine cumulative and projected 3/4.11.1.2, doses due to radioactive effluents 3/4.11.2.2.
Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec Tech Spec REC REC 5.5.4.f 5.5.4.g 5.5.4.h 5.5.4.i 5.5.4.j 5.6.2 5.6.3 PART II -3/4.11.1.1 3/4.11.1.2 Effluent treatment systems operability requirements Limit gaseous effluent dose rate Limit noble gas air dose Limit gaseous effluent iodine and particulate dose Limit total dose Annual Radiological Environmental Operating Report Radioactive Effluent Release Report CALCULATIONAL METHODOLOGIES 3/4.11.2.3 3/4.11.1.3 and 3/4.11.2.4 3/4.11.1.3 and 3/4.11.2.4 3/4.11.2.1 3/4.11.2.2 3/4.11.2.3 3/4.11.4 6.9.1.3 6.9.1.4 1.1 1.3 Liquid effluent concentration Dose due to liquid effluents CPSES -UNITS 1 AND 2- ODCM vii Rev. 23 CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC (continued)
Document REC REC REC Number or Section 3/4.11.1.3 3/4.11.2.1.a 3/4.11.2.1 .b Requirement Dose projections for liquid releases Dose rate due to noble gases Dose rate due to iodine, tritium, and particulates with half-lives greater than eight days Air dose due to noble gases Doses due to iodine, tritium, and particulates with half-lives greater than eight days Dose projections for gaseous releases ODCM Section 1.4 2.1.1 2.1.2 2.3.1 2.3.2 2.4 REC REC 3/4.11.2.2 3/4.11.2.3 REC REC REC REC 3/4.11.2.4 3/4.11.4 3/4.12.1 3/4.12.2 REC REC 3/4.12.3 3.3.3.4 Total dose due to releases of radioactivity and direct radiation Description of radiological environmental sampling locations Dose calculations for identifying changes to environmental sampling locations Description of the Interlaboratory Comparison Program Radioactive liquid effluent monitoring channels alarm/trip setpoints* liquid waste monitor (XRE-5253)
- turbine building sump monitors (1 RE-51 00 and 2RE-51 00)* service water monitors (1 RE-4269/4270 and 2RE-4269/4270)
- auxiliary building to LVW Pond radiation monitor (XRE-5251A) 2.5 3.1 2.5 3.2 1.2.1 1.2.2 1.2.3 1.2.4 CPSES -UNITS 1 AND 2- ODCM viii Rev. 23 CROSS-REFERENCE TO TECHNICAL SPECIFICATIONS AND REC (continued)
Number or Section Document Requirement ODCM Section REC 3.3.3.5 Radioactive gaseous effluent monitoring channels alarm/trip setpoints" noble gas release rate monitors XRE-5570A and XRE-5570B (WGRM release rate channels)" noble gas activity monitors XRE-5570A and XRE-5570B (WRGM low range activity channel) XRE-5567A and XRE-5567B (noble gas channel)" waste gas holdup system monitor (auxiliary building vent monitor) XRE-5701* sampler flow rate monitor XFT-5570A2/B2 Radiation monitoring channels alarm/trip setpoint Containment atmosphere gaseous monitors (containment vent monitors) 1 RE-5503 and 2RE-5503 2.2.1 2.2.2 2.2.4 2.2.3 Tech Spec 3.3.6 2.2.5 Tech Spec REC Tech Spec REC Tech Spec REC 5.6.3 6.9.1.4 5.6.3 6.9.1.4 5.6.3 6.9.1.4 Assessment of radiation doses due 2.5 to liquid and gaseous effluents released during the previous year Assessment of doses to members of the public inside the site boundary Assessment of doses to the most likely exposed member of the public from reactor releases and direct radiation 2.5 2.5 CPSES -UNITS 1 AND 2- ODCM ix Rev. 23 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," TU Electric, Comanche Peak Steam Electric Station.4. "Final Safety Analysis Report," TU Electric, Comanche Peak Steam Electric Station.5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976).6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111, Rev. 1 (July 1977).7. Meteorology and Atomic Energy; Edited by Slade, D. H.; U. S. Department of Commerce (July 1968).8. "Technical Specifications," TU Electric, Comanche Peak Steam Electric Station.9. Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01), USNRC, January 31, 1989.10. CPSES Technical Evaluation No. RP-90-3077, "Calculation of Site Related Ingestion Dose Commitment Factors For Sb-122." 11. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," USNRC Regulatory Guide 1.109 (March 1976).12. Code of Federal Regulation, Title 10, Parts 20, 50, and 72.CPSES -UNITS 1 AND 2- ODCM X Rev. 31 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the CPSES Technical Specifications.
Part I of the ODCM contains (1) the Radioactive Effluent Controls required by Technical Specification 5.5.4, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3, (3) Controls for Meteorological Monitoring Instrumentation and Sealed Source Leakage, and (4) Radiological Environmental Monitoring Controls.
Part II of the ODCM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.
Liquid and Gaseous Radwaste Treatment System configurations are shown in Part II, Figures 1.1 and 2.1.The ODCM is maintained for use as a reference guide and training document on accepted methodologies and calculations.
Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. TXU Power initiated changes to the ODCM will be implemented in accordance with Section 5.5.1 of the Technical Specifications.
The ODCM follows the methodology and models suggested by NUREG-0133 (Ref. 1) and Regulatory Guide 1.109, Revision 1 (Ref. 2). Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementing the Radiological Effluent Control requirements.
This simplified approach will result in a more conservative dose evaluation, but requires the least amount of time for establishing compliance with regulatory requirements.
This manual is designed to provide necessary information in order to simplify the dose calculations.
The dose calculations can be optionally expanded to several levels of effort. The complexity of the dose calculations can be expanded by several levels of effort, aiming toward a full calculation in accordance with Regulatory Guide 1.109. Future changes to the 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 (Radioactive Effluent Release Report) requirements is to use a computerized system to determine the effluent releases and update cumulative doses.CPSES -UNITS 1 AND 2- ODCM xi Rev. 23 PART I RADIOLOGICAL EFFLUENT CONTROLS CPSES -UNITS 1 AND 2- ODCM SECTION 1.0 USE AND APPLICATIONS CPSES -UNITS 1 AND 2- ODCM PART 1 1-0 Rev. 28 1.0 USE AND APPLICATIONS
1.1 DEFINITIONS
The defined terms of this section appear in capitalized type and are applicable throughout these Controls.ACTION ACTION shall be that part of a Control that prescribes required actions to be taken under designated conditions within specified completion times.ANALOG CHANNEL OPERATIONAL TEST 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 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping or total channel steps.CHANNEL CHECK 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 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.
DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same does when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or from Table E-7 of CPSES -UNITS 1 AND 2- ODCM PART I11-1 Rev. 28 DEFINITIONS Regulatory Guide 1.109, Revision 1, NRC, 1977, or from ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity.
The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil", or using the dose conversion factors from Table B-1 of Regulatory Guide 1.109, Revision 1, NRC, 1977.FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.MEMBER(S)
OF THE PUBLIC MEMBER(S)
OF THE PUBLIC means an individual in a CONTROLLED or UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 5.5.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3, respectively.
OPERABLE -OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
CPSES -UNITS 1 AND 2- ODCM PART 1 1-2 Rev. 28 DEFINITIONS PRIMARY PLANT VENTILATION SYSTEM A PRIMARY PLANT VENTILATION SYSTEM shall be any system designed and installed to reduce gaseous radioiodine 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 particulates from the gaseous exhaust stream prior to the release to the environment.
Such a system is not considered to have any effect on noble gas effluents.
PURGE -PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3458 MWt through Cycle 13 for Unit I and through Cycle 11 for Unit 2. Starting with Cycles 14 and 12 of Units 1 and 2, respectively, RTP shall be 3612 MWt.REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 1 OCFR50.73.
SITE BOUNDARY The SITE BOUNDARY shall be that line as shown in Figure 5.1-3.SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.UNRESTRICTED AREA An UNRESTRICTED AREA means any area beyond the SITE BOUNDARY.VENTING 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.CPSES -UNITS 1 AND 2- ODCM PART 1 1-3 Rev. 28 DEFINITIONS WASTE GAS HOLDUP SYSTEM 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 the purpose of reducing the total radioactivity prior to release to the environment.
CONTROLLED AREA A CONTROLLED AREA means an area outside of a restricted area, as defined in 10 CFR 20.1003, but inside the SITE BOUNDARY, access to which can be limited by the licensee for any reason.CPSES -UNITS 1 AND 2- ODCM PART 1 1-4 Rev. 28 TABLE 1.1 ODCM FREQUENCY NOTATION NOTATION S D w M Q SA SR R S/U N.A.P FREQUENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.At least once per 7 days.At least once per 31 days At least once per 92 days.At least once per 184 days.At least once per 9 months.At least once per 18 months.Prior to each reactor startup.Not applicable.
Completed prior to each release.CPSES -UNITS 1 AND 2- ODCM PART I11-5 Rev. 27 TABLE 1.2 This Table is Deleted.CPSES -UNITS 1 AND 2 -ODCM PART 1 1-6 Rev. 27 SECTION 2.ONOT USED CPSES -UNITS 1 AND 2 -ODCM PART 1 2-0 Rev. 23 SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS CPSES -UNITS 1 AND 2- ODCM PART I13/4-0 Rev. 33 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY The guidance provided for the use and application of LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY in Section 3.0, "LIMITING CONDITION FOR OPERATION (LCO)APPLICABILITY" of the Technical Specifications is applicable to the Controls contained in this manual, except as noted below.The guidance provided for the use and application of SURVEILLANCE REQUIREMENT (SR)APPLICABILITY in Section 3.0, "SURVEILLANCE REQUIREMENT (SR) APPLICABILITY" of the Technical Specifications is applicable to the Surveillance Requirements contained in this manual.For the purpose of the ODCM, the ODCM terms specified below should be considered synonymous with the listed Technical Specification term: ODCM Control ACTION Technical Specification LCO Required Action A cross reference between Section 3/4.0 of the Offsite Dose Calculation Manual (ODCM) and the applicable Section 3.0 of the Technical Specifications is as follows: ODCM Control: 3.0.1 Technical Specification Section LCO 3.0.1 3.0.2 N/A (see Note 1)N/A (see Note 1)N/A (see Note 1)N/A (see Note 1)N/A (see Note 1)ODCM Surveillance Requirement:
LCO 3.0.2 LCO 3.0.3 LCO 3.0.4 LCO 3.0.5 LCO 3.0.6 LCO 3.0.7 Technical Specification Section 4.0.1 4.0.2 SR 3.0.1 SR 3.0.2 SR 3.0.3 SR 3.0.4 4.0.3 N/A (see Note 1)-NOTE 1 -The provisions of the cross referenced Technical Specification LCO/SR are not pertinent for use in the ODCM; therefore, the Technical Specification LCO/SR is not applicable (N/A).CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-1 Rev. 33 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.4 In accordance with CPSES TS 5.5.4.a, 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 Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).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 Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.SURVEILLANCE REQUIREMENTS 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.CPSES -UNITS 1 AND 2- ODCM PART I13/4-2 Rev. 33 TABLE 3.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE INSTRUMENT
- 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluent Line (XRE-5253)
- b. Turbine Building (Floor Drains) Sumps Effluent Lines (IRE-5100
& 2RE-5100)c. Auxiliary Building to LVW Pond Liquid Effluent Line (XRE-5251A)
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a. Service Water System Effluent Lines (1RE-4269, IRE-4270, 2RE-4269 & 2RE-4270)3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line (XFT-5288)
ACTION 1 1/sump i 1/train 1 30 31 31A 32 33 CPSES -UNITS 1 AND 2- ODCM PART I13/4-3 Rev. 33 TABLE 3.3-7 (Continued)
ACTIONS STATEMENTS ACTION 30- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a 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 OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/mi:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram DOSE EQUIVALENT 1-131;or b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram DOSE EQUIVALENT 1-131. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)
ACTION 31A- With number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters at a lower-limit of detection of no more than 5 x 10-7 microCurie/ml at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.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 (uRE-4509, uRE-4510,&uRE-451 1)* OPERABLE and indicating an activity of less than 1X10-4 micro Curie/ml, a grab sample is collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml at least every 31 days; or* "u" designates monitor for the applicable unit, e.g., 1 or 2.CPSES -UNITS 1 AND 2- ODCM PART13/4-4 Rev. 33 TABLE 3.3-7 (Continued)
ACTIONS STATEMENTS (Continued)
- b. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters at a lower limit of detection of no more than 5 x 10-7 microCurie/ml. (Refer to Notation 3 of Table 4.11-1 for the applicability of the LLD requirement.)
NOTE: Collection of grab samples is not required when there is no process flow at the monitor.ACTION 33- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases Via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.CPSES -UNITS 1 AND 2- ODCM PART 13/4-5 Rev. 33 TABLE 4.3-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG DIGITAL CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluent Line (XRE-5253)
D P R(4) N.A. Q(1)b. Turbine Building (Floor Drains) Sumps Effluent Lines (1 RE-5100 & 2RE-51 00) D M R(4) N.A. Q(2)c. Auxiliary Building to LVW Pond Liquid Effluent Line (XRE-5251 A) D M R(4) N.A. Q(2)2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a. Service Water System Effluent Lines (1RE-4269, IRE-4270, 2RE-4269 &2RE-4270)
D M R(4) N.A. Q(3)3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line (XFT-5288)
D(5) N.A. R Q N.A.CPSES -UNITS I AND 2- ODCM PART I13/4-6 Rev. 33 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, or Check Source Failure).(3) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the Alarm Setpoint; or b. Circuit failure (Channel Out of Service -Loss of Power, Loss of Counts, Loss of Sample Flow, or Check Source Failure).(4) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.(5) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.CPSES -UNITS 1 AND 2- ODCM PART I13/4-7 Rev. 33 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.5 In accordance with CPSES TS 5.5.4.a, 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 Part II of 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 inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8.Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected in a timely manner.SURVEILLANCE REQUIREMENTS 4.3.3.5 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST or ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.CPSES -UNITS 1 AND 2- ODCM PART I13/4-8 Rev. 33 TABLE 3.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT' OPERABLE APPLICABILITY ACTION 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Release Rate Monitor -Providing Alarm and Automatic Termination of Release[XRE-5570A
& XRE-5570B (effluent release rate channel)]
1/stack ** 34 2. PRIMARY PLANT VENTILATION
- a. Noble Gas Release Rate Monitor[XRE-5570A
& XRE-5570B (effluent release rate channel)]
1/stack 36 b. Iodine Sampler (WRGM sample skid) 1/stack 37 c. Particulate Sampler (WRGM sample skid) 1/stack 37 d. Sampler Flow Rate Monitor SMPL Flow I (X-RFT-5570A-1, X-RFT-5570B-1) 1/stack 35 CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-9 Rev. 33 TABLE 3.3-8 (Continued)
TABLE NOTATIONS* At all times.** During Batch Radioactive Releases via this pathway.ACTION 34-ACTION 35-ACTION 36-With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: a. The auxiliary building vent duct monitor (XRE-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.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the sample flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.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-5570B (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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or b. The Plant Vent Flow Monitor, PROC FLOW N (X-FT-5570A-1, X-FT-5570B-1), is OPERABLE, and an alternate Plant Vent Noble Gas Activity Monitor is OPERABLE (XRE-5567A, XRE-5567B) or grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or c. The plant vent flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or d. if the number of channels OPERABLE is less than required by the"Minimum Channels OPERABLE" requirement due to loss of sample line, effluent releases via this pathway may continue for no more than 7 days, provided monitors on the other stack are OPERABLE and actions are initiated in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical.
CPSES- UNITS 1 AND 2- ODCM PART I13/4-10 Rev. 33 TABLE 3.3-8 (Continued)
TABLE NOTATIONS 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 that: a. samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2, or b. if the number of channels OPERABLE is less than required by the'minimum Channels OPERABLE" requirement due to loss of heat tracing, then declare the Iodine & Particulate samplers INOPERABLE.
Restore the heat tracing within 7 days and declare the samplers OPERABLE or initiate action in accordance with the Corrective Action Program to restore the channel(s) to OPERABLE status as soon as practical; or c. if the number of channels OPERABLE is less than required by the"Minimum Channels OPERABLE" requirement due to loss of sample line, effluent releases via the affected pathway may continue for no more than 7 days, provided monitors on the other stack are OPERABLE and actions are initiated in accordance with the Corrective Action Program to restore the channel(s) to OPERABLE status as soon as practical.
CPSES -UNITS 1 AND 2- ODCM P 3 PART I13/4-11 Rev. 33 TABLE 4.3-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL OPERATIONAL TEST DIGITAL CHANNEL OPERATIONAL TEST CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION INSTRUMENT
- 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Release Rate Monitor Providing Alarm and Automatic Termination of Release[XRE-5570A, XRE-5570B (effluent release rate channel)]2. PRIMARY PLANT VENTILATION
- a. Noble Gas Release Rate Monitor[XRE-5570A, XRE-5570B (effluent release rate channel)]b. Iodine Sampler (WRGM sample skid)c. Particulate Sampler (WRGM Sample Skid)d. Sampler Flow Rate Monitor SMPL Flow 1 (X-RFT-5570A-1, X-RFT-5570B-1)
P P R(3)N.A.Q(1)D W(4)W(4)D R(3)N.A.N.A.N.A.N.A.N.A.R N.A.N.A.N.A.Q Q(2)N.A.N.A.N.A.CPSES -UNITS 1 AND 2- ODCM PART I13/4-12 Rev. 33 TABLE 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 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 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).(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration, reference standards certified by NIST, or standards that have been obtained from suppliers that participate in measurement assurance activities with NIST shall be used.(4) The CHANNEL CHECK shall consist of visually verifying that the collection element (i.e., filter or cartridge.
etc.) is in place for sampling.CPSES -UNITS 1 AND 2- ODCM PART I13/4-13 Rev. 33 INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION CONTROLS 3.3.3.6 The meteorological monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE.APPLICABILITY:
At all times.ACTION: a. With less than the minimum number of meteorological monitoring instrumentation channels OPERABLE for more than 7 days, initiate action in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical.
SURVEILLANCE REQUIREMENTS 4.3.3.6 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE: a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by performance of a CHANNEL CHECK; and b. At least once per 184 days by performance of a CHANNEL CALIBRATION except the wind speed and wind direction sensors which are replaced with calibrated sensors at least once per 12 months.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-14 Rev. 33 TABLE 3.3-9 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT CHANNEL 1. WIND SPEED a. X-S-4117 b. X-S-4118 c. X-S-4128*2. WIND DIRECTION a. X-Z-4115 b. X-Z-4116 c. X-Z-4126*3. AIR TEMPERATURE
-AT a. X-T-4119 b. X-T-4120 LOCATION MINIMUM OPERABLE 1 of 3 Nominal Elev. 60 m.Nominal Elev. 10 m.Nominal Elev. 10 m.1 of 3 Nominal Elev. 60 m Nominal Elev. 10 m.Nominal Elev. 10 m.1 of 2 Nominal Elev. 60 m. and Nominal Elev. 10 m.Nominal Elev. 60 m. and Nominal Elev. 10 m.* Mounted on backup tower.CPSES- UNITS 1 AND 2- ODCM PART 1 3/4-15 Rev. 33 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: 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 REQUIREMENTS 4.7.15.1 Test Requirements
-Each sealed source shall be tested for leakage and/or contamination by: a. The licensee; or b. Other persons specifically authorized by the Commission or an Agreement State.The test method shall have a detection sensitivity of at least 0.005 microCurie per test sample.4.7.15.2 Test Frequencies
-Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.a. Sources in use -At least once per 6 months for all sealed sources containing radioactive materials:
- 1) With a half-life greater than 30 days (excluding Hydrogen 3), and 2) In any form other than gas.b. Stored sources not in use -Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-16 Rev. 33 SURVEILLANCE REQUIREMENTS (Continued)
- c. Startup sources and fission detectors
-Each sealed startup source and fission detector shall be tested prior to installation or within 31 days prior to being subjected to core flux and following repair or maintenance to the source.4.7.15.3 Reports- A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microCurie of removable contamination.
CPSES -UNITS 1 AND 2 -ODCM PART I13/4-17 Rev. 33 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with CPSES TS 5.5.4.b and 5.5.4.c the concentration of radioactive material released in liquid effluents from the site to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microCurie/ml total activity.APPLICABILITY:
At all times.ACTION: a. With the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Part II of the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.CPSES -UNITS 1 AND 2- ODCM PART I13/4-18 Rev. 33 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION0 1)TYPE FREQUENCY FREQUENCY ANALYSIS (p.Ci/ml)1A. Batch Waste Release (2) P P Principal Gamma 5.OE-07 Tanks to the Circulating Each Batch Each Batch Emitters (3)Water Discharge 1-131 1.OE-06 a. Waste Monitor Tanks Dissolved
& Ete1.E-05 b. Laundry Holdup& Gases (Gamma Emitters)Monitor Tanks M H-3 1.0E-05 c. Waste Water Composite (4) Gross Alpha 1.0E-07 Holdup Tanks (8) Q Sr-89, Sr-90 5.OE-08 d. Plant Effluent Composite (4) Fe-55 1.0E-06 Tanks lB. Batch Waste Release (2) P P Principal Gamma 5.OE-07 Tanks to the Waste Water Each Batch Each Batch Emitters (3)Management System a. Condensate Polisher 1-131 1.OE-06 Backwash Recovery Tanks (6,7)b. Waste Water H-3 1.OE-05 Holdup Tanks (6,8)c. Temporary holdup tanks (10)2A. Continuous Release(5) to Monthly Monthly Dissolved
& Entrained (3) (11)the Circulating Water Grab (11) Grab (11) Gases (Gamma Emitters)Discharge Daily Grab Composite over Principal Gamma 5.0E.07(11)
- a. Low Volume Sample (9) pond discharge Emitters (3)Waste Pond plriod (43 Effluents period (4) 1-131 1.0E-06 H-3 1.OE-05 Gross Alpha 1.OE-07 Q Sr-89, Sr-90. 5.OE-08 Composite (4) Fe-55 1.OE-06 2B. Continuous Releases (5)to W W Principal Gamma 5.OE-07 the Waste Water Grab Sample Emitters (3)Management System a. Turbine Bldg.Sump No. 2 1-131 1.OE-.06 Effluents (6,7)b. Turbine Bldg.Sump No. 4 Effluents (6,7) H-3 1.OE-05 c. Auxiliary Bldg.Secondary Effluents (6,7)CPSES- UNITS 1 AND 2- ODCM PART I13/4-19 Rev. 33 TABLE 4.11-1 (Continued)
TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
LLD = 4"66Sb E*V°2.22x 106 e Y
- exp (-XAt)Where: LLD = "A priori" lower limit of detection (microCurie per unit mass or volume), sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = Counting efficiency (counts per disintegration), V = Sample size (units of mass or volume), 2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, X = Radioactive decay constant for the particular radionuclide (sec-1), and At = 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.
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.
(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in Part II of the ODCM to assure representative sampling.(3) The principal gamma emitters 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, and Ce-141 for fission and corrosion products, and Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-138 for dissolved or entrained gases. Ce-144 shall also be measured, but with an LLD of 5 x 10-6. This list does not mean that only these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-20 Rev. 33 TABLE 4.11-1 (Continued)
TABLE NOTATIONS (Continued) also be analyzed and reported in the 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 representative of the liquids released.(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.(6) These waste streams shall be sampled and analyzed, in accordance with this table, if radioactive material is detected in the LVW Pond composite samples in concentrations that exceed 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2. This sampling shall continue until 2 consecutive samples from the waste stream show that the concentration of radioactive materials in the waste stream is less than or equal to 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2.(7) All flow from these waste streams shall be diverted to the Waste Water Holdup Tanks if activity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Sampling and analysis of the respective Tanks or sumps are not required when flow is diverted to the Waste Water Holdup Tanks.(8) Waste Water Holdup Tanks (WWHT) shall be discharged directly to the Circulating Water Discharge Tunnel when results of sample analyses indicate activity in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Otherwise, WWHTs may be discharged to the Low Volume Waste Pond. WWHT discharges to the Circulating Water Discharge Tunnel shall be sampled and analyzed per Item 1A.c of this table. WWHT discharges to the LVW Pond shall be sampled and analyzed per Item 1 B.b of this table.(9) Samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the release is occurring.
To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.(10) Temporary holdup tanks used to support special plant activities (e.g., Steam Generator Secondary Cleaning) involving potentially radioactive systems may be transferred to the Waste Water Management System when sampled in accordance with this table and the special plant activity has been evaluated in accordance with the 50.59 process. This waste stream shall not be discharged to the Waste Water Management System if activity is present in the waste stream in concentrations that exceed 10 times the limits of 10CFR20, Appendix B, Table 2, Column 2.(11) Dissolved and entrained gases should be included in the analysis (including Kr-87, Kr-88, Xe-133, Xe-1 33m, Xe-1 35, and Xe-138). There are no LLD requirements for these gases in the LVW samples since the half life of the isotopes are relatively short with respect to the sample counting frequency.
Gases are also not expected to be found in the LVW due CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-21 Rev. 33 TABLE 4.11-1 (Continued)
TABLE NOTATIONS (Continued) to delay times associated with water being transported to the LVW and the open exposure of the ponds which would aid in the degasification of the liquids. One sample should be obtained monthly from the Low Volume Waste in addition to the composite sample to analyze for these noble gases. The count time for the sample should be equal to the time required to establish LLD values for the noble gas isotopes (e.g., 2000 seconds or the same count time used for effluent liquid batch releases).
CPSES -UNITS 1 AND 2- ODCM PART I13/4-22 Rev. 33 RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with CPSES TS 5.5.4.d and 5.5.4.e the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to CONTROLLED AREAS and UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ; and b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.APPLICABILITY:
At all times.ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit a report to the Commission within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This 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.SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative-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 Part II of the ODCM at least once per 31 days.CPSES -.UNITS 1 AND 2- ODCM PART 1 3/4-23 Rev. 33 RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with CPSES TS 5.5.4.f, the Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to CONTROLLED AREAS and 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 a report to the Commission within 30 days, pursuant to 10 CFR 50, Appendix I, 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, 2) Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3) Summary description of action(s) taken to prevent a recurrence.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to CONTROLLED AREAS and UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.CPSES -UNITS 1 AND 2- ODCM PART I13/4-24 Rev. 33 RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY CONTROLS 3.11.1.4 The quantity of radioactive material contained in resins transferred to the LVW Pond shall be limited by the following expression:
264 IA<v j c, excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life, where: Aj = Pond inventory limit for single radionuclide "j" (Curies), Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j" (microCuries/ml), V = Volume of resins in the pond (gallons), and 264 = Unit conversion factor (microCuries/Curie per millilitertgallon).
APPLICABILITY:
At all times.ACTION: a. With the quantity of radioactive material contained in resins in the LVW Pond exceeding the above limit, immediately suspend all additions of resins to the pond.SURVEILLANCE REQUIREMENTS 4.11.1.4 Prior to transferring any batch of used powdex resin to the pond, the total inventory of radioactive materials in resins contained in the pond, including the batch to be transferred, shall be determined to be within the above limit. The inventory shall be determined based on analysis of a representative sample of the resin batch. Decay of radionuclides in previously discharged resins may be taken into account in determining inventory levels.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-25 Rev. 33 RADIOACTIVE EFFLUENTS LVW POND RESIN INVENTORY SURVEILLANCE REQUIREMENTS (Continued)
Additionally, each batch of resins transferred to the pond shall be limited by the expression:
7.J Qj-where: Qj Concentration of radioactive materials (microCuries/ml) in wet, drained slurry (used powdex resin) for radionuclide "j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life.
The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-60.Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent quarterly composite analysis, Cj= 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j" (microCuries/milliliter).
CPSES -UNITS 1 AND 2- ODCM PART I13/4-26 Rev. 33 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE 3.11.2.1 In accordance with CPSES TS 5.5.4.c and 5.5.4.g, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
- a. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin; and b. For Iodine-1 31, for Iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/yr to any organ.APPLICABILITY:
At all times.ACTION: a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limits(s).
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-2.4.11.2.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Part II of the ODCM to assure that the dose rates at or beyond the SITE BOUNDARY are maintained within the limits of Control 3.11.2.1.CPSES -UNITS 1 AND 2- ODCM PART I13/4-27 Rev. 33 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM SAMPLING ANALYSIS TYPE OF FREQUENCY FREQUENCY ACTIVITY ANALYSIS LOWER LIMIT OF DETECTION (LLD) (1)(pCif/ml)GASEOUS RELEASE TYPE 1 Waste Gas Storage P P Tank Each Tank Each Tank Grab Sample Principal Gamma Emitters(2) lx10"4 2. Containment Purge P P or Vent Each Release(3)
Each Release(3)
Principal Gamma Emitters(2) lx10-Grab Sample M H-3 (oxide) 1x10-6 3. Plant Vent M(3), (4), (5) M(3) Principal Gamma Emitters(2) 1x10-4 Grab Sample H-3 (oxide) 1x10-6 Continuous(6)
W(7)Radioiodine Adsorber 1-131 lx10-1 2 Continuous(6)
W(7)Particulate Sample Principal Gamma Emitters(2) lx10-1 1 Continuous(6)
M Composite Par-ticulate Sample Gross Alpha 1x10-1 1 Continuous(6)
Q Composite Par-ticulate Sample Sr-89, Sr-90 1x10-1 1 Continuous(6)
Noble Gas **Beta or Gamma Noble Gas lxlO 6 Outside Buildings Grab sample W(8) Principle Gamma Emitters(2) lx10-11* Table notations next page**This sample is continuously analyzed by a radiation monitor CPSES- UNITS 1 AND 2- ODCM PART 1 3/4-28 Rev. 33 TABLE 4.11-2 (Continued)
TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
LLD = 4.66sb 6 E*V.°2.22x106 .Yexp(-XAt)
Where: LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume), sb = Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = Counting efficiency (counts per disintegration), V = Sample size (units of mass or volume), 2.22 x 106 = Number of disintegrations per minute per microCurie, Y = Fractional radiochemical yield, when applicable, XL = Radioactive decay constant for the particular radionuclide (sec" 1), and At = 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.
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.
(2) The principal gamma emitters for which the LLD specification applies include the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, 1-131, Cs-1 34, Cs-1 37, Ce-141 and Ce-144 in iodine and particulate releases.
This list does not mean that only these nuclides are to be considered.
In the case of release type 4, Outside Buildings, noble gases and iodine may not be sampled based on an evaluation of the source term. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the 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.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-29 Rev. 33 TABLE 4.11-2 (Continued)
TABLE NOTATIONS (Continued)
(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change _> 15% of RATED THERMAL POWER within a 1-hour period.This requirement does not apply if: (1) analysis of primary coolant activity performed pursuant to Technical Specification 3.4.16 shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3, and (2)noble gas monitoring shows that effluent activity has not increased more than a factor of 3.(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from the sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change _> 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) noble gas monitoring shows that effluent activity has not increased more than a factor of 3.(8) Samples shall be changed at least once per seven (7) days and analysis shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from the sampler. This requirement does not apply, if no activities are being conducted in the Outside Building that would generate radioactive effluent.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-30 Rev. 33 RADIOACTIVE EFFLUENTS DOSE -NOBLE GASES CONTROLS 3.11.2.2 In accordance with CPSES TS 5.5.4.e and 5.5.4.h, the air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY:
At all times.ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, 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.SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.CPSES -UNITS 1 AND 2 -ODCM PART 1 3/4-31 Rev. 33 RADIOACTIVE EFFLUENTS DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with CPSES TS 5.5.4.e and 5.5.4.i, the dose to a MEMBER OF THE PUBLIC from lodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ; and b. During any calendar year: Less than or equal to 15 mrems to any organ.APPLICABILITY:
At all times.ACTION: a. With the calculated dose from the release of Iodine-1 31, Iodine-1 33, 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 a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit and defines the corrective actions that have to be taken to assure that subsequent releases will be in compliance with the above limits.SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-1 31, Iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in Part II of the ODCM at least once per 31 days.CPSES -UNITS 1 AND 2- ODCM PART I13/4-32 Rev. 33 RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 In accordance with CPSES TS 5.5.4.f, the PRIMARY PLANT VENTILATION SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed: a. 0.2 mrad to air from gamma radiation, or b. 0.4 mrad to air from beta radiation, or c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.APPLICABILITY:
At all times.ACTION: a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, 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 3) Summary description of action(s) taken to prevent a recurrence.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in Part II of the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.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.CPSES -UNITS 1 AND 2- ODCM PART I13/4-33 Rev. 33 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with CPSES TS 5.5.4.j, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.APPLICABILITY:
At all times.ACTION: a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 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, the Independent Spent Fuel Storage Installation (ISFSI), 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 a report to the NRC within 30 days, pursuant to 10 CFR 20.1301(d) and 10 CFR 20.2203(a)(4) 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 report, as defined in 10 CFR 20.2203(b), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.
If the estimated dose(s)exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the 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.SURVEILLANCE REQUIREMENTS 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 Part II of the ODCM.4.11.4.2 Cumulative dose contributions from direct radiation from the units, the ISFSI, and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Part II of the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4.CPSES -UNITS 1 AND 2- ODCM PART I13/4-34 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 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 NRC, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3, a description of the reason(s) for not conducting the program as required and the 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 a report to the NRC within 30 days, pursuant to 10 CFR 50, Appendix I, that identifies the cause(s) for exceeding the limit(s) and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3.
When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) + concentration (2) +... >1.0 reporting level (1) reporting level (2)When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose*to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Control 3.11.1.2, 3.11.2.2, or 3.11.2.3.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 6.9.1.3.The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.CPSES- UNITS 1 AND 2- ODCM PART I13/4-35 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued)
- 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 days to the Radiological Environmental Monitoring Program. The specific locations from which samples were unavailable may then be deleted from the monitoring program. New sampling locations shall be listed in the results of the annual Land Use Census.SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1. The specific sample locations for the Radiological Environmental Monitoring Program shall be listed and maintained current in the results of the annual Land Use Census.CPSES -UNITS 1 AND 2- ODCM PART I13/4-36 Rev. 33 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS0)
EXPOSURE PATHWAY AND/OR SAMPLE SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 1. Direct Radiation(2)
Forty routine monitoring stations either with Quarterly two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY;An outer ring of stations, onein each meteorological sector in the 6- to 8-km range from the site; and Gamma dose quarterly 2. Airborne Radioiodine and Particulates The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.Samples from five locations:
Three samples from close to the three SITE BOUNDARY locations, in different sectors, of the highest calculated annual average ground-level D/Q;Continuous sampler operation Radioiodine Canister: with sample collection weekly, 1-131 analysis weekly or more frequently if required by dust loading.Particulate Sampler: Gross beta radioactivity analysis following filter change;(4) and gamma isotopic analysis(5) of composite (by location quarterly).
CPSES- UNITS 1 AND 2- ODCM PART I13/4-37 Rev. 33 TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS0 1)One sample from the vicinity of a community having the highest calculated annual average ground-level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.(3)
SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 3. Waterborne
- a. Surface Squaw Creek Reservoir(6)
Lake Granbury Control-Brazos River upstream of Lake Granbury Samples from two sources if likely to be affected.(8)
Monthly composite of weekly grab samples.Monthly composite of weekly grab samples when Lake Granbury is receiving letdown from SCR. Otherwise, monthly grab sample.(7)
Monthly Quarterly Gamma isotopic analysis(5) monthly.Composite for tritium analysis quarterly.
Gamma isotopic analysis(5)monthly.Composite for tritium analysis quarterly.
Gamma isotopic analysis(5) monthly.Composite for tritium analysis quarterly.
Gamma isotopic(5) and tritium analysis quarterly.
- b. Ground CPSES -UNITS 1 AND 2 -ODCM PART 1 3/4-38 Rev. 33 TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1)EXPOSURE PATHWAY AND/OR SAMPLE 3. Waterborne (Continued)
- c. Drinking d. Sediment from Shoreline SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS One sample from Squaw Creek Reservoir.
One sample from downstream area with existing or potential recreational value.Composite of weekly grab samples over 2-week period when 1-131 analysis is performed; monthly composite of weekly grab samples otherwise.
Semiannually.
1-131 analysis of each composite sample when the dose calculated for the consumption of the water is greater than 1 mrem per year(9). Gross beta and gamma isotopic analyses(5) monthly.Composite for tritium analysis quarterly.
Gamma isotopic analysis(5) semiannually.
- 4. Ingestion a. Milk Samples from milking animals in three locations within 5 km distance having the highest dose potential.
If there are none, sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.(9) One sample from milking animals at a control location, 15 to 30 km distant and in the least prevalent wind direction.(3)Semimonthly when animals are Gamma isotopic(5) and 1-131 on pasture; monthly at other analysis semimonthly when times. animals are on pasture; monthly at other times.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-39 Rev. 33 TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS0 1)EXPOSURE PATHWAY AND/OR SAMPLE 4. Ingestion (Continued)
- b. Fish and Invertebrates SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS One sample of at least two recreationally Sample semiannually.
important species in vicinity of plant discharge area.One sample of same species in areas not influenced by plant discharge.
Gamma isotopic analysis(5) on edible portions semiannually
- c. Food Products*One sample of each principal class of food products from any area that is irrigated by water in which liquid plant wastes have been discharged.
At time of harvest(1 0)A sample of broad leaf vegetation grown Monthly, when available.
nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed at all required locations.
One sample of each of the similar broad leaf Monthly, when available.
vegetation grown 15 to 30 km distant in the least prevalent wind direction(3) if milk sampling is not performed at all required locations.
Gamma isotopic analysis(5)on edible portion following sample collection.
Gamma isotopic(5) and 1-131 analyses, monthly, when samples are collected Gamma isotopic(5) and 1-131 analyses, monthly, when samples are collected Reports from 3 additional airborne radioiodine sample locations may be supplemented for broad leaf vegetation samples.CPSES- UNITS 1 AND 2- ODCM PARTI13/440 Rev. 33 TABLE 3.12-1 (Continued)
TABLE NOTATIONS (1) For each sample location required by Table 3.12-1, specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided in information maintained current in the results of the annual Land Use Census. 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.New sampling locations shall be listed in the results of the annual Land Use Census.(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 dosimeter is considered to be one phosphor or aluminum oxide chip (detector) or; two or more phosphors or aluminum oxide chips (detectors) in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation.
(3) The purpose of this sample is to obtain background information.
If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.
The control sample location at 12.3 miles in the southwest sector has been evaluated and found to be an acceptable substitute sampling location.(4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.(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 and at a distance beyond significant influence of the discharge.
(8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
CPSES- UNITS 1 AND 2- ODCM PARTI13/441 Rev. 33 TABLE 3.12-1 (Continued)
TABLE NOTATIONS (Continued)
(9) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in Part II of the ODCM.(10) If harvest occurs more than once a year, sampling shall be performed 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.CPSES- UNITS 1 AND 2- 0DCM PART 1 3/4-42 Rev. 33 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS ANALYSIS (pCi/1) (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet)H-3 20,000*Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-1 37 50 20 2,000 70 2,000 Ba-La-140 200 300 (*) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.(**) If no drinking water pathway exists, a value of 20 pCi/I may be used.CPSES -UNITS 1 AND 2 -ODCM PARTI13/443 Rev. 33 TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lower Limit of Detection (LLD)(3)AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS SEDIMENT ANALYSIS (pCi/1) (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry)Gross Beta 4 0.01 H-3 2000*Mn-54 15 130 Fe-59 30 260 Co -58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15* If no drinking water pathway exists, a value of 3000 pCi/I may be used.** If no drinking water pathway exists, a value of 15 pCi/I may be used.CPSES- UNITS 1 AND 2- ODCM PART I13/4-44 Rev. 33 TABLE 4.12-1 (Continued)
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 TLD (Thermoluminescent Dosimeter)
Badge used for environmental measurements shall be in accordance with the recommendations of 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 a 5% probability of falsely concluding that a blank observation represents a "real" signal.LLD = 4"66Sb E V e Y
- exp (-XAt) 2.22 Where: LLD the "a priori" lower limit of detection (picoCurie per unit mass or volume), sb Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E Counting efficiency (counts per disintegration), V = Sample size (units of mass or volume), 2.22 = Number of disintegrations per minute per picoCurie, Y = Fractional radiochemical yield, when applicable,? = Radioactive decay constant for the particular radionuclide (sec-1), and At = 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.
It should be recognized that the LLD is defined as an a orion (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.
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.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-45 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 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 50m 2 (500 ft 2) producing broad leaf vegetation.
APPLICABILITY:
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 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) within 30 days, to the Radiological Environmental Monitoring Program. The sampling locations having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.
New sampling locations shall be listed in the results of the annual Land Use Census.SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1, Item 4.c. shall be followed, including analysis of control samples.CPSES -UNITS I AND 2- ODCM PART 13/4-46 Rev. 33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by Table 3.12-1.APPLICABILITY:
At all times.ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3.SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in Part II of 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.CPSES -UNITS 1 AND 2- ODCM PART 1 3/4-47 Rev. 33 BASES CPSES -UNITS I AND 2- ODCM PART I B 3/4-0 Rev. 31 INSTRUMENTATION BASES 3/4.3.3.4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II of the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 1 OCFR50.3/4.3.3.5 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part II of the ODCM to ensure that the alarm/trip will occur prior to exceeding the dose rate limits of Control 3.11.2.1.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.3/4.3.3.6 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of the second proposed Revision 1 to Regulatory Guide 1.23, "Onsite Meteorological Programs," April 1986.The surveillance requirements of the meteorological instrumentation are consistent with the recommendations of the second proposed Revision 1 to Reg. Guide 1.23 except for the calibration requirements for the Wind Speed and Wind Direction sensors which are replaced with calibrated sensors at least once per each 12 months. The calibration interval starts when the sensor is installed provided the sensor has been vendor calibrated within two years, and the sensor has been in proper storage up to the time of installation.
These controls have been shown to meet the accuracy and data recovery recommendations of the above reference version of Reg. Guide 1.23.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-1 Rev. 31 INSTRUMENTATION BASES 3/4.7.15 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 1 OCFR70.39(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 mechanism.
CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-2 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be less than 10 times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.
It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in CONTROLLED AREAS and UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) restrictions authorized by 10 CFR 20.1301(e).
The concentration limit for the dissolved or entrained noble gases is based upon the assumption that XE-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This control does not affect the requirement to comply with the annual limitation of 10 CFR 20.1301 (a).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-300.3/4.11.1.2 DOSE This control is provided to implement the requirements of Sections II.A, III.A and IV.A of 1OCFR50, 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 material in liquid effluents to CONTROLLED AREAS and 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 radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141.
The dose calculation methodology and parameters in Part II of the 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 Part II of 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 1OCFR50, 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.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-3 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES This control applies to the release of radioactive materials in liquid effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.
This control applies to the release of radioactive materials in liquid effluents from each unit at the site. The liquid effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.1.4 LVW POND RESIN INVENTORY The inventory limits of the LVW Pond are based on limiting the consequences of an uncontrolled release of the pond resin inventory.
The expression in Control 3.11.1.4 assumes the pond inventory is uniformly mixed, and that the pond is located in a CONTROLLED AREA as defined in 10 CFR Part 20, and that the concentration limit in Note 4 to Appendix B of 10 CFR Part 20 applies. This expression limits the total quantity of radioactive materials in resins discharged to the LVW Pond to a value such that the average concentration in the resins, calculated over the total volume of resins in the pond, will not exceed the Effluent Concentration Limits specified in 10 CFR 20, Appendix B, Table 2, Column 2. Because Control 3.11.1.1 limits the concentration of liquid effluents from other pathways to the LVW Pond to 10 times the 10 CFR 20 Effluent Concentration values, also limiting the average concentration in resins to the Effluent Concentration values will assure that the average concentration in the pond from all sources, calculated over the total volume of the pond (liquid and resins), will not exceed the limits of Control 3.11.1.1.The batch limits for resins transferred to the LVW Pond assure that radioactive material in the slurry transferred to the Pond are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in Control 4.11.1.4 assures no batch of resins will be transferred to the Pond unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than 10% of the limits established in 10 CFR 20, Appendix B.The batch limit is arbitrarily established at 10% of the 10 CFR 20, Appendix B limits to minimize input of radioactive materials to the LVW Pond consistent with detection limits for the resin analysis.
The batch limit also provides assurance that the radioactive material released is within the inventory limitation of Control 3.11.1.4.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-4 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This control, in conjunction with Controls 3.11.2.2 and 3.11.2.3, is provided to ensure that the dose at or beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20 for MEMBERS OF THE PUBLIC. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.
Because these dose rate limits are applied on an instantaneous basis and because of the overriding 10 CFR 50, Appendix I, cumulative dose limitations established in Controls 3.11.2.2 and 3.11.2.3, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR 20.1301(a).
For MEMBERS OF THE PUBLIC who may at times be in CONTROLLED AREAS within the SITE BOUNDARY, the occupancy factors for those MEMBERS 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 is provided in PART II of the ODCM.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 gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). 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-300.3/4.11.2.2 DOSE -NOBLE GASES This control is provided to implement the requirements of Sections lI.B, III.A and IV.A of 10CFR50, Appendix I. The control implements the guides set forth in Section 1.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 CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by 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 dose calculation methodology and parameters established in Part II of the ODCM for calculating the doses due to the actual release rates of the radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-5 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 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. The ODCM equations provided for determining the air doses at or beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. The gaseous effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM This control is provided to implement the requirements of Sections II.C, Ill.A, and IV.A of 10CFR50, Appendix I. The Controls are the guides set forth in Section IL.C 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 materials in gaseous effluents to CONTROLLED AREAS and UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The calculational methodology and parameters specified in Part II of the ODCM for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion 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 Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days is dependent upon the existing radionuclide pathways to man in the areas at or beyond the SITE BOUNDARY.
The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals 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. The gaseous effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP 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 portions of these CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-6 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 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 IL.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. The gaseous effluents from the shared radwaste treatment system are proportioned equally between Unit 1 and Unit 2.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-7 Rev. 31 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(e).
The control requires the preparation and submittal of a report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the total 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 !, and if direct radiation doses from the units (including outside storage tanks, etc.)are kept small. The 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 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 radius 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 report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4) and 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the 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. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-8 Rev. 31 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant and ISFSI 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 measurable 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 priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and 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-300.3/4.12.2 LAND USE CENSUS This control is provided to ensure that changes in the use of areas at or beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program 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 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden.was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2.3/4.12.3 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 environmental sample matrices are performed as part of the quality CPSES- UNITS 1 AND 2- ODCM PART I B 3/4-9 Rev. 31 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES assurance 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.CPSES -UNITS 1 AND 2- ODCM PART I B 3/4-10 Rev. 31 SECTION 5.ODESIGN FEATURES CPSES -UNITS 1 AND 2- ODCM PART I15-0 Rev. 23 5.0 DESIGN FEATURES MAP DEFINING CONTROLLED AREAS, UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which allows identification of structures and release points as well as definition of CONTROLLED AREAS, UNRESTRICTED AREAS and the SITE BOUNDARY are shown in Figure 5.1-3.The UNRESTRICTED AREA, as shown in Figure 5.1-3, is that area beyond the SITE BOUNDARY.
Access to this area is not limited or controlled by the licensee.
This is consistent with the definition of UNRESTRICTED AREA given in 10 CFR 20.1003. The SITE BOUNDARY coincides with the Exclusion (fenced) Area Boundary, as defined in 10 CFR 100.3(a).
For calculations performed pursuant to 10 CFR 50.36a, the concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable.
The CONTROLLED AREA, as shown in Figure 5.1-3, is that area that is inside the SITE BOUNDARY but is outside of any plant areas defined by the licensee as restricted areas, per the definition of restricted area in 10 CFR 20.1003. Access to the CONTROLLED AREA is limited or controlled by the licensee.
This is consistent With the definition of CONTROLLED AREA given in 10 CFR 20.1003.CPSES -UNITS 1 AND 2- ODCM PART I15-1 Rev. 23 UmPINSTll ARE UNRESTRICTED AREA KEY---- SITE BOUNDARY M McMi STAX MIT MLNAMa PONT.N UWh. MSAA POWT EWTML 201)-The pa.,l wUI t.t.ka as I 2W chows grade. ml. Is 64'below U,.tops of lho Cantabnnwnt OuldIng..FIGURE 5.1-3CONTROLLED AREA, UNRESTRICTED AREA AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS CPSES -UNITS 1 AND 2 -ODCM PART I15-2 Rev. 23 SECTION 6.OADMINISTRATIVE CONTROLS CPSES -UNITS 1 AND 2- ODCM PART 1 6-0 Rev. 31 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*6.9.1.3 A Routine Annual Radiological Environmental Operating Report covering the operation of the units during the previous calendar year shall be submitted prior to May I of each year.The Annual Radiological Environmental Operating Report shall include summaries, interpretations, 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 the environment.
The report shall also include the results of the annual Land Use Census required by Control 3.12.2.The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations listed and maintained current in the results of the annual Land Use Census, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.The Annual Radiological Environmental Operating Report 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 participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.
A single submittal may be made for both units.One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
Maps are included in the results of the annual Land Use Census.CPSES -UNITS 1 AND 2- ODCM PART I16-1 Rev. 31 ADMINISTRATIVE CONTROLS RADIOACTIVE EFFLUENT RELEASE REPORT*6.9.1.4 A routine Radioactive Effluent Release Report covering the operation of the units during the previous year of operation shall be submitted prior to May 1 of each year. The period of the first report shall begin with the date of initial criticality.
The Radioactive Effluent Release Report 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 Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.**
This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in Part II of the OFFSITE DOSE CALCULATION MANUAL (ODCM).The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 8, October 1977.A single submittal may be made for both units. The submittal should combine those sections that are common to both units at the station.In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.CPSES -UNITS 1 AND 2- ODCM PART 1 6-2 Rev. 31 ADMINISTRATIVE CONTROLS RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
The Radioactive Effluent Release Report shall include a list and description of unplanned releases, from the site to CONTROLLED AREAS and UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.The Radioactive Effluent Release Report shall include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2.The Radioactive Effluent Release Report 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 a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the Technical Specification limits.6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)Changes to the ODCM: a. Shall be documented and records of reviews performed shall be retained as required FSAR Section 17.2.17.1.
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 20.1302, 40 CFR Part 190, 10 CFR 72.104, 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 Vice President of Nuclear Operations.
- 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 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.
CPSES -UNITS 1 AND 2- ODCM PART 1 6-3 Rev. 31 PART IICALCULATIONAL METHODOLOGIES CPSES -UNITS 1 AND 2- ODCM Rev. 23 SECTION 1.OLIQUID EFFLUENTS The Comanche Peak Steam Electric Station (CPSES) is a 2-unit nuclear generating facility.Each unit is a 1150 MWe, 4-loop, Westinghouse PWR. The units share a common primary liquid radwaste processing system. CPSES is located on Squaw Creek Reservoir (SCR), which serves as the point of supply and discharge for the plant circulating water. Radioactive liquid effluent releases from the primary radwaste processing system are batch type releases, from the Plant Effluent Tanks (PET), Laundry Holdup & Monitor Tanks (LHMT) and Waste Monitor Tanks (WMT), discharged to SCR via the Circulating Water Discharge Tunnel. Potentially radioactive liquid effluent releases from secondary systems include a continuous release from the Turbine Building Sumps (TB Sump), the Unit 1 and Unit 2 Component Cooling Water Drain Tanks (CCWDT), Auxiliary Building Sumps 3 and 11, and the Unit 1 and Unit 2 Diesel Generator Sumps 1, 2, 3 and 4, and batch releases from the Condensate Polisher Backwash Recovery Tanks (CPBWRT).
These secondary pathways from each unit are normally discharged to the common Low Volume Waste (LVW) Pond for chemical treatment.
The LVW Pond normally discharges to SCR via the circulating Water Discharge Tunnel. Alternatively, secondary waste streams may be routed to the common Waste Water Holdup Tanks (WWHT). The WWHTs may be released on a batch basis to the LVW Pond or to SCR via the Circulating Water Discharge Tunnel, depending on the levels of radioactivity present. Table 4.11-1 of Part I of this document requires that secondary waste streams be diverted to the WWHT's if radioactivity is present in the waste stream in concentrations that exceed 10 times the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Also, releases from the Station Service Water (SSW) System are monitored for radioactivity, although no significant releases of radioactivity are expected from this pathway.Sampling and analysis requirements for all release sources are given in Part I, Table 4.11-1. All batch release sources are isolated and thoroughly mixed by mechanical mixing or recirculating the tank contents, prior to sampling, to assure representative sampling.
The recirculation or mixing times necessary to assure representative sampling shall be specified in station procedures.
A summary of all liquid effluent release sources, volumes, flow rates, and associated radiation monitors is shown in Table 1.1. A flow diagram of all liquid effluent discharge pathways is shown in Figure 1.1.The liquid effluent radiation monitors shown in Figure 1.1 are part of the plant Digital Radiation Monitoring System (DRMS) supplied by Sorrento Electronics (formerly General Atomics).
Since the DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uCi/ml). The conversion factor for detector output from counts per minute to uCi/ml is determined in the calibration process and input into the database for the monitor microprocessor.
1.1 10 CFR 20 AND RADIOLOGICAL EFFLUENT CONTROL 314.11.1.1 COMPLIANCE To demonstrate compliance with 10 CFR 20.1301, ODCM Radiological Effluent Control 3/4.11.1.1 requires that the concentration of radioactive material released in liquid effluents to CONTROLLED AREAS and UNRESTRICTED AREAS be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases, and to 2E-4 uCi/ml for dissolved or entrained noble gases. 10 CFR 20 compliance is checked for all discharges to SCR via the Circulating Water Discharge Tunnel listed in Table 1.1. Because the LVW Pond is located in a CONTROLLED AREA, discharges to the LVW Pond are also checked for 10 CFR 20 compliance.
If radioactive materials are present in the LVW Pond CPSES -UNITS 1 AND 2- ODCM PART 1I11-1 Rev. 23 discharge in concentrations that exceed 10% of the limits of 10 CFR 20, Appendix B, Table 2, Column 2, then all inputs to the LVW Pond are sampled and checked for compliance with 10 CFR 20. The following methodology is used to determine compliance with these limits.1.1.1 Isotopic Concentration of the Waste Tank Determine the isotopic concentration in waste stream to be released: 7_ Ci Y XCg + (Ca + Cs + Ct + CFe) [Eq. 1-1]i g Where: E Sum of the concentrations of each radionuclide, i, in the release Ci (uCi/mi),-Sum of the concentrations of each measured, gamma emitter, Cg g, (uCi/ml) as required by Radiological Effluent g Control 3/4.11.1.1, Table 4.11-1.Ca Concentration of alpha emitters as measured in the most recent composite sample (uCi/mi) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (Sample analyzed for gross alpha only), Cs Concentration of 8 9 Sr and 9 0 Sr as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, Ct Concentration of 3 H as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, and CFe Concentration of 5 5 Fe as measured in the most recent composite sample (uCi/ml) required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1.1.1.2 Effluent Flow Rate (f)The maximum effluent discharge flow rates for each release source are shown in Table 1.1. For pre-release calculations, the maximum effluent flow rate is normally used.For post-release calculations, the average effluent flow rate during the release may be used. When the maximum effluent flow rate is used for pre-release calculations, no setpoint is required for the flow measuring device for the effluent release line. If a lower effluent flow rate is used in pre-release calculations, a flow measuring device setpoint shall be established to ensure that the ratio of the Required Dilution Factor (RDF) to the Actual Dilution Factor (ADF) is maintained less than or equal to 1.0, as discussed in Section 1.1.6. ADF and RDF are defined in Section 1.1.4 and 1.1.5, respectively.
CPSES -UNITS 1 AND 2- ODCM PART I111-2 Rev. 23 1.1.3 Dilution of Liquid Effluents a. Discharges to SCR via Circulating Water Discharge Tunnel Since liquid effluents from the radwaste treatment system, Waste Water Holdup Tanks and the LVW Pond are mixed with Circulating water prior to being discharged to Squaw Creek Reservoir, compliance with 10 CFR 20 is a function of the Circulating water flow rate. The maximum Circulating water flow rate per plant is 1.1 million gpm. This is determined from the Ingersoll-Rand pump curves (Fig. 1.2) which indicate a flow rate per pump of 275,000 gpm. The actual Circulating water dilution flow is given by: F(diluting flow) = (275,000 gpm/pump) x (# of pumps) x 0.9[Eq. 1-2]Where: 0.9 = Safety Factor to compensate for flow fluctuations from the rate predicted by the Circulating water pump curves (Fig. 1.2).As an additional consideration, the available dilution flow for any release may be corrected to allow for simultaneous releases from the Radwaste Processing System, a Waste Water Holdup Tank, and/or the LVW Pond (i.e., a radwaste system tank, a Waste Water Holdup Tank, and the LVW Pond may be discharged simultaneously).
For simultaneous releases, the available dilution flow for any release is reduced by the required dilution flow for any other concurrent releases.
Also, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isotopes.
It is therefore necessary to account for recirculation of previously discharged radionuclides.
This is accomplished as follows: F'= F(1 -Zi(C'i/10ECLi))
[Eq. 1-3]Where: F' = Adjusted Circulating Water Flow Rate C'i Maximum concentration of radionuclide i in Squaw Creek Reservoir (uCi/ml) as measured in the analysis of the monthly samples of the reservoir required by Radiological Effluent Control 3/4.12.1, Table 3.12.1. Sample locations are listed and maintained current in the results of the annual Land Use Census.ECLi Effluent Concentration Limit of radionuclide i, from 10CFR20, Appendix B, Table 2, Column 2 F = (275,000 gpm/pump) x (# or pumps) x 0.9 NOTE: If C'i 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.CPSES -UNITS 1 AND 2- ODCM.PART 11 1-3 Rev. 23
- b. Discharges to the LVW Pond Secondary release sources are discharged directly to the LVW Pond with no dilution (i.e., F=O).1.1.4 Actual Dilution Factor (ADF)ADF is the ratio of the effluent flow rate plus the Circulating water flow rate divided by the effluent flow rate.ADF = (f + F)/f [Eq. 1-4]Where: f = Effluent flow rate (gpm)F = Dilution flow rate (gpm)NOTE: If radioactivity is detected in the Reservoir, an adjusted Circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See Section 1.1.3 for the calculation of F' (Eq. 1-3). Also, if simultaneous releases are occurring, the available dilution flow shall be reduced by the required dilution flow for any other concurrent release.1.1.5 Required Dilution Factor (RDF)The required dilution factor ensures that the limits of Control 3/4.11.1.1 (i.e., 10 times the effluent concentrations expressed in 10CFR20, Appendix B, Table 2, Column 2, and a total concentration of dissolved or entrained noble gases of 2 x 10-4 uCi/ml) are not exceeded during a discharge.
The required dilution factor includes a safety factor of 2 to provide a margin of assurance that the instantaneous concentration limits are not exceeded.RDF = (yi (Ci/10ECL 1)) x SF (Xg (Cg/10ECLg)+ (Ca/10ECLa+
Cs/10ECLs
+Ct/10ECLt+
CFe/10ECLFe))
x SF [Eq. 1-5]Where: ECLi Effluent Concentration Limit of radionuclide i, from 1OCFR20, Appendix B, Table 2, Column 2 SF = Safety Factor of 2.CPSES- UNITS I AND 2- ODCM PARTII11-4 Rev. 23 All other variables and subscripts are previously defined.NOTE: If RDF is less than 1, the release 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 C 0 w in Section 1.2.1.1.1.6 10 CFR 20 Compliance Compliance with 10 CFR 20 is demonstrated if the Actual Dilution Factor (ADF) is greater than the Required Dilution Factor (RDF), or: RDF ADF < 1.0 [Eq. 1-6]1.2 RADIATION MONITOR ALARM SETPOINTS 1.2.1 Primary Liquid Effluent Monitor XRE-5253 To ensure that releases from the primary radwaste processing system do not exceed 10 times the 10 CFR 20, Appendix B, Table 2, Column 2 limits at the point of release to the CONTROLLED AREA or UNRESTRICTED AREA, a radiation detector (XRE-5253) monitors discharges to the Circulating Water Discharge Tunnel. XRV-5253 is the discharge isolation valve controlled by XRE-5253.
The isolation valve shuts automatically if the detector alarms on high radiation or a detector operation failure occurs. It should be noted that the liquid effluent monitor setpoint values determined using the methodology from this section will be regarded as upper bounds for the actual setpoint adjustments.
That is, setpoints may be established at values lower than the calculated values, if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.Since the radiation monitor XRE-5253 is a gamma sensitive device, the monitor setpoint value shall be set based on the gamma radionuclides present in the waste stream.Therefore, a Required Dilution Factor gamma (RDFg) must be determined before the setpoint can be calculated.
RDFg = X (Cg/10ECLg)
X SF [Eq. 1-6a]CPSES -UNITS 1 AND 2- ODCM PART I111-5 Rev. 23 Where: RDFg The required dilution factor (gamma) corresponding to the gamma concentration in the undiluted waste stream ensuring that 10 times the effluent concentration limits in 10CFR20, Appendix B, Table 2, Column 2 are not exceeded at the point of release during a discharge.
If RDFg is less than 1, set RDFg equal to 1.0.SF = A required safety factor of 2 is used to account for the presence of Tritium, composited Alpha emitters, Fe-55, Sr-89 and Sr-90 values which are undetectable by this monitor and are at or near equilibrium and/or not expected to change rapidly under most plant conditions and statistical errors of measurement.
The monitor XRE-5253 setpoint is determined using the following calculation:
C0w = (ADF/RDFg)
X 9gCg [Eq. 1-7]Where: Cw The liquid waste effluent monitor alarm setpoint.
This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in a release at the limits of Control 3.11.1.1.All other variables are as previously defined.When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be those referenced in Radiological Effluent Control 3/4.11.1.1, Table 4.11-1, Table Notation 2. Figure 1.3 is a representative energy spectrum response for the RD-33 type detector used in XRE-5253.
This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant.
In fact between 1 3 7 Cs and 6 0 Co, the total change in sensitivity is approximately 7%. Because this is well within the accuracy of measurement, there is no need to change the software sensitivity for given varied effluent concentrations.
However, should the concentration of previously unexpected nuclides become significant, further evaluation would be required.1.2.2 Turbine Building Sump Effluent Radiation Monitor 1RE-5100 and 2RE-5100 The purpose of the turbine building sump monitor (1 RE-51 00 and 2RE-51 00) is to monitor turbine building sump discharges and divert this discharge from the Low Volume Waste Pond to the Waste Water Holdup Tanks if radioactivity is detected.
Because the only sources of water to the turbine building sump are from the secondary steam system, activity is expected only if a significant primary-to-secondary leak is present. Since detectable radioactivity is not normally present in the Turbine Building Sumps, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm, should an inadvertent radioactive release occur. To this end, the setpoint will be initially established at three (3) times background until further data can be collected.
Then, if this setpoint is exceeded, the monitor will direct control valves to divert the turbine building sumps discharges from the LVW Pond to the Waste CPSES -UNITS 1 AND 2- ODCM PARTII11-6 Rev. 23 Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir, if required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. When radioactive materials are detected in the Turbine Building Sumps, a setpoint then may be established for 1 RE-51 00 or 2RE-51 00 using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond.1.2.3 Station Service Water (SSW) Effluent Radiation Monitors I RE-4269/4270 and 2RE-4269/4270 The concentration of byproduct radioactive materials released from plant operations to the station service water (SSW) effluent lines normally is expected to be insignificant.
However, because the SSW effluent has no additional dilution prior to its release into Squaw Creek Reservoir, it is important that this stream's process radiation monitors be optimized to detect any potential radioactive release of CPSES radioactive materials which could leak via this pathway. Complicating this surveillance task, operational experience has shown that the SSW radiation monitors periodically detect natural radionuclides in the SSW effluent.
These natural radionuclides originate from washout of radon daughter products on plant surfaces following rainfall events. The detection of natural radionuclides in the SSW effluent is consistent with the normal expected function and operable status of the SSW radiation monitors.
However, if a SSW radiation monitor setpoint is exceeded and an alarm is initiated (especially during or immediately after rainfall), then it is necessary to verify if the detected radioactivity is from natural radionuclides or from plant contamination by established assessment techniques.
Natural radionuclides may be verified when a SSW alert setpoint only is exceeded by sampling or by comparison to the Component Cooling Water (CCW) process radiation monitors since the source of CPSES byproduct radionuclides in the SSW would be from the CCW.Plant procedures and operating practices provide verification of detector alert or alarm conditions.
The SSW effluent radiation monitors should have alert setpoints established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release of plant byproduct radioactive materials occur. To this end, the monitor's alert setpoint is normally established at three (3) times background.
Alert setpoint alarms should be verified in accordance with plant procedures.
Those alert setpoint alarms attributable to natural radionuclides should not be considered to be a plant adverse condition (i.e., release of plant contamination) and should not result in the monitor being declared inoperable.
The SSW effluent radiation monitor's alarm setpoint is set at a higher level threshold, based on operating experience, to prevent alarm by most natural radionuclide washout events. Events that result in a SSW effluent radiation monitor alarm setpoint alarm should be considered a plant adverse condition and be investigated in accordance with plant procedures and applicable Controls of Part I of the ODCM. If the SSW effluent stream becomes contaminated with plant byproduct radioactive materials, radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows: Csw Y= 9[Eq. 1-8]DF CPSES -UNITS 1 AND 2- ODCM PARTII11-7 Rev. 23 Where: Csw = Station Service Water effluent monitor alarm setpoint Cg = Concentration of each measured gamma emitter (g), observed in the effluent (uCi/ml)DF = Xi(Ci/10ECLj)
= Dilution factor required to ensure limits of Control 3/4.11.1.1 are not exceeded.As stated above, for the SSW effluent release pathway there is no additional dilution available.
Therefore, if the calculated DF is greater than 1.0, any releases occurring via this pathway will result in a violation of Radiological Effluent Control 3/4.11.1.1.
If plant byproduct radioactivity is detected in the SSW effluent, doses due to releases shall be calculated in accordance with the methodology given in Section 1.3, with the near field average dilution factor, Fk, equal to 1.0.1.2.4 Auxiliary Building to LVW Pond Radiation Monitor XRE-5251A The purpose of the Auxiliary Building to LVW Pond monitor (XRE-5251A) is to monitor the Auxiliary Building Sumps 3 and 11, Unit 1 and Unit 2 Diesel Generator Sumps 1 and 2 and the Unit 1 and Unit 2 Component Cooling Water Drain Tanks continuous discharges and divert these discharges from the Pond to the Waste Water Holdup Tanks if radioactivity is detected.
Since detectable radioactivity is not normally present in these discharges, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent radioactive release occur. To this end, the setpoint will be initially established at three (3) times background until further data can be collected.
Then, if this setpoint is exceeded, XRE-5251A will direct valves X-HV-WM182 and 183 to divert the discharges from the LVW Pond to the Waste Water Holdup Tanks where the effluent can then be sampled and released in a batch mode to Squaw Creek Reservoir, if required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. When radioactive materials are detected in the discharges, a setpoint then may be established for XRE-5251A using the methodology in Section 1.2.1 to ensure that the limits of Control 3.11.1.1 are not exceeded in discharges to the LVW Pond.1.3 DOSE CALCULATIONS FOR LIQUID EFFLUENTS For implementation of Radiological Effluent Control 3/4.11.1.2, the dose commitment from the release of liquid effluents will be calculated at least once per 31 days and a cumulative summation of the total body and organ dose commitments will be maintained for each calendar quarter and each calendar year. Dose calculations will be performed for releases from the Plant Effluent Tanks, Waste Monitor Tanks, Laundry Holdup &Monitor Tanks, Waste Water Holdup Tanks, and the LVW Pond via the Circulating Water Tunnel at the point of discharge to Squaw Creek Reservoir.
Although the LVW Pond is located in a CONTROLLED AREA, dose calculations for discharges to the LVW Pond will not be performed because there are no real pathways for exposure to members of the public. Doses for these pathways will be calculated when the LVW Pond is discharged to Squaw Creek Reservoir.
The cumulative dose over the desired time period (e.g., the sum CPSES -UNITS 1 AND 2- ODCM PART II11-8 Rev. 23 of all doses due to releases during a 31 day period, calendar quarter, or a calendar year)will be calculated using the following equation: DT =7 Dk + E D(lake)m k m[Eq. 1-9]Where: DT = Dose commitment to the total body or any organ due to all releases during the desired time interval from all release sources (mrem).Dk = Dose commitment received by the total body or any organ during the duration of release k(mrem). The equation for calculating Dk is given in Section 1.3.1 (Eq. 1-10).D(lake)m = 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 1.3.2 (Eq. 1-12).To demonstrate compliance with the dose limits of Control 3/4.11.1.2, the calculated cumulative dose (i.e., the total dose for both units) will be compared to two times the dose limits for a unit. In other words, the dose assigned to each unit will be one-half of the total doses from all releases from the site.1.3.1 Calculation of Dose Due to Liquid Releases The dose commitment to the total body or any organ due to a release will be calculated using the following equation: Dk IjAl tk Ci Fk[Eq. 1-10]Where: tk Cik Fk Time duration of the release k (hrs)Isotopic concentration (uCi/ml) of radionuclide i found in the release sample for release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For Sr-89, SR-90, H-3, Fe-55 and alpha emitters, the last measured value will be used in the dose calculation.
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 average flow into the Circulating water during the release.CPSES -UNITS 1 AND 2- ODCM PART 11 1-9 Rev. 23 Fk average undiluted liquid effluent flow rate circulating water flow rate Ai = Site related ingestion dose commitment factor for the toal body or any organ, t, for each identified gamma or beta emitter (mrem/hr per uCi/ml). Ai, is calculated as follows: .= 1.14x1:05 (Uw/Dw+ UfBFi) DF 1 [Eq. 1-11]Where: 1.14x10 5= unit conversion factor, pCi ml. yrs p.Ci. I. hrs Uw Adult water consumption from Squaw Creek Reservoir, 0 liters/yr for CPSES Uf = Adult fish consumption, 21 kg/yr BFj Bioaccumulation factor for radionuclide i, in fish from Table A-1, Ref. 2 (pCi/kg per pCi/I)DFj Adult dose conversion factor for radionuclide i, from Table E-1 1, Ref. 22 (mrem/pCi ingested)Dw = Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption; 1.0 for CPSES. (unitless)
Calculated values for Ai, are given in Table 1.2.1.3.2 Calculation of Dose Due to Radionuclide Buildup in the Lake The dose contribution from significant pathways, due to buildup of previously discharged radionuclides in the lake, must be considered in the committed dose calculation only if radioactivity is detected in the water of Squaw Creek Reservoir or in fish from Squaw Creek Reservoir.
Based on the design calculations presented in the CPSES FSAR, Appendix 11A and documented in CPSES Engineering Calculation No. ME-CA-0000-3161, the significant pathways included in this calculation are fish consumption from Squaw Creek Reservoir and consumption of meat from cows drinking water from Squaw Creek. Additionally, consumption of milk from cows drinking water from Squaw Creek is included, but a CPSES site-specific consumption factor of 0 is normally used since there are no identified animals milked for human consumption along Squaw Creek. If animals milked for consumption are identified along Squaw Creek during the annual land use census, this pathway should be included in the dose calculation.
Also, water from Squaw Creek Reservoir or Squaw Creek is not used as a source of drinking water, so the drinking water pathway is not included in dose calculations.
To further simplify the calculation, the dose due to consumption of meat and milk from cows drinking water from Squaw Creek is only calculated for tritium. CPSES Engineering CPSES -UNITS 1 AND 2- ODCM PART 11 1-10 Rev. 23 Calculation No. ME-CA-0000-3161 shows that tritium is the only isotope routinely released from CPSES that significantly contributes to the dose from these pathways (i.e., >95% of the total dose). The calculation does show a significant dose contribution from Ru-1 06 for the cow-meat pathway, but this isotope has not historically been observed in actual CPSES liquid effluent samples. The dose from the fish consumption pathway will be calculated for all measured isotopes.The contribution to the total dose due to the buildup of radionuclides in the reservoir is determined as follows: D(lake)m = 1.14xlO 1-4 [(Xi DFi C 0 f Uf)+DFt Ctw Qaw (UmilkFrt Umeat Fft)] x t [Eq. 1-12]Where: 1.14 x 10-4 = Units conversion factor (yr/hr).C'if = Concentration of radionuclide i in fish sampled from Squaw Creek Reservoir from location F1 as described in the most current CPSES Land Use Census (pCi/kg).DFt Adult ingestion dose conversion factor for tritium for the organ of interest from Table E-1 1, Ref. 2 (mrem/pCi).
C'tw Concentration of tritium in the reservoir.
This value shall correspond to the highest concentration measured at any Squaw Creek Reservoir sample location (pCi/I).Qaw = Consumption rate of contaminated water by a cow, 60 I/day from Table E-3, Ref. 2.Umilk Adult milk consumption rate. A CPSES site-specific usage factor of 0 is normally used unless milk cows are identified along Squaw Creek during the annual Land Use Census. If milk cows are identified, a value of 310 I/yr from Table E-5, Ref. 82, should be used.Fmt Stable element transfer coefficient for tritium that relates the daily intake rate of tritium by a cow to the concentration in milk, 1.OE-2 pCi/I per pCi/day from Table E-1, Rev. 2.CPSES -UNITS 1 AND 2- ODCM PART 11 1-11 Rev. 23 Umeat =-Adult meat consumption rate, 110 kg/yr from Table E-5, Ref. 2.Fft Stable element transfer coefficient for tritium that relates the daily intake rate of tritium by a cow to the concentration in meat, 1.2E-2 pCi/kg per pCi/day.t = Exposure time, hrs (8760 hrs = 1 year)All other variables are previously defined.NOTE: This calculation is only required if activity is detected in water and/or fish in excess of the appropriate LLD values given in Radiological Effluent Control 3/4.12.1, Table 4.12-1. If the measured activity in water or fish is less than the required LLD values, the concentration for that particular pathway is assumed to be zero.1.4 DOSE PROJECTIONS FOR LIQUID EFFLUENTS Radiological Effluent Control 3/4.11.1.3 requires that appropriate portions of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each reactor unit to CONTROLLED AREAS and UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided for performing this dose projection.
At least once every 31 days, the total dose from liquid releases for each unit for the previous three months will be divided by the number of days in the three month period and multiplied by 31. Also, this dose projection may include the estimated dose for a unit due to any anticipated unusual releases during the period for which the projection is made. If the projected dose for a unit exceeds 0.06 mrem total body or 0.2 mrem for any organ, appropriate portions of the Liquid Radwaste Treatment System shall be used to reduce radioactivity levels prior to release.1.5 DEFINITIONS OF COMMON LIQUID EFFLUENT PARAMETERS TERM DEFINITION ADF Actual Dilution Factor (unitless).
This is defined as the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.Ai, The site related ingestion dose commitment factor to the total body or any organ, t, for each identified gamma or beta emitter, i. (mRem/hr per uCi/ml)BFi Biaccumulation factor for radionuclide, i, in fish from Reg. Guide 1.109.(pCi/kg per pCi/I)Ca The concentration of alpha emitters in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)CPSES -UNITS 1 AND 2- ODCM PART 1I11-12 Rev. 23 TERM DEFINITION CFe The concentration of 5 5 Fe in liquid waste as measured in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)Cg The concentration of each measured gamma emitter, g, in the waste tank as measured in the analysis of the sample of each batch as required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)Ci The concentrations of radionuclide, i, in the waste tank. (uCi/ml)C'i The concentration of radionuclide i in the Reservoir as measured in the analysis of the monthly sample of the Reservoir required by Radiological Effluent Control 3/4.12.1, Table 3.12-1. This sample is taken at the Circulatory Water Intake Structure as indicated by location SW6 as described in the most current CPSES Land Use Census. (uCi/ml)C'if The concentration of radionuclide i in fish sampled from the reservoir from location F1 as described in the most current CPSES Land Use Census.(pCi/kg)Cik The isotopic concentration of radionuclide i found in the pre-release sample for batch release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample. For 8 9 Sr, 9 0 Sr, 3 H, 5 5 Fe and alpha emitters, the last measured value will be used. (uCi/ml)C'iw The maximum concentration of radionuclide i in SCR as measured in analysis of monthly samples of SCR.C 1 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 a release at the limits of Control 3.11.1.1. (uCi/ml)Cs The concentration of 8 9 Sr and 9 0 Sr in liquid waste as measured in the analysis of the most recent quarterly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)Csw The Station Service Water effluent monitor alarm setpoint. (uCi/ml).Ct The concentration of 3 H in liquid waste as measured in the analysis of the most recent monthly composite sample required by Radiological Effluent Control 3/4.11.1.1, Table 4.11-1. (uCi/ml)DFi Adult dose conversion factor for radionuclide, i, from Reg. Guide 1.109.(mrem/pCi ingested)Dk The dose commitment received by the total body or any organ during the duration of batch release k of liquid effluents. (mRem)D(lake)m The dose commitment received by the total body or any organ during a desired time period, m, due to the buildup in the lake of previously discharged radionuclides. (mRem)DT The total dose commitment to the total body or any organ due to all releases of liquid effluents during a desired time interval. (mRem)CPSES -UNITS 1 AND 2- ODCM PART 11 1-13 Rev. 23 TERM DEFINITION Dw Dilution factor, from the near field area within 1/4 mile of the release point to the potable water intake for adult water consumption, 1.0 for CPSES.(unitless) f Effluent flow rate. (gpm)F Circulating water flow rate (or dilution flow rate). (gpm)F' Adjusted Circulating water flow rate to account for buildup of radionuclides in the Circulating water due to previous releases. (gpm)Fk The near field average dilution factor during a liquid effluent release (unitless).
This is defined as the ratio of the average undiluted liquid waste flow to the average Circulating water flow during the release.ECLa Effluent Concentration Limit* of a mixture of unidentified alpha emitters.(uCi/ml)ECLFe Effluent Concentration Limit* of 5 5 Fe. (uCi/ml)ECLg Effluent Concentration Limit* of each identified gamma emitter, g.(uCi/ml)ECLi Effluent Concentration Limit* of radionuclide, i. (uCi/ml).ECLs Effluent Concentration Limit* of a mixture of 8 9 Sr and 9 0 Sr. (uCi/ml)ECLt Effluent Concentration Limit* of tritium (3 H). (uCi/ml).SF Safety Factor of 2. Used in the calculation of the Required Dilution Factor (RDF) for liquid releases to provide a margin of assurance that the instantaneous concentration limits are not exceeded.RDF Required Dilution Factor (unitless).
This is defined as the dilution factor that ensures that 10 times the effluent concentrations expressed in 10CFR20, Appendix B, Table 2, Column 2, are not exceeded at the point of release to CONTROLLED AREAS and UNRESTRICTED AREAS during a discharge.
tk The time duration of batch release k. (hours)Uf Adult fish consumption. (kg/yr)Uw Adult water consumption. (liters/yr)
Effluent Concentration limits (ECL) for liquids are given in 10CFR20, Appendix B, Table 2, Column 2. A value of 2x10-4 uCi/ml for dissolved or entrained noble gas shall be used.CPSES -UNITS 1 AND 2 -ODCM PART 11 1-14 Rev. 23 TABLE 1.
SUMMARY
OF LIQUID RELEASE PATHWAYS 1. RELEASES TO SCR VIA THE CIRC WATER DISCHARGE Max FIl Release Source Release Type Rate (gp PET-1 Batch 101 PET-2 Batch 101 WMT-1 Batch 101 WMT-2 Batch 101 LHMT-1 Batch 10(LHMT-2 Batch 10'WWHT-1 Batch 30'WWHT-2 Batch 30 LVW Pond Continuous 160 2. RELEASES TO THE WASTE WATER MANAGEMENT SYSTEM OW 3m)M)0 0 0 0 0 0 0 0 0 Max Vol (gal)30000 30000 5340 5340 5875 5875 30500 30500 Monitor XRE-5253 XRE-5253 XRE-5253 XRE-5253 XRE-5253 XRE-5253 None None None Release Source CPBWRT-A CPBWRT-B WWHT-1 WWHT-2 TBSump2 (Unit1)TBSump4 (Unit2)AB Secondary*
Temporary holdup tanks Release Type Batch Batch Batch Batch Continuous Continuous Continuous Max Flow Rate (gpm)1550 1550 200 200 300 300 380 Max Vol (gal)8500 17000 33100 33100 Monitor None None None None 1 RE-5100 2RE-51 00 XRE-5251A None Batch** Maximum flow and volume will be determined by temporary systems design.3. DIRECT RELEASES TO SCR (SAFE SHUTDOWN IMPOUNDMENT)
Release Source Release Type Unit 1 SSW Train A Continuous Unit 1 SSW Train B Continuous Unit 2 SSW Train A Continuous Unit 2 SSW Train B Continuous AB Secondary Effluents contain the following sources: Max Flow Rate (gpm)17,000 17,000 17,000 17,000 Max Vol (gal)Monitor 1RE-4269 1 RE-4270 2RE-4269 2RE-4270 Auxiliary Building Sump 3 Auxiliary Building Sump 11 Diesel Generator Sump 1 (Unit 1)Diesel Generator Sump 2 (Unit 1)Diesel Generator Sump 1 (Unit 2)Diesel Generator Sump 2 (Unit 2)CCWDT (Unit 1)CCWDT (Unit 2)Max. Flow (opn)50 50 50 50 50 50 40 40 CPSES -UNITS 1 AND 2- ODCM PART 11 1-15 Rev. 23 TABLE 1.2SITE RELATED INGESTION DOSE COMMITMENT FACTOR Ai, ISOTOPE H-3 C-14 NA-24 P-32 CR-51 MN-54 MN-56 FE-55 FE-59 CO-58 CO-60 NI-63 N 1-65 CU-64 ZN-65 ZN-69 BR-83 BR-84 BR-85 RB-86 RB-88 RB-89 SR-89 SR-90 SR-91 BONE 0.OOE+00 3.13E+04 4.07E+02 4.62E+07 0.00E+00 0.OOE+00 0.OOE+00 6.58E+02 1.04E+03 0.OOE+00 0.OOE+00 3.11 E+04 1.26E+02 0.OOE+00 2.32E+04 4.93E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.21 E+04 5.47E+05 4.07E+02 LIVER 2.26E-01 6.25E+03 4.07E+02 2.87E+06 0.OOE+00 4.38E+03 1.1OE+02 4.55E+02 2.44E+03 8.91E+01 2.56E+02 2.16E+03 1.64E+01 9.97E+00 7.37E+04 9.44E+01 0.OOE+00 0.OOE+00 0.OOE+00 1.01 E+05 2.94E+02 1.95E+02 0.OOE+00 0.00E+00 0.OOE+00 T-BODY 2.26E-01 6.25E+03 4.07E+02 1.79E+06 1.27E+00 8.35E+02 1.95E+01 1.06E+02 9.35E+02 2.OOE+02 5.65E+02 1.05E+03 7.49E+00 4.68E+00 3.33E+04 6.56E+00 4.05E+01 5.24E+01 2.15E+00 4.71 E+04 1.56E+02 1.37E+02 6.35E+02 1.33E+05 1.64E+01 THYROID 2.26E-01 6.25E+03 4.07E+02 0.OOE+00 7.62E-01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.O0E+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 KIDNEY 2.26E-01 6.25E+03 4.07E+02 0.OOE+00 2.80E-01 1.31 E+03 1.40E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.51E+01 4.93E+04 6.13E+01 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+0O O.OOE+0C O.OOE+OC LUNG 2.26E-01 6.25E+03 4.07E+02 0.OOE+00 1.69E+00 0.OOE+00 0.OOE+00 2.54E+02 6.82E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00) O.OOE+0C O.OOE+0C O.OOE+OC GI-LLI 2.26E-01 6.25E+03 4.07E+02 5.20E+06 3.20E+02 1.34E+04 3.51 E+03 2.61 E+02 8.16E+03 1.81 E+03 4.81 E+03 4.50E+02 4.16E+02 8.49E+02 4.65E+04 1.42E+01 5.82E+01 4.11 E-04 1.01 E-15 2.OOE+04 3.93E-09 1.13E-11 3.55E+03 1.58E+04 1 .94E+03 SR-92 1.54E+02 0.OOE+00 6.67E+00 0.OOE+00 O.OOE+00 0.OOE+00 3.06E+03 CPSES -UNITS 1 AND 2- ODCM PART II11-16 Rev. 23 TABLE 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR Ai, ISOTOPE Y-90 Y-91 M Y-91 Y-92 Y-93 ZR-95 ZR-97 NB-95 MO-99 TC-99M TC-101 RU-103 RU-1 05 RU-1 06 AG-A11M TE-125M TE-127M TE-127 TE-129M TE-129 TE-131M TE-1 31 TE-132 1-130 1-131 1-132 1-133 BONE 5.77E-01 5.44E-03 8.45E+00 5.06E-02 1.60E-01 2.40E-01 1.33E-02 4.46E+02 0.OOE+00 8.86E-03 9.13E-03 4.42E+00 3.69E-01 6.59E+01 8.81 E-01 2.57E+03 6.49E+03 1.05E+02 1.10E+04 3.01 E+01 1.66E+03 1.89E+01 2.41 E+03 2.72E+01 1.50E+02 7.29E+00 5.09E+01 LIVER 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 7.70E-02 2.68E-03 2.49E+02 1.03E+02 2.51 E-02 1.31 E-02 0.OOE+00 0.OOE+00 0.OOE+00 8.13E-01 9.29E+02 2.32E+03 3.78E+01 4.11E+03 1.13E+01 8.11E+02 7.88E+00 1.56E+03 8.02E+01 2.14E+02 1.95E+01 8.86E+01 T-BODY 1.54E-02 2.11 E-04 2.25E-01 1.48E-03 4.43E-03 5.21 E-02 1.22E-03 1.34E+02 1.96E+01 3.20E-01 1.29E-01 1.91 E+00 1.45E-01 8.33E+00 4.84E-01 3.44E+02 7.90E+02 2.28E+01 1.74E+03 7.32E+00 6.75E+02 5.95E+00 1.46E+03 3.17E+01 1.22E+02 6.81 E+00 2.70E+01 THYROID 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 7.72E+02 1.66E+03 7.80E+01 3.78E+03 2.31E+01 1.28E+03 1.55E+01 1.72E+03 6.78E+03 6.99E+04 6.81 E+02 1.30E+04 KIDNEY 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.21 E-01 4.05E-03 2.46E+02 2.35E+02 3.80E-01 2.37E-01 1.69E+01 4.76E+00 1.27E+02 1.60E+00 1.04E+04 2.63E+04 4.29E+02 4.60E+04 1.26E+02 8.21 E+03 8.26E+01 1.50E+04 1.25E+02 3.68E+02 3.10E+01 1.55E+02 LUNG 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-'00 0.OOE+00 1 .23E-02 6.72E-03 0.OOE+0O 0.OOE-I00 0.OOE+0Q 0.00E4-00 0.OOE-I0Q Q.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+0C* .OOE+OC* .OOE+OC 0.OOE+OC 0.OOE+OC 0.OOE+OC GI-LLI 6.11 E+03 1.60E-02 4.64E+03 8.87E+02 5.1OE+03 2.44E+02 8.30E+02 1.51 E+06 2.39E+02 1.48E+01 3.95E-14 5.16E+02 2.26E+02 4.27E+03 3.33E+02 1.02E+04 2.17E+04 8.31 E+03 5.54E+04 2.27E+01 8.04E+04 2.67E+00 7.38E+04 I 6.90E+01 I 5.64E+01 3.68E+00 7.96E+01 CPSES -UNITS 1 AND 2- ODCM PART II11-17 Rev. 23 TABLE 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR Ai, ISOTOPE 1-134 1-135 CS-1 34 CS-1 36 CS-1 37 CS-1 38 BA-1 39 BA-140 BA-141 BA-142 LA-1 40 LA-142 CE-141 CE-143 CE-144 PR-143 PR-144 ND-147 W-187 NP-239*SB-122**SB-124**BR-82**SB-1 25**SB-1 26**SB-1 27**LA-141 BONE 3.80E+00 1.59E+01 2.98E+05 3.12E+04 3.81E+05 2.64E+02 9.29E-01 1.94E+02 4.51E-01 2.04E-01 1.50E-01 7.66E-03 2.24E-02 3.94E-03 1.17E+00 5.52E-01 1.80E-03 3.76E-01 2.95E+02 2.86E-02 4.42E+00 5.38E+01 0.OOE+00 4.27E+01 2.20E+01 4.94E+00 1.14E-02 LIVER 1.03E+01 4.16E+01 7.09E+05 1.23E+05 5.22E+05 5.22E+02 6.61 E-04 2.45E-01 3.41 E-04 2.09E-04 7.53E-02 3.16E-03 1.51E-02 2.91E+00 4.89E-01 2.21 E-01 7.49E-04 4.35E-01 2.48E+02 2.79E-03 8.71 E-02 1.01 E+00 0.OOE+00 4.58E-01 4.47E-01 1.80E-01 3.55E-03 T-BODY 3.71 E+00 1.54E+01 5.79E+05 8.86E+04 3.42E+05 2.59E+02 2.72E-02 1.27E+01 1.53E-02 1.28E-02 1.99E-02 8.66E-04 1.72E-03 3.24E-04 6.26E-02 2.73E-02 9.16E-05 2.60E-02 8.65E+01 1.54E-03 1.29E+00 2.12E+01 1.78E+02 8.58E+00 7.93E+00 1.90E+00 5.81 E-04 THYROID 1.79E+02 2.75E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.00E+00 6.01E-02 1.30E-01 O.OE+00 3.80E-02 1.35E-01 5.94E-02 KIDNEY 1.65E+01 6.69E+01 2.29E+05 6.85E+04 1.77E+05 3.83E+02 6.18E-04 8.30E-02 3.17E-04 1.77E-04 0.OOE+00 0.OOE+00 7.05E-03 1.29E-03 2.91 E-01 1.28E-01 4.23E-04 2.54E-01 0.OOE+00 8.74E-03 0.OOE+OC 0.OOE+OC O.OOE+OC O.OOE+OC 0.OOE+0C O.OOE+O(LUNG 0.00E+00 0.0OE+00 7.62E+04 9.39E+03 5.89E+04 3.78E+01 3.76E-04 1.39E-01 1.93E-04 1.19E-04 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00)0.OE+O0 O.OOE+OC) 2.30E+0C) 4.18E+01 O.OOE+OC 1.35E+0'2.93E+O(GI-LLI 9.01 E-03 4.70E+01 1.24E+04 1.40E+04 1.01 E+04 2.23E-03 1.65E+00 4.OOE+02 2.06E-1 0 2.87E-1 9 5.52E+03 2.54E+01 5.79E+01 1.09E+02 3.94E+02 2.41 E+03 2.59E-1 0 2.09E+03) 8.11 E+04) 5.74E+02 1 1.27E+03 1 .52E+03 2.05E+02 3.78E+02 I 1.80E+03) 1.13E+03 0.OOE+00 0.OOE+00 0.OOE+00 4.23E+02 CPSES -UNITS 1 AND 2 -ODCM PART II11-18 Rev. 23 The adult dose conversion factors, DFi, for Sb-122 are not published in Reference
- 2. The calculation of dose conversion factors and site-related ingestion dose commitment factors for Sb-1 22 is documented in Reference 10.The adult dose conversion factors, DFi, for Sb-124, Sb-1 25, Br-82, Sb-1 26, Sb-1 27 and La-141 are not published in Reference
- 2. The site-related dose commitment factors for Sb-124, Sb-125, Br-82, Sb-126, Sb-127 and La-141 were calculated using the "Adult Ingestion Dose Factors" given in Table A-3 of Reference 11, and Equation 1-11 of Part II, Section 1.3.1 of this Manual.CPSES -UNITS 1 AND 2- ODCM PART 1I 1-19 Rev. 23 Inputs [I1SW~n Input Unit I SSW -Train A From Liquid Waste IUnit I SSW-Train B Processing S stem I nt2SW-Trln A 33.100 gal ea. XRE-5253 Unit 2 SSW-Train B 300 gpm ea.-- -------Waste Water ic Holdup Tanks N =ter (2 tanks) A: 8500 gal/1 550 gpm T I B: 17000 gal/1550 gpm I C.P.' " Backwash Temporary 1975 gal -- -Recovery Holdup Tanks30 .... ... .. ..... ... Tanks 300 A and B 1 RE-,5100 Unit 1 Turbine I,0Waste' Building Sump -1 i Water No. 2 Management 1975 gal Clarfier , 300 gpm Sump I 600 gpm Unit 2 Turbine 2RE-5100 Building Sump No.4 XRE-5251A I ~ AuxilliaryI Unit1 Unt 2Unit 1 Unit 2 Bilding Diesel Gen. Diesel Gen. CCW Drain CCW Drain Sumps SumpsSumpsTank Tank No.3 &11 135 gal ea. 135 gal ea. 2300 gal 2300 gal 135 gal ea.50 gpm ea. 50 gpm ea. 40 gpm 40 gpm 50 gpm ea.LIQUID EFFLUENT DISCHARGE PATHWAYS FIGURE 1.1 (Simplified diagram)KEY:_ Normal flow path----------
Flow path f > ECL..... -Flow path If < ECL CPSES -UNITS 1 AND 2- ODCMA 2 PART 11 1-20 Rev. 23 C)FIGURE 1.2 MOEBOhISLt-RAND CURVE # XV-3552-4 o r 214.000 ErrOUas CIRCULATING WATER PUMP CURVES BANrmpS m iuarm 288 sv1 01 aE112141-~ IS 9F ri"1,1 " III .............
.... ......... .... .... .... .................
...........
N, ":: 3,-.; .... .....Ifli ilýl~hIIIIjllIJIIjll!11111$'iIIIT 11 ffh~lh~ l ~l lllii I' lff l 1lJiJIlII~llf 34,-40~-A I i 0 .'Ivor1 i.o il £ ~ s~ ~ 1130arm2 I --r- -f 32 34 A-.------I I -CPSES -UNITS 1 AND 2 -ODCM PART II11-21 Rev. 23 c-! 20 8 7 5 0 01 0.4 0.6 0.8 1.0 1.2 1.4 GAMMA PHOTON ENERGY, MeV ENERGY RESPONSE TO GAI9Yk RADIATIONS FOR PD-33 TYPE DETECTOR Figure 1.3?The &Vokw por oft am curv gwa efa~ from mrly isfoto Ciibra~os utrV a chaImbwe of simil goomeiry.on otm golma we odw raw .CPSES -UNITS 1 AND 2- ODCM P2 PART 11 1-22 Rev. 23 SECTION 2.0 GASEOUS EFFLUENTS At CPSES, normal radioactive gaseous effluents are collected in a common exhaust air intake plenum, processed through charcoal and HEPA filters, and discharged to the atmosphere through the two common Plant Vent Stacks designated as Stack A and Stack B. Due to the fact that these release points are below the height of the nearest adjacent structure (i.e., containment building), all gaseous releases from these stacks are conservatively assumed to be entrained into the building wake and cavity regions, which results in a conservative ground-level release.Routine gaseous effluent releases may occur from the Unit 1 and Unit 2 Containment Buildings (purges and vents), Waste Gas Decay Tanks (WGDT), and the plant vent stacks (continuous ventilation).
The normal ventilation exhaust via the plant vent stacks is considered a continuous release. Containment Building vents for pressure relief and WGDT discharges are treated as batch releases.
Because Containment Building purges are only allowed during MODES 5 and 6 and because radioactivity is discharged rapidly from the containment atmosphere during purges, the first portion (i.e., the release period during which most containment atmospheric radioactivity is discharged) of a Containment Building purge is considered a batch release. The remainder of a purge is treated as a contribution to the continuous release already occurring through the plant vent stacks.Operating experience has shown that occasional releases may be required from Pressurizer Relief Tank (PRT) vents for depressurizing the RCS during outages, from Volume Control Tank (VCT) vents during maintenance on the Waste Gas Processing System, from the Containment Buildings during Integrated Leak Rate Tests (ILRT), and from secondary steam releases (potentially radioactive during periods of primary-to-secondary leaks). These releases occur infrequently and are treated as batch releases.Occasional operational requirements involve handling radioactive materials in buildings outside the permanent structures that may contribute to gaseous effluents.
Since these buildings are not connected to the PRIMARY PLANT VENTILATION SYSTEM, portable air sampling equipment may be used to determine effluent airborne radioactivity concentrations.
Offsite dose estimates will be based on the analysis of samples collected, estimated effluent flow rates and treated as a planned continuous or batch release. The effluent discharge point is not the plant stack and the distance to the site boundary may be adjusted, if the proximity to the site boundary would significantly affect the offsite dose estimates.
No automated monitoring or isolation equipment is provided, however, due to a limited source term, this pathway is expected to contribute a small fraction of the dose limits from gaseous effluents.
A summary of all gaseous effluent release points, release sources, flow rates (if applicable) and associated radiation monitors is shown in Table 2.1. A flow diagram of all Gaseous Waste Processing System discharge pathways is shown in Figure 2.1.Each Plant Vent Stack is equipped with a Wide Range Gas Monitor (WRGM) and a Noble Gas Monitor. These monitors are part of the plant Digital Radiation Monitoring System (DRMS)supplied by Sorrento Electronics (formerly General Atomics).
Since all DRMS monitors provide a digital output, they may be calibrated to read out in the appropriate engineering units (i.e., uCi/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.
The WRGMs are designated as monitors XRE-5570A and XRE-5570B for Stacks A and B, respectively.
Each WRGM consists of a low range (10-7 to 10-1 uCi/cc), mid range (10-4 to CPSES -UNITS 1 AND 2- ODCM PART II12-1 Rev. 33 102 uCi/cc), and high range (10-1 to 105 uCi/cc) 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 flow rate detectors (X-FT-557OA-1/B-1) to provide an indication of noble gas release rate in uCi/sec. Alarm setpoints are established for the WRGM effluent release rate channel to fulfill the requirements of Radiological Effluent Control 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 Noble Gas Monitors are designated as noble gas channels XRE-5567A and XRE-5567B for Stacks A and B, respectively.
The stack noble gas channels may be used as a back-up to the WRGM when no automatic control functions are required.
Therefore, a methodology is provided for calculating the noble gas monitor setpoints.
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 Monitors, 1 RE-5503 and 2RE-5503.
XRE-5701 may be used to monitor Waste Gas Decay Tank releases by monitoring the Auxiliary Building Ventilation Duct. XRE-5701 also provides the automatic control function for termination of Waste Gas Decay Tank releases.
1 RE-5503 and 2RE-5503 monitor the Unit 1 and Unit 2 Containment atmospheres, respectively, and provide the only automatic control function for termination of Containment vents or purges.2.1 RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.1 COMPLIANCE 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 BOUNDARY due to noble gases released from the site shall be calculated as follows: a. Total Body Dose Rate Due to Noble Gases Dt= Dtv =_ (X/Q) K Qiv [Eq. 2-1]v v (noble gases)Where: Dt = Total body dose rate at the SITE BOUNDARY due to noble gases from all release sources (mRem/yr)Dtv = Total body dose rate at the SITE BOUNDARY due to noble gases from release source v (mRem/yr).(X/Q)= Highest annual average relative concentration at the SITE BOUNDARY (3.3 x 10-6 sec/m 3 in the NNW sector at a distance of 1.29 miles from the plant*)NOTE: The annual average X/Q is also used in determining setpoints for containment purge or vent as required by Technical Specification 3.3.6.CPSES -UNITS 1 AND 2- ODCM PART 11 2-2 Rev. 33 Ki Total body dose factor due to gamma emissions from noble gas radionuclide i from Table 2.2 (mRem/yr per uCi/m 3)4v Total release rate of noble gas radionuclide i from the release source v (uCi/sec) (See C below for calculation of Q 1 v)v = Index over all release sources Reference 4, Section 2.3.5.2.b. Skin Dose Rate Due To Noble Gases Ds= Dsv v= % (X/Q)V 7- (Li + 1.1 Ml)Qiv (noble gases)[Eq. 2-2]Where: Ds Skin dose rate at the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)Dsv Skin dose rate at the SITE BOUNDARY due to noble gases from release source v. (mRem/yr)Li Skin dose factor due to beta emissions from noble gas radionuclide i from Table 2.2 (mRem/yr per uCi/m 3)1.1 = Conversion factor of mRem skin dose per mRad air dose Mi = Air dose factor due to gamma emissions from noble gas radionuclide i from Table 2.2 (mRad/yr per uCi/m 3)All other terms are as previously defined.c. Release Rate Qj is defined as the total release rate (uCi/sec) of radionuclide i from all release sources. Qi is given by: Qi = , Qiv= _I XiVFV v v[Eq. 2-3]Where: Xiv Measured concentration of radionuclide i present in each release source v (uCi/cm 3)CPSES -UNITS 1 AND 2- ODCM PART 11l2-3 Rev. 33 Flow rate from each release source v (cm 3/sec)Qiv = Release rate of radionuclide i from release source v (uCi/sec)v = Index over all release sources 2.1.2 Dose Rates Due to Radioiodines, Tritium, and Particulates Organ dose rates due to iodine-1 31 and iodine-1 33, tritium, and all radioactive materials in particulate form with half-lives greater than eight days released from the site will be calculated to implement the requirements of Radiological Effluent Control 3/4.11.2.1 .b as follows: D o Dov (X/Q) I PAQ 1 [Eq. 2-4]v v IP&T Where: Do Total organ dose rate due to iodine-131, iodine-133, particulates with half-lives greater than eight days, and tritium from all release sources. (mrem/yr)Dov Organ dose rate due to iodine-1 31, iodine-1 33, particulates with half-lives greater than eight days, and tritium from release source v. (mrem/yr)Pi = Pathway dose rate parameter factor for radionuclide, i, (for radioiodines, particulates, and tritium) for the inhalation pathway in mRem/yr per uCi/m 3 (Table 2.3). The methodology used for determining values of Pi is given in Appendix A.IP&T = Iodine-131, iodine-133, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed.
All other variables are previously defined.2.2 GASEOUS 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.
Setpoints may be established at values lower than the calculated values if desired.Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.If a calculated setpoint is less than the measured concentration associated with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and the setpoint recalculated.
CPSES -UNITS 1 AND 2- ODCM PARTI12-4 Rev. 33 2.2.1 Plant Vent Effluent Release Rate Monitors XRE-5570A and XRE-5570B Effluent Release Rate Channels The WRGM effluent release rate channels monitor the release rate of radioactive materials from each plant vent stack by combining inputs from the WRGM low range noble gas activity channel (uCi/cm 3) indication and a stack flow rate (cm 3/sec) indication (X-FT-5570A-1/B-1) to yield an effluent release rate (uCi/sec).
By establishing an alarm setpoint for this monitor, an increase in either the noble gas activity or stack flow rate will cause an alarm trip. The WRGM effluent channel also provides an automatic control function for termination of Waste Gas Decay Tank Releases.
The setpoint for each plant vent effluent release rate monitor will be calculated using the following methodology:
QSITE = the lessor of: 500 xS =125 QNG[E.27 NG= D-x SF = t[Eq. 2-7]QNG Dt Dt OR 3000 .QDNN QN6- s x SF = 750 [Eq. 2-6]Where: Qsite Total site noble gas release rate limit corresponding to a dose rate at or beyond the SITE BOUNDARY of 500 mrem/yr to the total body or 3000 mrem/yr to the skin. (uCi/sec)QNG (noble gases) Qi Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with Radiological Effluent Control 3/4.11.2.1, Table 4.11-2.500 = Dose rate limit to the total body of an individual at or beyond the SITE BOUNDARY due to noble gases from all release sources.(mRem/yr)3000 = Dose rate limit to the skin of the body of an individual at or beyond the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)SF Safety Factor of 0.5 applied to compensate for statistical fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks (unitless)
CPSES -UNITS 1 AND 2- ODCM PART 1I12-5 Rev. 33 Then the release rate setpoint for each stack monitor, Cf, in uCi/sec is determined as follows: Cf = Qsite" AF [Eq. 2-7]Where: AF Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitless).
This factor will limit the release rate contribution from each stack to 1/2 the limit for the site.2.2.2 Plant Vent Stack Noble Gas Activity Monitors XRE-5570A/XRE-5570B (WRGM low range noble gas activity channel) and XRE-5567A/XRE-5567B (noble gas channel)The WRGM low range noble gas activity channels provide noble gas concentration data to the effluent release rate channels, as discussed in Section 2.2.1 above. The monitor design does not include an alarm setpoint for this channel that provides an audible alarm if the setpoint is exceeded.
Therefore, setpoint adjustments are not performed for these channels.
Radiological Effluent Control 3/4.3.3.5, Table 3.3-8, ACTION 36 allows for use of the stack noble gas monitors (XRE-5567A and XRE-5567B) as a backup for an inoperable WRGM effluent release rate channel when no automatic control function is required.
The alarm setpoint for these channels, CG, in uCi/cm 3 is determined using the following methodology:
CG = Cf [Eq. 2-8]Where: Fpvs Maximum stack flow rate (cc/sec) corresponding to 115,000 cfm during normal operations and 130,000 cfm during containment purges.2.2.3 Sampler Flow Rate Monitors (X-RFT-5570A-1/B-1)
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.
2.2.4 Auxiliary Building 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 (ABV) Duct Monitor (XRE-5701) to be used as a backup for an inoperable WRGM for monitoring Waste Gas Decay Tank (WGDT) releases.
XRE-5701 monitors WGDT releases by measuring activity in the Auxiliary Building Vent Duct and providing an automatic control function for termination of WGDT releases.
If required, the alarm setpoint for XRE-5701 will be calculated using the following methodology.
The alarm setpoint calculation is based on the following assumption:
CPSES -UNITS 1 AND 2- ODCM PART 11I2-6 Rev. 33 (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).Based on assumption (1) above, there are a maximum of three release sources that may contribute to the total release rate from the site during a WGDT release. These are the WGDT batch release, the continuous release from Stack A, and the continuous release from Stack B. Therefore, a release factor of 1/3 will be used for the ABV monitor setpoint determination.
The total release rate from the site at the alarm setpoint release rate from each stack would correspond to a value of 2Cf uCi/sec. To determine the ABV monitor setpoint, the release rate contribution from the ABV will be limited to 1/3 of the limiting site release rate: Qaux = 1/3
- 2 Cf= 2/3 Cf [Eq. 2-9]Where: Qaux = Limiting release rate contribution from the Auxiliary Building Vent during WGDT releases (uCi/sec)Other terms have been previously defined.To determine the setpoint, Caux, for the ABV monitor in uCi/cc, the limiting ABV release rate is divided by the Maximum ABV flow rate: Caux =Qaux -2Cf [q -u [Eq. 2-10]Faux 3Faux Where: Faux = Maximum ABV flow rate (cc/sec) corresponding to 106,400 cfm.2.2.5 Containment Atmosphere Gaseous Monitors (1RE-5503 and 2RE-5503)For implementation of Technical Specification 3.3.6, the alarm setpoint for the Containment Atmosphere Gaseous Monitor for Containment Ventilation Isolation will be calculated using the following methodology.
The alarm setpoint calculation is based on the following assumption:
(1) a purge or vent from each containment may occur simultaneously and no other batch release is occurring (i.e., a waste gas decay tank release is not occurring at the same time as a containment release).Based on assumption (1) above, there are a maximum of four release sources that may contribute to the total release rate from the site during a containment release. These are a Unit 1 Containment release, a Unit 2 Containment release, the continuous release from Stack A, and the continuous release from Stack B. Therefore, a release factor of 1/4 will be used for the the containment monitor setpoint determination.
The total release rate from the site at the alarm setpoint release rate from each stack would correspond to a value of 2Cf uCi/sec. To determine the containment monitor setpoint, the release rate CPSES -UNITS 1 AND 2- ODCM PART I112-7 Rev. 33 contribution from a containment release will be limited to 1/4 of the limiting site release rate: 1 1[Eq. 2-11]Where: Qcont= Limiting release rate contribution from a containment release (uCi/sec)Other terms have been previously defined.To determine the setpoint, Ccont, for the containment monitor in uCi/cc, the limiting containment release rate is divided by the maximum containment release flow rate: cont = Qcont -Cf Fcont 2 Fcont[Eq. 2-12]Where: Fcont Maximum containment release flow rate (cc/sec) corresponding to 750 cfm for containment vents and 30,000 cfm for containment purges.2.3 DOSE CALCULATIONS FOR GASEOUS EFFLUENTS The methodologies for calculating doses from gaseous effluents are given in Sections 2.3.1 and 2.3.2 below. For purposes of demonstrating compliance with the dose limits of Radiological Effluent Controls 3.11.2.2 and 3.11.2.3, the calculated cumulative doses (i.e., the total dose for both units) will be compared to two times the dose limits for a unit. In other words, the doses assigned to each unit will be one-half of the total doses from all releases from the site.2.3.1 Dose Due to Noble Gases For implementation of Radiological Effluent Control 3/4.11.2.2, the cumulative air dose due to noble gases to areas at and beyond the SITE BOUNDARY will be calculated at least once per 31 days and a cumulative summation of the air doses will be maintained for each calendar quarter and each calendar year. The air dose over the desired time period will be calculated as follows: a. Air Dose Due to Gamma Emissions Dy Air dose due to gamma emissions from noble gas radionuclides from all release sources. (mrad)Dr = 3.17x10-8 (X/Q)E MiQ'i (noble gases)[Eq. 2-13]CPSES -UNITS 1 AND 2- ODCM PART II12-8 Rev. 33 Where: 3.17 x 10-8 = Fraction of a year represented by one second.Q'i = Cumulative release of radionuclide i during the period of interest from all release sources. (uCi)(Q'i = Qi (uCi/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.b. Air Dose Due to Beta Emissions.
Do Air dose due to beta emissions from noble gas radionuclides. (mrad)D 3.17x10-8 (X/Q) NAQ' [Eq. 2-14](noble gases)Where: Ni Air dose factor due to beta emissions from noble gas radionuclide i from Table 2.2.(mRad/yr per uCi/m 3).All other variables are previously defined.NOTE: If the methodology in this section is used in determining dose to an individual rather than air dose due to noble gases, substitute Ki for Mi, (Li + 1.1 Mi) for Ni, and the Annual Average X/Q values from information listed and maintained current in the results of the annual Land Use Census for the highest annual average relative concentration (X/Q) at the SITE BOUNDARY.2.3.2 Dose Due to Radiodines, Tritium, C-14, and Particulates For implementation of Radiological Effluent Control 3/4.11.2.3, the cumulative dose to each organ of an individual due to iodine-131, iodine-133, tritium, C-14, and particulates with half-lives greater than 8 days will be calculated at least once per 31 days and a cumulative summation of these doses will be maintained for each calendar quarter and each calendar year. The dose over the desired period will be calculated as follows: D p = y 3.17x10-8 W' E Rp i,a,o Q! [Eq. 2-15]Paths I&PT CPSES -UNITS 1 AND 2- ODCM PART 1I12-9 Rev. 33 Where: Dp Dose due to all real pathways to organ, o, of an individual in age group, a, from iodine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than eight days from all release sources (mRem).Wr Dispersion parameter for estimating the dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.
Locations of interest are listed in the results of the annual Land Use Census, W = X/Q for the inhalation pathway in sec/m 3.X/Q is the annual average relative concentration at the location of interest.Values for X/Q are listed in the results of the annual Land Use Census. If desired, the highest individual receptor X/Q or X/Q value may be used, or Wf DIQ for the food and ground plane pathways in m-2.D/Q is the annual average deposition at the location of interest.
Values for D/Q are listed in the results of the annual Land Use Census. If desired, the highest individual receptor D/Q or D/Q value may be used.NOTE: For tritium and C-14, the dispersion parameter, W' is taken as the annual average X/Q values from information listed and maintained current in the results of the annual Land Use Census for inhalation, food and ground plane pathways.RPi,a,o Dose factor for radionuclide i, pathway p, age group a and organ o, in mRem/yr per uCi/m 3 for the inhalation pathway and m 2 (mRem/yr) per uCi/sec for food and ground plane pathways, except for tritium which is in mRem/yr per uCi/m 3 for all pathways.
The values for RPi,a,o for each pathway, radionuclide, age group and organ are listed in Table 2.4.The methodioogies used for determining values of RPi,a,o for each pathway are given in Appendices B through F.Q'i Cumulative release of radionuclide, i, during the period of interest (uCi). Q'i is based on the activities measured in each plant vent stack from the analyses of the particulate and iodine samples required by Radiological Effluent Control 3/4.11.2.1, Table 4.11-2. Carbon-14 (C14) airborne activity released to the environment is established based on actual power generation as discussed in Regulatory Guide 1.21, Revision 2. The methodology for estimating C-14 produced and released to the environment via gaseous effluents from CPNPP is provided in"Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", EPRI, Palo Alto, CA: 2010. 1021106.CPSES -UNITS 1 AND 2- ODCM PART II12-10 Rev. 33 I&PT = lodines, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed.
PATHS = The real pathways of exposure to individuals at the locations of interest.2.4 DOSE PROJECTIONS FOR GASEOUS EFFLUENTS Radiological Effluent Control 3/4.11.2.4 requires that appropriate portions of the PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent from a unit to areas at or beyond the SITE BOUNDARY 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 projection:
At least once every 31 days the gamma air dose, beta air dose and the maximum organ dose for each unit for the previous three months will be divided by the number of days in the three month period and multiplied by 31. Also, this dose projection may include the estimated dose due to any anticipated unusual releases during the period for which the projection is made, such as.Waste Gas Decay Tank release. If the projected doses for a unit exceed any of the values listed above, appropriate portions of the PRIMARY PLANT VENTILATION SYSTEM and WASTE GAS HOLDUP SYSTEM shall be used to reduce radioactivity levels prior to release.2.5 DOSE CALCULATIONS TO SUPPORT OTHER REQUIREMENTS For the purpose of implementing the requirements of Radiological Effluent Control 6.9.1.4, the Annual 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 year of operation.
This assessment shall be a summary of the doses determined in accordance with Section 1.3 for doses due to liquid effluents, Section 2.3.1 for air doses due to noble gases, and Section 2.3.2 for doses due to iodines, tritium, and particulates.
This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the SITE BOUNDARY.
This assessment shall be performed in accordance with the methodologies in Section 1.3, 2.3.1, and 2.3.2, using either historical average or concurrent dispersion and deposition parameters for the locations of interest, and taking into account occupancy factors. All assumptions and factors used in the determination shall be included in the report.For the purpose of implementing Radiological Effluent Control 3/4.12.2 dose calculations for the new locations identified in the land use census shall be performed using the methodology in Section 2.3.2, substituting the appropriate pathway receptor dose factors and dispersion parameters for the location(s) of interest.
Annual average dispersion CPSES -UNITS 1 AND 2- ODCM PART II 2-11 Rev. 33 parameters may be used for these calculations.
If the land use census changes, the critical location (i.e., the location where an individual would be exposed to the highest dose) must be reevaluated for the nearest residence, the nearest milk animal, and the nearest vegetable garden. Additionally, when a location is identified that yields a calculated dose 20% greater than at a location where environmental samples are currently being obtained, add the new location within 30 days to the Radiological Environmental Monitoring locations described in Section 3.1 of this manual.For the purpose of implementing Radiological Effluent Control 3/4.11.4, the total annual dose to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by summing the annual doses determined for a member of the public in accordance with the methodology of Sections 1.3, 2.3.1, and 2.3.2 and the direct radiation dose contributions from the units and from outside storage tanks to the particular member of the public. This assessment must be performed in the event calculated doses from the effluent releases exceed twice the limits of Controls 3/4.11.1.2, 3/4.11.2.2, or 3/4.11.2.3.
This assessment will be included in the Annual Radioactive Effluent Release Report to be submitted the year after the assessment was required.
Otherwise, no assessments are required.For the evaluation of doses to real individuals from liquid releases, the same calculation methods as employed in Section 1.3 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides.
The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide concentrations.
For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as employed in Sections 2.3.1 and 2.3.2 will be used. In Sections 2.3.1, the total body dose factor should be substituted for the gamma air dose factor (Mi) 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 Monitoring Program will be included in determining more realistic doses based on actual measured radionuclide concentrations.
The dose component due to direct radiation may be determined by calculation or actual measurement (e.g., TLD (Thermoluminescent Dosimeter)
Badge, micro-R meter). The calculation or actual measurement of direct radiation shall be documented in the Special Report that must be submitted if this determination is required.2.6 METEOROLOGICAL MODEL 2.6.1 Dispersion Calculations Atmospheric dispersion for gaseous releases is 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 CPSES -UNITS 1 AND 2- ODCM PART II12-12 Rev. 33 account for plume depletion and effects of the open terrain. The average relative concentration is given by the following equation:-= 2.0328 K Q Where: X/Q Yk j,k njk (NrOjk I j(rý[Eq. 2-16]Average concentration normalized by source strength. (sec/m 3)2.032 = (2/n)1/2 (21/16)-1.8 K njk= Plume depletion factor at distance r for the applicable stability class (Figure 2.2). Normally, a value of 1.0 is assumed when undepleted X/Q values are to be used in dose calculations.
= Terrain correction factor (Figure 2.5).Number of hours meteorological conditions are observed to be in a given wind direction, wind speed class, k, and atmospheric stability class, j.N Total hours of valid meteorological data throughout the period of release.NOTE: If hourly meteorological data are used, all variable subscripts are dropped, nJk and N are set equal to 1, and the hourly averaged meteorological variables are used in the model.r FUj k Downwind distance from the release point to the location of interest. (meters)Average windspeed (midpoint of windspeed class, k) measured at the 10 meter level during stability class j. (meters/sec)
= Vertical plume spread with a volumetric correction for a release within the building wake cavity, at a distance, r, for stability class, j, expressed in meters.NOTE: All parameters are considered dimensionless unless otherwise indicated.
The equation for calculating 1j(r) is: Zj(r) = the lesser of{(o2 + 0.5 b 2/7r)2 j F3oT[Eq. 2-17][Eq. 2-18]CPSES -UNITS 1 AND 2- ODCM PART I112-13 Rev. 33 Where: j = Vertical standard deviation of materials in the plume at distance, r, for atmospheric stability class, j, expressed in meters (Figure 2.3).0.5 = Building shape factor.b = Vertical height of the reactor containment structure (79.4 meters).2.6.2 Deposition Calculations The relative deposition per unit area is calculated as follows: D _ KDgZ [Eq. 2-19]Q 0.3927 r Where: D/Q = Deposition per unit area normalized by source strength (m-2)Dg = Relative deposition rate for a ground level release (m-1)(Figure 2.4)z -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 = Width in radians of a 22.50 sector.Other variables are as previously defined.NOTE: All parameters are considered dimensionless unless otherwise indicated.
2.7 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS TERM DEFINITION AF Allocation Factor of 0.5 applied to account for releases from both stacks simultaneously.
This factor will limit the release rate contribution from each stack to 1/2 the limit for the site.B vertical height of the reactor containment structure.
CG the alarm setpoint for each plant vent stack noble gas activity monitor.(uCi/cm 3)Cf the alarm setpoint for each plant vent stack effluent release rate monitor.(uCi/sec)Caux the Auxiliary Building Ventilation Exhaust monitor alarm setpoint.(uCi/cm 3)Ccont the Containment Atmosphere Gaseous monitor alarm setpoint. (uCi/cm 3)CPSES -UNITS 1 AND 2- ODCM PART I112-14 Rev. 33 TERM DEFINITION Dg relative deposition rate for a ground-level release. (m-1)Do the total organ dose rate due to tritium, iodines, and particulates with half-lives greater than eight days from all gaseous release sources.(mRem/yr)Dov the organ dose rate due to tritium, iodines, and particulates with half-lives greater than eight days from gaseous release source v. (mRem/yr)Dp dose to any organ of an individual from radioiodines, tritium and radionuclides in particulate form with half-lives greater than eight days from all release sources. (mRem)Ds Skin dose rate at the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)Dsv Skin dose rate at the SITE BOUNDARY due to noble gases from release source v. (mRem/yr)Dt Total body dose rate at the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)Dtv Total body dose rate at the SITE BOUNDARY due to noble gases from release source v. (mRem/yr)Do3 Air dose due to beta emissions from noble gases from all release sources. (mRad)Dy Air dose due to gamma emissions from noble gases from all release sources. (mRad)D/Q Annual average relative deposition at the location of interest. (m-2)8 Plume depletion factor at distance r for the appropriate stability class (radioiodines and particulates).
Fv Flow rate from each release source v. (cm 3/sec)Faux Maximum Auxiliary Building Ventilation flow rate (cm 3/sec) corresponding to 106,400 cfm.Fcont Maximum containment release flow rate (cm 3/sec) corresponding to 750 cfm for containment vents and 30,000 cfm for containment purges.Fpvs Maximum stack flow rate (cc/sec) corresponding to 115,000 cfm during normal operations and 130,000 cfm during containment purges.K terrain correction factor. (unitless)
Ki total body dose factor due to gamma emissions from noble gas radionuclide
- i. (mRem/yr per uCi/m 3)Li skin dose factor due to beta emissions from noble gas radionuclide i.(mRem/yr per uCi/m 3)Mi air dose factor due to gamma emissions from noble gas radionuclide i.(mrad/yr per uCi/m 3)CPSES -UNITS 1 AND 2- ODCM PART I112-15 Rev. 33 TERM DEFINITION Ni air dose factor due to beta emissions from noble gas radionuclide i.(mrad/yr per uCi/m 3)nik number of hours meteorological conditions are observed to be in a given wind direction, wind speed class k, and atmospheric stability class j.N total hours of valid meteorological data.Pi pathway dose rate parameter for radionuclide i, (other than noble gases)for the inhalation pathway. (mRem/yr per uCi/cm 3)Qaux the limiting release rate contribution from the Auxiliary Building Vent during WGDT releases. (uCi/sec)Qcont the limiting release rate contribution from a containment release.(uCi/sec)Qi total release rate of radionuclide i from all release sources. (uCi/sec)Qiv Total release rate of radionuclide i from release source v. (uCi/sec)Q'i Cumulative release of radionuclide i during the period of interest from all release sources. (uCi)QNG Actual release rate of noble gases from all release sources as calculated from the radionuclide concentrations determined from analyses of samples taken in accordance with Control 3/4.11.2.1, Table 4.11-2.QSITE Total site noble gas release rate limit corresponding to a dose rate at or beyond the SITE BOUNDARY of 500 mRem/yr to the total body or 3000 mRem/yr to the skin. (uCi/sec)RPi,a,o Dose factor for radionuclide i, pathway p, and age group a, and organ o (mRemlyr per uCi/m 3) or(m 2-mRem/yr per uCi/sec).r Distance from the point of release to the location of interest for dispersion calculations. (meters)SF Safety Factor of 0.5 applied to compensate for statistical fluctuations, errors of measurement, and non-uniform distribution of release activity between the stacks.Xi(r) Vertical plume spread with a volumetric correction for a release within the building wake cavity, at a distance, r, for stability class, j, expressed in meters.Gi Vertical standard deviation of the plume concentration (in meters), at distance, r, for stability category j.Ujk Wind speed (midpoint of windspeed class k) at ground level (m/sec)during atmosphere stability class j.W' Dispersion parameter for estimating the dose to an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum exposures.
X/Q Annual average relative concentration at the location of interest. (sec/m 3)CPSES -UNITS 1 AND 2- ODCM PART 1I12-16 Rev. 33 TERM DEFINITION X/-Q Highest annual average relative concentration at the SITE BOUNDARY.(sec/m 3) (3.3 x 10-6 sec/m 3 in the NNW sector)Xiv Measured concentration of radionuclide i present in each release source v. (uCi/cm 3).z Fraction of time the wind blows to the sector of interest.1.1 Conversion factor of mRem skin dose per mRad air dose.500 Dose rate limit to the total body of an individual at or beyond the SITE BOUNDARY due to noble gases from all release sources. (mRem/yr)3000 Dose rate limit to the skin of the body of the individual at or beyond the SITE BOUNDARY due to noble gases from all release sources.(mRem/yr)CPSES- UNITS 1 AND 2- ODCM PART 11 2-17 Rev. 33 TABLE 2.1
SUMMARY
OF GASEOUS RELEASE PATHWAYS 1. RELEASES VIA THE PLANT VENT STACKS RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfm)MONITOR(S)
Stack A Stack B WGDT's U-1 Cont. Vent.U-1 Cont. Purge U-2 Cont. Vent.U-2 Cont. Purge Continuous Continuous Batch Batch Batch Batch Batch 115,000 115,000 20 750 30,000 750 30,000 XRE-5570A/XRE-5567A XRE-5570B/XRE-5567B XRE-5570A&B/XRE-5701 1 RE-5503 1 RE-5503 2RE-5503 2RE-5503 2. RELEASES VIA THE ILRT VENT RELEASE SOURCE RELEASE TYPE MAX. FLOW RATE (cfm)MONITOR(S)
ILRT Batch 3) RELEASES FROM OUTSIDE BUILDINGS I RELEASE SOURCE Outside Buildings RELEASE TYPE Continuous or Batch MAX. FLOW RATE (cfm)MONITOR(S)
CPSES -UNITS 1 AND 2- ODCM PART II12-18 Rev. 26 TABLE 2.2DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES P3-Skin***(L)
Isotope y-Body***(K) y-Air**(M) p-Air**(N)
Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr- 90 Xe-131m Xe-1 33m Xe-1 33 Xe-1 35m Xe-1 35 Xe-137 Xe-138 Ar-41 7.56E-02 1.17E+03 1.61 E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51 E+02 2.94E+02 3.12E+03 1.81E+03 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01 E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11 E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51 E+03 9.21 E+03 9.30E+03 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03*Values taken from Reference 2, Table B-1 mrad-m 3 pCi-yr 3 mrem-m ptCi-yr CPSES -UNITS 1 AND 2- ODCM PART II12-19 Rev. 23 TABLE 2.3PATHWAY DOSE RATE PARAMETER (Pl)*BASED ON THE INHALATION PATHWAY FOR THE CHILD AGE GROUP NUCLIDEF ORGAN DOSE FACTORS H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-A11M TE-1 25M TE-127M TE-1 29M 1-131 1-133 CS-1 34 CS-136 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 3.59E+04 2.60E+06 0.00E+00 O.OOE+00 4.74E+04 2.07E+04 0.OOE+00 0.OOE+00 8.21 E+05 4.26E+04 0.OOE+00 5.99E+05 1.01 E+08 9.14E+05 1.90E+05 2.35E+04 2.79E+03 1.36E+05 1.69E+04 6.73E+03 2.49E+04 1.92E+04 4.81 E+04 1.66E+04 6.51 E+05 6.51 E+04 9.07E+05 7.40E+04 3.92E+04 6.77E+06 1.85E+04 1.08E+04 LIVER 1.12E+03 6.73E+03 1.14E+05 0.OOE+00 4.29E+04 2.52E+04 3.34E+04 1.77E+03 1.31E+04 4.63E+04 1.13E+05 1.98E+05 0.OOE+00 0.OOE+00 O.OOE+00 4.18E+04 9.18E+03 0.OOE+00 0.OOE+O0 1.14E+04 2.33E+03 8.55E+03 6.85E+03 4.81 E+04 2.03E+04 1.01 E+06 1.71 E+05 8.25E+05 6.48E+01 1.95E+04 2.12E+06 5.55E+03 8.73E+03 T. BODY 1.12E+03 6.73E+03 9.88E+04 1.54E+02 9.51 E+03 7.77E+03 1.67E+04 3.16E+03 2.26E+04 2.80E+04 7.03E+04 1.14E+05 1.72E+04 6.44E+06 2.44E+04 3.70E+04 6.55E+03 1.07E+03 1.69E+04 9.14E+03 9.14E+02 3.02E+03 3.04E+03 2.73E+04 7.70E+03 2.25E+05 1.16E+05 1.28E+05 4.33E+03 2.90E+03 3.61 E+05 9.14E+02 6.81 E+02 THYROID 1T.12E+03 6.73E+03 0.OOE+00 8.55E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 O.00E+00 0.OOE+00 1.92E+03 6.07E+03 6.33E+03 1.62E+07 3.85E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY T.12E+03 6.73E+03 0.OOE+00 2.43E+01 1.OOE+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 7.14E+04 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 5.96E+04 8.62E+03 7.03E+03 1.84E+05 2.12E+04 O.OOE+00 6.36E+04 5.03E+04 7.88E+04 3.38E+04 3.30E+05 9.55E+04 2.82E+05 2.11E+01 8.55E+03 1.17E+06 3.OOE+03 4.81 E+03 LUNG 1.12E+03 6.73E+03 0.OOE+00 1.70E+04 1.58E+06 1.11E+05 1.27E+06 1.11 E+06 7.07E+06 2.75E+05 9.95E+05 0.OOE+00 2.16E+06 1.48E+07 2.63E+06 2.23E+06 6.14E+05 6.62E+05 1.43E+07 5.48E+06 4.77E+05 1.48E+06 1.76E+06 0.OOE+00 0.OOE+00 1.21E+05 1.45E+04 1.04E+05 1.74E+06 5.44E+05 1.20E+07 4.33E+05 3.28E+05 GI-LLI 1.12E+03 6.73E+03 4.22E+04 1.08E+03 2.29E+04 2.87E+03 7.07E+04 3.44E+04 9.62E+04 6.33E+03 1.63E+04 7.99E+03 1.67E+05 3.43E+05 1.84E+05 6.11 E+04 3.70E+04 4.48E+04 4.29E+05 1.OOE+05 3.38E+04 7.14E+04 1.82E+05 2.84E+03 5.48E+03 3.85E+03 4.18E+03 3.62E+03 1.02E+05 5.66E+04 3.89E+05 9.73E+04 8.21 E+04 CPSES- UNITS 1 AND 2- ODCM PART II12-20 Rev. 32 TABLE 2.4PATHWAY DOSE FACTORS AGE GROUP: ALL NUCLIDE I H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-1 06 AG-11OM TE-1 25M TE-1 27M TE-129M 1-131 1-133 CS-134 CS-1 36 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 PATHWAY: GROUND PLANE ORGAN DOSE FACTORS T. BODY S 0.OOE+00 0.0(0.00E+00 0.01 0.OOE+00 0.01 4.65E+06 5.5'1.39E+09 1.6: O.00E+00 0.0'2.73E+08 3.2 3.79E+08 4.4 2.15E+10 2.5 0.OOE+00 0.0 7.47E+08 8.5 8.97E+06 1.0 2.16E+04 2.5 0.OOE+00 0.0 1.07E+06 1.2 2.45E+08 2.8 1.37E+08 1.6 1.08E+08 1.2 4.22E+08 5.0 3.44E+09 4.0 1.55E+06 2.1 9.17E+04 1.0 1.98E+07 2.3 1.72E+07 2.0 2.45E+06 2.9 6.86E+09 8.C 1.51E+08 1.03E+10 2.06E+07 2.1.37E+07 1.1 6.96E+07 8.C 0.OOE+00 0.8.39E+06 1 .KIN 0E+00 0E+00 0E+00 0E+06 2E+09 0E+00 1 E+08 4E+08 3E+10 OE+00 9E+08 3E+07 1 E+04 OE+00 1E+06 4E+08 1E+08.6E+08 6E+08 1E+09 3E+06)8E+05 V1E+07)9E+07 18E+06)OE+09!1E+08 20E+10 36E+07 54E+07)5E+07)OE+00)1E+07 I CPSES -UNITS 1 AND 2- ODCM PART I112-21 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS -COW -MILK ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 N 1-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-11iM TE-125M TE-1 27M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 2.25E+04 1.70E+10 0.OOE+00 0.OOE+00 2.51 E+07 2.97E+07 0.OOE+00 0.00E+00 6.72E+09 1.37E+09 0.OOE+00 1.45E+09 4.67E+1 0 8.57E+03 9.41 E+02 8.24E+04 1.02E+03 2.04E+04 5.81 E+07 1.63E+07 4.57E+07 6.01E+07 2.96E+08 3.87E+06 5.64E+09 2.63E+08 7.37E+09 2.69E+07 4.84E+03 3.57E+05 1.57E+02 9.40E+01 LIVER 7.62E+02 4.50E+03 1.06E+09 0.OOE+00 8.40E+06 1.73E+07 6.97E+07 4.71 E+06 1.64E+07 4.65E+08 4.36E+09 2.59E+09 0.OOE+00 0.OOE+00 0.OOE+00 3.02E+02 4.58E+04 0.OOE+00 0.OOE+00 5.38E+07 5.89E+06 1.63E+07 2.24E+07 4.23E+08 6.73E+06 1.34E+10 1.04E+09 1.01E+10 3.38E+04 3.27E+03 1.49E+05 6.32E+01 1.09E+02 T. BODY 7.62E+02 4.50E+03 6.58E+08 2.85E+04 1.60E+06 4.04E+06 2.67E+07 1.05E+07 3.61 E+07 2.25E+08 1.97E+09 1.21 E+09 4.16E+07 1.15E+10 2.29E+02 2.04E+02 2.46E+04 4.38E+02 2.58E+03 3.19E+07 2.18E+06 5.57E+06 9.51E+06 2.42E+08 2.05E+06 1.10E+10 7.48E+08 6.60E+09 1.76E+06 3.71 E+02 1.92E+04 7.81 E+00 6.50E+00 THYROID 7.62E+02 4.50E+03 0.OOE+00 1.70E+04 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.89E+06 1.17E+07 2.06E+07 1.39E+1 1 9.88E+08 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 7.62E+02 4.50E+03 0.OOE+00 6.28E+03 2.50E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.91E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.74E+02 4.53E+04 3.88E+03 3.93E+04 1.06E+08 6.61 E+07 1.86E+08 2.51 E+08 7.25E+08 1.17E+07 4.34E+09 5.78E+08 3.42E+09 1.15E+04 1.52E+03 8.85E+04 3.65E+01 6.35E+01 LUNG 7.62E+02 4.50E+03 O.OOE+00 3.78E+04 0.OOE+00 9.66E+06 1.95E+07 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.44E+09 7.92E+07 1.14E+09 1.94E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 7.62E+02 4.50E+03 1.91 E+09 7.17E+06 2.57E+07 9.93E+06 2.32E+08 9.54E+07 3.08E+08 9.71 E+07 2.74E+09 5.1OE+08 2.32E+08 1.35E+09 4.72E+06 9.57E+05 2.78E+08 1.19E+05 1.32E+06 2.19E+10 6.49E+07 1.53E+08 3.02E+08 1.12E+08 6.04E+06 2.35E+08 1.18E+08 1.95E+08 5.54E+07 1.25E+07 1.21 E+08 6.90E+05 5.22E+05 CPSES -UNITS 1 AND 2- ODCM PART II12-22 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS -COW -MILK ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 N 1-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 N B-95 RU-103 RU-106 AG-11OM TE-1 25M TE-127M TE-129M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-1 40 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 4.15E+04 3.15E+10 0.OOE+00 0.OOE+00 4.46E+07 5.19E+07 0.OOE+00 0.OOE+00 1.18E+10 2.11E+09 0.00E+00 2.68E+09 6.62E+10 1.58E+04 1.65E+03 1.41 E+05 1.81 E+03 3.76E+04 9.64E+07 3.01 E+07 8.45E+07 1.10E+08 5.38E+08 7.08E+06 9.83E+09 4.49E+08 1.34E+10 4.87E+07 8.89E+03 6.59E+05 2.90E+02 1.81E+02 LIVER 9.93E+02 8.31 E+03 1.95E+09 0.OOE+00 1.40E+07 3.16E+07 1.21 E+08 7.94E+06 2.78E+07 8.36E+08 7.32E+09 4.73E+09 0.OOE+00 0.OOE+00 0.OOE+00 5.21E+02 7.82E+04 0.OOE+00 0.OOE+00 9.12E+07 1.08E+07 3.OOE+07 4.09E+07 7.53E+08 1.20E+07 2.31 E+1 0 1.77E+09 1.78E+10 5.97E+04 5.94E+03 2.73E+05 1.16E+02 1.97E+02 T. BODY 9.93E+02 8.31 E+03 1.22E+09 4.99E+04 2.78E+06 7.37E+06 4.68E+07 1.83E+07 6.27E+07 4.01 E+08 3.42E+09 2.22E+09 7.67E+07 1.63E+10 4.24E+02 3.58E+02 4.30E+04 7.75E+02 4.73E+03 5.55E+07 4.02E+06 1.OOE+07 1.74E+07 4.05E+08 3.66E+06 1.07E+10 1.19E+09 6.21 E+09 3.14E+06 6.82E+02 3.54E+04 1.44E+01 1.18E+01 THYROID 9.93E+02 8.31 E+03 0.OOE+00 2.77E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 8.40E+06 2.01 E+07 3.56E+07 2.20E+ 11 1.68E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 9.93E+02 8.31 E+03 0.OOE+00 1.09E+04 4.19E+06 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 4.69E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.65E+02 7.58E+04 6.39E+03 7.24E+04 1.74E+08 0.OOE+00 3.42E+08 4.61 E+08 1.30E+09 2.11 E+07 7.35E+09 9.63E+08 6.06E+09 2.02E+04 2.80E+03 1.63E+05 6.73E+01 1.16E+02 LUNG 9.93E+02 8.31 E+03 0.OOE+00 7.13E+04 0.OOE+00 2.01 E+07 3.82E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.81 E+09 1.52E+08 2.36E+09 4.01 E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 9.93E+02 8.31 E+03 2.65E+09 8.39E+06 2.88E+07 1.37E+07 2.86E+08 1.10E+08 3.62E+08 1.33E+08 3.1 OE+09 7.OOE+08 3.19E+08 1.86E+09 6.48E+06 1.20E+06 3.34E+08 1.51E+05 1.80E+06 2.56E+10 8.87E+07 2.11 E+08 4.14E+08 1.49E+08 9.09E+06 2.88E+08 1.42E+08 2.54E+08 7.51 E+07 1.70E+07 1.66E+08 9.55E+05 7.12E+05 I CPSES -UNITS 1 AND 2- ODCM PART II12-23 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS -COW -MILK ORGAN DOSE FACTORS NUCLIDE NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 N 1-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-11OM TE-125M TE-1 27M TE-1 29M 1-131 1-133 CS-1 34 CS-136 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE LIVER 0.00E+00 1.57E+03 1.02E+05 2.04E+04 7.77E+10 3.64E+09 0.OOE+00 0.OOE+00 0.OOE+00 2.1OE+07 1.12E+08 5.94E+07 1.20E+08 1.95E+08 0.OOE+00 1.21E+07 0.00E+00 4.32E+07 2.97E+10 1.59E+09 4.14E+09 1.10E+1o 0.OOE+00 8.78E+09 6.63E+09 0.00E+00 1.12E+ii 0.OOE+00 3.91E+04 0.OOE+00 3.84E+03 8.43E+02 3.18E+05 1.24E+05 4.29E+03 0.00E+00 9.25E+04 0.OOE+00 2.09E+08 1.41E+08 7.39E+07 2.OOE+07 2.08E+08 5.61E+07 2.72E+08 7.59E+07 1.31E+09 1.31E+09 1.72E+07 2.13E+07 2.27E+10 3.72E+10 1.01E+09 2.79E+09 3.23E+10 3.09E+10 1.18E+08 1.03E+05 2.19E+04 1.09E+04 1.63E+06 5.09E+05 7.18E+02 2.16E+02 4.45E+02 3.61E+02 T. BODY 1.57E+03 2.04E+04 3.OOE+09 1.02E+05 5.59E+06 1.84E+07 9.70E+07 3.72E+07 1.27E+08 1.01E+09 6.86E+09 5.40E+09 1.89E+08 2.84E+10 1.05E+03 7.51 E+02 8.86E+04 1.65E+03 1.15E+04 1.13E+08 9.85E+06 2.47E+07 4.22E+07 7.46E+08 8.05E+06 7.85E+09 1.80E+09 4.56E+09 6.86E+06 1.62E+03 8.67E+04 3.56E+01 2.79E+01 THYROID 1.57E+03 2.04E+04 0.OOE+00 5.65E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.07E+07 4.98E+07 8.76E+07 4.34E+ 1i 3.95E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 1.57E+03 2.04E+04 0.OOE+00 1.54E+04 5.89E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.95E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.21 E+03 1.16E+05 1.08E+04 1.25E+05 2.63E+08 0.OOE+00 5.94E+08 7.98E+08 2.16E+09 3.55E+07 1.15E+10 1.49E+09 1.01E+10 3.35E+04 4.79E+03 2.82E+05 1.17E+02 1.98E+02 LUNG 1.57E+03 2.04E+04 0.OOE+00 1.03E+05 0.OOE+00 3.36E+07 5.65E+07 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.14E+09 2.21 E+08 3.62E+09 6.14E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 1.57E+03 2.04E+04 2.15E+09 5.40E+06 1.76E+07 1.10E+-07 2.03E+08 7.08E+07 2.39E+08 1.07E+08 1.94E+09 5.65E+08 2.57E+08 1.51 E+09 5.21 E+06 8.80E+05 2.29E+08 1.11E+05 1.44E+06 1.68E+10 7.13E+07 1.69E+08 3.31 E+08 1.17E+08 8.58E+06 2.01 E+08 9.80E+07 1.93E+08 5.96E+07 1.36E+07 1.33E+08 7.75E+05 5.71 E+05 CPSES -UNITS 1 AND 2- ODCM PART II12-24 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS -COW -MILK ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-1 06 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-1 34 CS-136 CS-137 BA-140 CE-141 CE-144 PR-143 BONE 0.OOE+00 1.82E+05 1.60E+1i 0.OOE+00 0.OOE+00 1.35E+08 2.25E+08 0.OOE+00 O.OOE+00 3.50E+10 5.56E+09 0.OOE+00 1.26E+10 1.22E+i1 7.34E+04 6.81 E+03 5.94E+05 8.68E+03 1.91 E+05 3.86E+08 1.51E+08 4.22E+08 5.58E+08 2.72E+09 3.63E+07 3.65E+10 1.98E+09 5.15E+10 2.42E+08 4.34E+04 2.33E+06 1.49E+03 LIVER 2.38E+03 3.88E+04 9.42E+09 0.OOE+00 3.91 E+07 8.74E+07 3.93E+08 2.43E+07 8.83E+07 2.16E+09 1.91E+10 2.23E+10 0.OOE+00 0.OOE+00 0.OOE+00 1.66E+03 2.45E+05 0.OOE+00 0.OOE+00 2.82E+08 5.05E+07 1.40E+08 1.91 E+08 3.21 E+09 5.29E+07 6.81E+10 5.83E+09 6.03E+10 2.42E+05 2.65E+04 9.53E+05 5.56E+02 T. BODY 2.38E+03 3.88E+04 6.21 E+09 1.61E+05 8.85E+06 2.34E+07 1.55E+08 6.06E+07 2.08E+08 1.21 E+09 8.79E+09 1.10E+10 3.62E+08 3.10E+10 1.95E+03 1.18E+03 1.41 E+05 2.90E+03 2.38E+04 1.87E+08 2.04E+07 5.10E+07 8.59E+07 1.41 E+09 1.55E+07 6.88E+09 2.18E+09 4.27E+09 1.25E+07 3.12E+03 1.30E+05 7.37E+01 THYROID 2.38E+03 3.88E+04 0.OOE+00 1.05E+05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.08E+07 1.22E+08 2.14E+08 1.05E+12 9.62E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 2.38E+03 3.88E+04 0.OOE+00 2.30E+04 8.65E+06 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.24E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.79E+03 1 .75E+05 1.81 E+04 2.25E+05 4.03E+08 0.OOE+00 1.04E+09 1.39E+09 3.75E+09 6.22E+07 1.75E+10 2.32E+09 1.62E+10 5.75E+04 8.17E+03 3.85E+05 2.07E+02 LUNG GI-LLI 2.38E+03 2.38E+03 3.88E+04 3.88E+04 0.OOE+00 2.17E+09 2.05E+05 4.70E+06 0.OOE+00 1.43E+07 4.27E+07 1.11E+07 1.16E+08 1.88E+08 0.OOE+00 6.05E+07 0.OOE+00 2.1OE+08 0.OOE+00 1.08E+08 0.OOE+00 1.61E+10 0.OOE+00 5.70E+08 0.OOE+00 2.59E+08 O.OOE+00 1.52E+09 0.OOE+00 5.26E+06 0.OOE+00 8.27E+05 0.OOE+00 2.07E+08 0.OOE+00 1.06E+05 0.OOE+00 1.45E+06 0.OOE+00 1.46E+10 0.OOE+00 7.19E+07 0.OOE+00 1.70E+08 0.00E+00 3.33E+08 0.OOE+00 1.15E+08 0.OOE+00 8.96E+06 7.19E+09 1.85E+08 4.75E+08 8.85E+07 6.55E+09 1.89E+08 1.49E+05 5.94E+07 0.OOE+00 1.37E+07 0.OOE+00 1.34E+08 0.OOE+00 7.84E+05 I ND-147 8.83E+02 9.07E+02 5.55E+01 O.OOE+00 3.50E+02 0.OOE+00 5.75E+05 CPSES -UNITS 1 AND 2- ODCM PART 1I12-25 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS -COW -MEAT ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE O.00E+00 2.06E+04 4.63E+09 0.OOE+00 0.00E+00 2.93E+08 2.66E+08 0.00E+00 0.OOE+0Q 1.89E+10 3.56E+08 0.00E+00 3.02E+08 1.24E+10 1.13E+06 1.87E+06 2.30E+06 1.05E+08 2.80E+09 6.68E+06 3.59E+08 1.12E+09 1.13E+09 1.08E+07 3.68E-01 6.58E+08 1.21 E+07 8.72E+08 2.90E+07 1.41 E+04 1.46E+06 2.09E+04 7.08E+03 LIVER 3.24E+02 4.13E+03 2.88E+08 0.OOE+00 9.18E+06 2.03E+08 6.25E+08 1.82E+07 7.52E+07 1.31E+09 1 .13E+09 4.87E+08 0.OOE+00 0.OOE+00 0.OOE+00 6.01 E+05 1.28E+06 0.00E+00 0.00E+00 6.18E+06 1.30E+08 3.99E+08 4.23E+08 1.54E+07 6.41 E-01 1.57E+09 4.78E+07 1.19E+09 3.64E+04 9.51 E+03 6.1OE+05 8.40E+03 8.18E+03 T. BODY 3.24E+02 4.13E+03 1.79E+08 7.04E+03 1..75E+06 4.73E+07 2.39E+08 4.09E+07 1.66E+08 6.33E+08 5.12E+08 2.27E+08 8.66E+06 3.05E+09 3.03E+04 4.07E+05 6.87E+05 4.53E+07 3.54E+08 3.67E+06 4.81 E+07 1.36E+08 1.79E+08 8.82E+06 1.95E-01 1.28E+09 3.44E+07 7.82E+08 1.90E+06 1.08E+03 7.83E+04 1.04E+03 4.90E+02 THYROID 3.24E+02 4.13E+03 0.OOE+00 4.21 E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.08E+08 2.85E+08 3.89E+08 5.04E+09 9.42E+01 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 KIDNEY 3.24E+02 4.13E+03 0.OOE+00 1.55E+03 2.73E+06 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.00E+00 7.57E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.43E+05 1.26E+06 4.02E+08 5.41 E+09 1.22E+07 1.46E+09 4.53E+09 4.73E+09 2.64E+07 1.12E+00 5.07E+08 2.66E+07 4.05E+08 1.24E+04 4.42E+03 3.62E+05 4.85E+03 4.78E+03 LUNG 3.24E+02 4.13E+03 0.00E+00 9.35E+03 0.OOE+00 1.13E+08 1.75E+08 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 1.68E+08 3.65E+06 1.35E+08 2.08E+04 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 GI-LLI 3.24E+02 4.13E+03 5.21 E+08 1.77E+06 2.81 E+07 1.16E+08 2.08E+09 3.70E+08 1.41E+09 2.73E+08 7.13E+08 9.59E+07 4.84E+07 3.60E+08 6.24E+08 1.90E+09 7.76E+09 1.23E+10 1.81 E+11 2.52E+09 1.43E+09 3.74E+09 5.71 E+09 4.06E+06 5.76E-01 2.74E+07 5.43E+06 2.31 E+07 5.96E+07 3.64E+07 4.93E+08 9.17E+07 3.93E+07 CPSES -UNITS 1 AND 2- ODCM PART 1I 2-26 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS -COW -MEAT ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-i1 OM TE-1 25M TE-127M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 1.74E+04 3.91 E+09 0.OOE+00 0.OOE+00 2.38E+08 2.12E+08 0.OOE+00 O.OE+00 1.52E+10 2.50E+08 O.OOE+00 2.55E+08 8.04E+09 9.54E+05 1.50E+06 1.79E+06 8.56E+07 2.36E+09 5.06E+06 3.03E+08 9.41E+08 9.49E+08 8.93E+06 3.08E-01 5.23E+08 9.43E+06 7.24E+08 2.39E+07 1.18E+04 1.23E+06 1.76E+04 6.23E+03 LIVER 1.93E+02 3.49E+03 2.42E+08 0.OOE+00 7.OOE+06 1.69E+08 4.95E+08 1.40E+07 5.83E+07 1.07E+09 8.68E+08 4.06E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.73E+05 9.95E+05 0.OOE+00 O.OOE+00 4.78E+06 1.09E+08 3.34E+08 3.52E+08 1.25E+07 5.22E-01 1.23E+09 3.71 E+07 9.63E+08 2.93E+04 7.87E+03 5.08E+05 7.03E+03 6.78E+03 T. BODY 1.93E+02 3.49E+03 1.52E+08 5.63E+03 1.39E+06 3.94E+07 1.91 E+08 3.24E+07 1.31 E+08 5.15E+08 4.05E+08 1.91 E+08 7.29E+06 1.99E+09 2.56E+04 3.25E+05 5.48E+05 3.66E+07 2.97E+08 2.91 E+06 4.05E+07 1.12E+08 1.50E+08 6.72E+06 1.59E-01 5.71 E+08 2.49E+07 3.35E+08 1.54E+06 9.05E+02 6.60E+04 8.76E+02 4.06E+02 THYROID 1.93E+02 3.49E+03 0.OOE+00 3.13E+03 0.OOE+00 o.OOE+00 O.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 O.OOE+00 O.OOE+00 o.OOE+00 O.OOE+00 0.0OE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 8.46E+07 2.24E+08 3.06E+08 3.65E+09 7.29E+01 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 KIDNEY 1.93E+02 3.49E+03 0.OOE+00 1.23E+03 2.09E+06 0.OOE+00 O.OE+00 0.OOE+00 O.OE+00 0.OOE+00 5.56E+08 0.OOE+00 o.OOE+00 0.OOE+00 0.OOE+00 6.95E+05 9.64E+05 3.02E+08 4.54E+09 9.13E+06 0.OOE+00 3.81 E+09 3.97E+09 2.15E+07 9.16E-01 3.91 E+08 2.02E+07 3.28E+08 9.94E+03 3.71 E+03 3.03E+05 4.08E+03 3.98E+03 LUNG 1.93E+02 3.49E+03 0.OOE+00 8.03E+03 0.OOE+00 1.07E+08 1.56E+08 0.OOE+00 O.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 o.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.O0E+00 0.0OE+00 O.OOE+00 0.OOE+00 1.49E+08 3.1 8E+06 1.27E+08 1.97E+04 0.OOE+00 O.OOE+00 O.OOE+00 0.0OE+00 GI-LLI 1.93E+02 3.49E+03 3.29E+08 9.46E+05 1.44E+07 7.31E+07 1.17E+09 1.94E+08 7.60E+08 1.71 E+08 3.68E+08 6.OOE+07 3.03E+07 2.26E+08 3.91 E+08 1.09E+09 4.25E+09 7.15E+09 1.13E+11 1.34E+09 8.94E+08 2.35E+09 3.56E+09 2.47E+06 3.95E-01 1.53E+07 2.99E+06 1.37E+07 3.69E+07 2.25E+07 3.09E+08 5.79E+07 2.44E+07 CPSES -UNITS I AND 2- ODCM PART II12-27 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS -COW -MEAT NUCLIDE ORGAN DOSE FACTORS H-3 C-1 4 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 N 1-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-I IOM TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 3.28E+04 7.38E+09 0.OOE+00 0.OOE+00 4.57E+08 3.77E+08 0.OOE+00 0.OOE+00 2.91E+10 3.76E+08 0.OOE+00 4.82E+08 1.04E+10 1.80E+06 2.66E+06 3.1OE+06 1.55E+08 4.44E+09 8.39E+06 5.69E+08 1.78E+09 1.79E+09 1.66E+07 5.72E-01 9.23E+08 1.63E+07 1.33E+09 4.42E+07 2.22E+04 2.32E+06 3.33E+04 1.17E+04 LIVER 2.34E+02 6.56E+03 3.45E+08 O.OOE+00 8.01 E+06 2.43E+08 6.1 OE+08 1.64E+07 6.93E+07 1.56E+09 1.OOE+09 5.76E+08 0.O0E+00 0.OOE+00 O.OOE+00 5.86E+05 1.12E+06 O.OOE+00 0.OOE+00 5.67E+06 1.54E+08 4.78E+08 5.OOE+08 1.67E+07 7.08E-01 1.51 E+09 4.48E+07 1.28E+09 3.87E+04 1.11E+04 7.26E+05 1.OOE+04 9.48E+03 T. BODY 2.34E+02 6.56E+03 2.85E+08 8.78E+03 2.13E+06 7.52E+07 3.04E+08 5.03E+07 2.04E+08 9.91 E+08 6.22E+08 3.54E+08 1.38E+07 2.64E+09 4.82E+04 5.21 E+05 8.63E+05 5.96E+07 5.54E+08 4.53E+06 7.59E+07 2.11E+08 2.78E+08 9.48E+06 2.68E-01 3.19E+08 2.90E+07 1.89E+08 2.58E+06 1.65E+03 1.24E+05 1.65E+03 7.34E+02 THYROID 2.34E+02 6.56E+03 0.OOE+00 4.88E+03 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.60E+08 4.25E+08 5.77E+08 5.52E+09 1.31 E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 2.34E+02 6.56E+03 0.OOE+00 1.33E+03 2.25E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.31 E+08 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 8.38E+05 1.13E+06 3.90E+08 6.OOE+09 1.06E+07 0.OOE+00 5.06E+09 5.26E+09 2.74E+07 1.18E+00 4.69E+08 2.39E+07 4.16E+08 1.26E+04 4.86E+03 4.02E+05 5.42E+03 5.20E+03 LUNG 2.34E+02 6.56E+03 0.OOE+00 8.90E+03 0.OOE+00 1.37E+08 1.77E+08 0.OOE+00 0.OOE+00 O.OE+00 0.OOE+00 0.0OE+O0 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0,00E+00 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.68E+08 3.56E+06 1.50E+08 2.31 E+04 0.OOE+00 0.O0E+00 0.OOE+00 O.OOE+00 GI-LLI 2.34E+02 6.56E+03 2.04E+/-08 4.66E+05 6.73E+06 4.49E+07 6.35E+08 9.58E+07 3.84E+08 1.05E+08 1.76E+08 3.71E+07 1.87E+07 1.40E+08 2.40E+08 6.11 E+08 2.23E+09 4.01 E+09 6.91E+10 6.74E+08 5.49E+08 1.44E+09 2.18E+09 1.48E+06 2.85E-01 8.16E+06 1.57E+06 8.OOE+06 2.24E+07 1.38E+07 1.89E+08 3.60E+07 1.50E+07 CPSES -UNITS 1 AND 2 -ODCM PART II12-28 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS -COW -MEAT NUCLIDE IORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 N 1-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-106 AG-11 OM TE-1 25M TE-127M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 LIVER 0.OOE+00 0 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 T. BODY 0.OOE+00 0 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 THYROID 0.OOE+00 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 KIDNEY 0.OOE+00 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 LUNG 0.OOE+00 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CPSES -UNITS 1 AND 2- ODCM PART I112-29 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: GRASS -GOAT -MILK ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 N 1-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110M TE-1 25M TE-127M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.00E+00 2.25E+04 2.05E+10 0.00E+00 0.OOE+00 3.27E+05 3.87E+05 0.OOE+00 0.OOE+00 8.08E+08 1.65E+08 0.OOE+00 3.05E+09 9.84E+10 1.03E+03 1.13E+02 9.92E+03 1.22E+02 2.45E+03 6.99E+06 1.96E+06 5.50E+06 7.23E+06 3.56E+08 4.65E+06 1.70E+10 7.92E+08 2.22E+10 3.24E+06 5.82E+02 4.30E+04 1.90E+01 1.13E+01 LIVER 1.56E+03 4.50E+03 1.27E+09 0.00E+00 1.01E+06 2.26E+05 9.09E+05 5.66E+05 1.97E+06 5.60E+07 5.24E+08 3.12E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.63E+01 5.52E+03 0.00E+00 0.OOE+00 6.47E+06 7.09E+05 1.97E+06 2.70E+06 5.09E+08 8.1OE+06 4.04E+10 3.13E+09 3.03E+10 4.07E+03 3.94E+02 1.80E+04 7.60E+00 1.31 E+01 T. BODY 1.56E+03 4.50E+03 7.92E+08 3.43E+03 1.93E+05 5.26E+04 3.48E+05 1.27E+06 4,35E+06 2.71 E+07 2.37E+08 1.45E+08 8.76E+07 2.41 E+1 0 2.76E+01 2.46E+01 2.97E+03 5.27E+01 3.1OE+02 3.84E+06 2.62E+05 6.70E+05 1.14E+06 2.92E+08 2.47E+06 3.30E+10 2.25E+09 1.99E+10 2.12E+05 4.47E+01 2.31E+03 9.40E-01 7.82E-01 THYROID 1.56E+03 4.50E+03 0.OOE+00 2.05E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 5.89E+05 1.41 E+06 2.48E+06 1.67E+11 1.19E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 KIDNEY 1.56E+03 4.50E+03 0.OOE+00 7.56E+02 3.01 E+05 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.51 E+08 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 5.70E+01 5.45E+03 4.67E+02 4.73E+03 1.27E+07 7.96E+06 2.23E+07 3.02E+07 8.73E+08 1.41 E+07 1.31E+10 1.74E+09 1.03E+10 1.38E+03 1.83E+02 1.07E+04 4.39E+00 7.65E+00 LUNG 1.56E+03 4.50E+03 0.OOE+00 4.55E+03 O.OOE+00 1.26E+05 2.54E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 4.34E+09 2.38E+08 3.42E+09 2.33E+03 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 1.56E+03 4.50E+03 2.30E+09 8.63E+05 3.1 OE+06 1.30E+05 3.03E+06 1.15E+07 3.70E+07 1.17E+07 3.30E+08 6.14E+07 4.89E+08 2.84E+09 5.68E+05 1.15E+05 3.35E+07 1.43E+04 1.59E+05 2.64E+09 7.81 E+06 1.84E+07 3.64E+07 1.34E+08 7.28E+06 7.07E+08 3.55E+08 5.87E+08 6.67E+06 1.51E+06 1.45E+07 8.30E+04 6.28E+04 CPSES- UNITS 1 AND 2- ODCM PART I112-30 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: GRASS -GOAT -MILK NUCLIDE BONE H-3 0.OOE+00 C-14 4.15E+04 P-32 3.78E+10 CR-51 0.OOE+00 MN-54 0.00E+00 FE-55 5.79E+05 FE-59 6.74E+05 CO-58 0.OOE+00 CO-60 0.OOE+00 NI-63 1.42E+09 ZN-65 2.53E+08 RB-86 0.OOE+00 SR-89 5.62E+09 SR-90 1.39E+11 Y-91 1.90E+03 ZR-95 1.98E+02 NB-95 1.69E+04 RU-103 2.17E+02 RU-1 06 4.50E+03 AG-110M 1.16E+07 TE-125M 3.61 E+06 TE-127M 1.01E+07 TE-129M 1.32E+07 1-131 6.45E+08 1-133 8.49E+06 CS-134 2.95E+10 CS-1 36 1.35E+09 CS-1 37 4.02E+10 BA-140 5.84E+06 CE-141 1.07E+03 CE-144 7.90E+04 PR-i 43 3.48E+01 ND-147 2.18E+01 LIVER 2.04E+03 8.31 E+03 2.34E+09 0.OOE+00 1.68E+06 4.11E+05 1.57E+06 9.53E+05 3.34E+06 1.OOE+08 8.78E+08 5.67E+08 0.OOE+00 0.OOE+00 0.OOE+00 6.25E+01 9.38E+03 0.OOE+00 0.OOE+00 1.09E+07 1.30E+06 3.59E+06 4.90E+06 9.03E+08 1.44E+07 6.93E+10 5.30E+09 5.34E+10 7.16E+03 7.12E+02 3.27E+04 1.39E+01 2.37E+01 ORGAN T. BODY 2.04E+03 8.31 E+03 1.46E+09 5.99E+03 3.34E+05 9.58E+04 6.08E+05 2.20E+06 7.52E+06 4.81 E+07 4.1OE+08 2.67E+08 1.61E+08 3.43E+10 5.09E+01 4.30E+01 5.16E+03 9.29E+01 5.68E+02 6.65E+06 4.82E+05 1.20E+06 2.09E+06 4.85E+08 4.40E+06 3.22E+10 3.56E+09 1.86E+10 3.76E+05 8.18E+01 4.25E+03 1.73E+00 1.42E+00 DOSE FACTORS THYROID 2.04E+03 8.31 E+03 0.OOE+00 3.33E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.01 E+06 2.41 E+06 4.26E+06 2.64E+11 2.01 E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 2.04E+03 8.31 E+03 0.OOE+00 1.31 E+03 5.02E+05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 5.62E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.18E+01 9.09E+03 7.66E+02 8.69E+03 2.09E+07 0.OOE+00 4.11 E+07 5.53E+07 1.56E+09 2.53E+07 2.20E+10 2.89E+09 1.82E+10 2.43E+03 3.35E+02 1.95E+04 8.08E+00 1.39E+01 LUNG 2.04E+03 8.31 E+03 0.OOE+00 8.55E+03 0.OOE+00 2.61 E+05 4.96E+05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 8.41 E+09 4.55E+08 7.07E+09 4.81 E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 2.04E+03 8.31 E+03 3.18E+09 1.01E+06 3.45E+06 1.78E+05 3.72E+06 1.31E+07 4.35E+07 1.60E+07 3.72E+08 8.40E+07 6.69E+08 3.90E+09 7.78E+05 1.44E+05 4.01 E+07 1.82E+04 2.16E+05 3.07E+09 1.06E+07 2.52E+07 4.96E+07 1.79E+08 1.09E+07 8.62E+08 4.27E+08 7.60E+08 9.01E+06 2.04E+06 1.99E+07 1.15E+05 8.54E+04 I.CPSES -UNITS 1 AND 2- ODCM PART 11I2-31 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: GRASS -GOAT -MILK ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-11 OM TE-1 25M TE-1 27M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.00E+00 1.02E+05 9.32E+10 0.OOE+00 0.00E+00 1.45E+06 1.56E+06 0.00E+00 0.00E+00 3.56E+09 4.96E+08 0.00E+00 1.39E+10 2.35E+ 11 4.69E+03 4.60E+02 3.82E+04 5.14E+02 1.11E+04 2.51E+07 8.86E+06 2.50E+07 3.26E+07 1.57E+09 2.06E+07 6.80E+10 3.04E+09 9.68E+10 1.41 E+07 2.63E+03 1.95E+05 8.61E+01 5.34E+01 LIVER 3.20E+03 2.04E+04 4.36E+09 0.OOE+00 2.52E+00 7.71 E+00 2.53E+06 1.46E+06 5.18E+06 1.91 E+08 1.32E+09 1.05E+09 0.00E+00 0.00E+00 0.00E+00 1.01 E+02 1.49E+04 0.OOE+00 0.OOE+00 1.69E+07 2.40E+06 6.72E+06 9.1OE+06 1.57E+09 2.55E+07 1.12E+11 8.36E+09 9.26E+10 1.24E+04 1.31E+03 6.11 E+04 2.59E+01 4.33E+01 T. BODY 3.20E+03 2.04E+04 3.59E+09 1.22E+04 6.71E+05 2.39E+05 1.26E+06 4.46E+06 1.53E+07 1.21E+08 8.22E+08 6.47E+08 3.97E+08 5.95E+10 1.25E+02 9.OOE+01 1.06E+04 1.98E+02 1.38E+03 1/35E+07 1.18E+06 2.96E+06 5.06E+06 8.95E+08 9.66E+06 2.35E+10 5.41 E+09 1.37E+10 8.23E+05 1.95E+02 1.04E+04 4.27E+00 3.35E+00 THYROID 3.20E+03 2.04E+04 0.OOE+00 6.78E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 2.49E+06 5.97E+06 1.05E+07 5.21E+1i 4.74E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 KIDNEY 3.20E+03 2.04E+04 0.OOE+00 1.85E+03 7.06E+05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 8.33E+08 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.45E+02 1.40E+04 1.29E+03 1.50E+04 3.15E+07 0.00E+00 7.12E+07 9.56E+07 2.58E+09 4.25E+07 3.46E+10 4.45E+09 3.02E+10 4.02E+03 5.74E+02 3.38E+04 1.40E+01 2.37E+01 LUNG 3.20E+03 2.04E+04 0.OOE+00 1.24E+04 0.OOE+00 4.36E+05 7.34E+05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.24E+10 6.64E+08 1.09E+10 7.37E+03 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 3.20E+03 2.04E+04 2.58E+09 6.48E+05 2.11E+06 1.43E+05 2.64E+06 8.49E+06 2.87E+07 1.28E+07 2.32E+08 6.77E+07 5.39E+08 3.16E+09 6.24E+05 1.05E+05 2.75E+07 1.33E+04 1.73E+05 2.01 E+09 8.55E+06 2.02E+07 3.97E+07 1.40E+08 1.03E+07 6.01E+08 2.94E+08 5.80E+08 7.15E+06 1.63E+06 1.59E+07 9.29E+04 6.85E+04 I CPSES -UNITS 1 AND 2- ODCM PART II12-32 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: GRASS -GOAT -MILK NUCLIDE BONE H-3 0.OOE+00 C-14 1.82E+05 P-32 1.92E+l1 CR-51 0.00E+00 MN-54 0.OOE+00 FE-55 1.76E+06 FE-59 2.92E+06 CO-58 0.OOE+00 CO-60 0.00E+00 NI-63 4.19E+09 ZN-65 6.67E+08 RB-86 0.OOE+00 SR-89 2.65E+10 SR-90 2.55E+11 Y-91 8.80E+03 ZR-95 8.17E+02 NB-95 7.13E+04 RU-103 1.04E+03 RU-1 06 2.28E+04 AG-11OM 4.63E+07 TE-125M 1.81E+07 TE-127M 5.06E+07 TE-129M 6.69E+07 1-131 3.27E+09 1-133 4.36E+07 CS-134 1.09E+11 CS-1 36 5.94E+09 CS-137 1.54E+11 BA-140 2.90E+07 CE-141 5.21E+03 CE-144 2.79E+05 PR-143 1.78E+02 ND-147 1.06E+02 ORGAN DOSE FACTORS LIVER 4.86E+03 3.88E+04 1.13E+10 0.OOE+00 4.68E+06 1.14E+06 5.1 OE+06 2.91 E+06 1.06E+07 2.59E+08 2.29E+09 2.67E+09 0.OOE+00 0.OOE+00 0.OOE+00 1.99E+02 2.93E+04 0.00E+00 0.00E+00 3.38E+07 6.05E+06 1.68E+07 2.29E+07 3.85E+09 6.35E+07 2.04E+1I 1.75E+10 1.81 E+11 2.90E+04 3.18E+03 1.14E+05 6.66E+01 1.09E+02 T. BODY 4.86E+03 3.88E+04 7.44E+09 1.94E+04 1.06E+06 3.03E+05 2.01 E+06 7.26E+06 2.50E+07 1.46E+08 1.05E+09 1.32E+09 7.59E+08 6.50E+10 2.34E+02 1.41 E+02 1.70E+04 3.48E+02 2.85E+03 2.24E+07 2.45E+06 6.12E+06 1.03E+07 1.69E+09 1.86E+07 2.06E+10 6.52E+09 1.28E+10 1.50E+06 3.74E+02 1.56E+04 8.83E+00 6.66E+00 THYROID 4.86E+03 3.88E+04 0.OOE+00 1.26E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.09E+06 1.46E+07 2.57E+07 1.27E+12 1.15E+10 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 4.86E+03 3.88E+04 0.OOE+00 2.76E+03 1.04E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.11E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.15E+02 2.1OE+04 2.17E+03 2.70E+04 4.84E+07 0.OOE+00 1.24E+08 1.67E+08 4.50E+09 7.46E+07 5.26E+10 6.96E+09 4.85E+10 6.89E+03 9.79E+02 4.62E+04 2.48E+01 4.19E+01 LUNG 4.86E+03 3.88E+04 0.OOE+00 2.46E+04 0.OOE+00 5.55E+05 1.51E+06 0.OOE+00 O.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 2.15E+10 1.42E+09 1.96E+10 1.78E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 4.86E+03 3.88E+04 2.60E+09 5.64E+05 1.72E+06 1.44E+05 2.44E+06 7.25E+06 2.52E+07 1.29E+07 1.93E+09 6.83E+07 5.44E+08 3.19E+09 6.31 E+05 9.91 E+04 2.48E+07 1.27E+04 1.73E+05 1.75E+09 8.62E+06 2.04E+07 3.99E+07 1.37E+08 1.07E+07 5.55E+08 2.65E+08 5.65E+08 7.13E+06 1.64E+06 1.60E+07 9.40E+04 6.89E+04 CPSES -UNITS 1 AND 2- ODCM PART I112-33 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: VEGETATION NUCLIDE BONE H-3 0.OOE+00 C-14 5.56E+04 P-32 1.40E+09 CR-51 0.OOE+00 MN-54 O.00E+00 FE-55 2.1OE+08 FE-59 1.26E+08 CO-58 0.00E+00 CO-60 0.0OE+00 NI-63 1.04E+10 ZN-65 3.17E+08 RB-86 0.00E+00 SR-89 9.98E+09 SR-90 6.05E+1 1 Y-91 5.12E+06 ZR-95 1.17E+06 NB-95 1.42E+05 RU-103 4.77E+06 RU-106 1.93E+08 AG-110M 1.05E+07 TE-125M 9.66E+07 TE-127M 3.49E+08 TE-129M 2.51E+08 1-131 8.08E+07 1-133 2.09E+06 CS-1 34 4.67E+09 CS-1 36 4.28E+07 CS-1 37 6.36E+09 BA-140 1.29E+08 CE-141 1.97E+05 CE-144 3.29E+07 PR-143 6.25E+04 ND-147 3.34E+04 ORGAN DOSE FACTORS LIVER 2.26E+03 1.11E+04 8.69E+07 0.OOE+00 3.13E+08 1.45E+08 2.97E+08 3.07E+07 1.67E+08 7.21 E+08 1.01E+09 2.19E+08 0.OOE+00 0.OOE+00 0.00E+00 3.77E+05 7.92E+04 0.OOE+00 0.OOE+00 9.75E+06 3.50E+07 1.25E+08 9.37E+07 1.16E+08 3.63E+06 1.11E+10 1.69E+08 8.70E+09 1.62E+05 1.33E+05 1.38E+07 2.51 E+04 3.85E+04 T. BODY 2.26E+03 1.11E+04 5.40E+07 4.64E+04 5.97E+07 3.38E+07 1.14E+08 6.89E+07 3.69E+08 3.49E+08 4.56E+08 1.02E+08 2.86E+08 1.48E+11 1.37E+05 2.55E+05 4.26E+04 2.06E+06 2.44E+07 5.79E+06 1.29E+07 4.26E+07 3.97E+07 6.62E+07 1.11E+06 9.08E+09 1.22E+08 5.70E+09 8.47E+06 1.51E+04 1.77E+06 3.1 OE+03 2.31 E+03 THYROID 2.26E+03 1.11E+04 0.OOE+00 2.77E+04 0.OOE+00 0.O0E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 O.OOE+00 0.OOE+00 2.90E+07 8.93E+07 8.63E+07 3.79E+10 5.34E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 KIDNEY 2.26E+03 1.11E+04 0.OOE+00 1.02E+04 9.31 E+07 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 6.75E+08 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 5.91 E+05 7.83E+04 1.82E+07 3.72E+08 1.92E+07 3.93E+08 1.42E+09 1.05E+09 1.98E+08 6.33E+06 3.59E+09 9.41 E+07 2.95E+09 5.52E+04 6.20E+04 8.16E+06 1.45E+04 2.25E+04 LUNG 2.26E+03 1.11E+04 0.0OE+00 6.15E+04 0.OOE+00 8.08E+07 8.29E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.19E+09 1.29E+07 9.81 E+08 9.29E+04 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 2.26E+03 1.11E+04 1.57E+08 1.17E+07 9.58E+08 8.31E+07 9.89E+08 6.23E+08 3.14E+09 1.50E+08 6.36E+08 4.32E+07 1.60E+09 1.75E+10 2.82E+09 1.19E+09 4.81 E+08 5.57E+08 1.25E+10 3.98E+09 3.86E+08 1.17E+09 1.26E+09 3.05E+07 3.26E+06 1.94E+08 1.92E+07 1.68E+08 2.66E+08 5.1OE+08 1.11E+10 2.74E+08 1.85E+08 I CPSES -UNITS 1 AND 2- ODCM PART II12-34 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: VEGETATION ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110M TE-1 25M TE-1 27M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 9.01 E+04 1.60E+09 0.OOE+00 0.OOE+00 3.26E+08 1.80E+08 0.OOE+00 0.OOE+00 1.61E+10 4.24E+08 0.OOE+00 1.52E+10 7.51 E+I 1 7.84E+06 1.72E+06 1.92E+05 6.82E+06 3.09E+08 1-.52E+07 1.48E+08 5.52E+08 3.61 E+08 7.69E+07 1.94E+06 7.10E+09 4.39E+07 1.01E+10 1.39E+08 2.83E+05 5.28E+07 6.99E+04 3.62E+04 LIVER 2.59E+03 1.80E+04 9.91 E+07 0.00E+00 4.54E+08 2.31 E+08 4.19E+08 4.36E+07 2.49E+08 1.13E+09 1.47E+09 2.73E+08 0.OOE+00 0.OOE+00 0.OOE+00 5.43E+05 1.07E+05 0.OOE+00 0.OOE+00 1.43E+07 5.34E+07 1.96E+08 1.34E+08 1.08E+08 3.29E+06 1.67E+10 1.73E+08 1.35E+10 1.71 E+05 1.89E+05 2.18E+07 2.79E+04 3.94E+04 T. BODY 2.59E+03 1.80E+04 6.20E+07 6.16E+04 9.01 E+07 5.39E+07 1.62E+08 1.01E+08 5.60E+08 5.45E+08 6.86E+08 1.28E+08 4.34E+08 1.85E+l1 2.10E+05 3.73E+05 5.87E+04 2.92E+06 3.90E+07 8.72E+06 1.98E+07 6.56E+07 5.72E+07 5.78E+07 1.OOE+06 7.75E+09 1.16E+08 4.69E+09 8.97E+06 2.17E+04 2.83E+06 3.48E+03 2.36E+03 THYROID 2.59E+03 1.80E+04 0.OOE+00 3.42E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.14E+07 1.31E+08 1.17E+08 3.14E+10 4.59E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 2.59E+03 1.80E+04 O.00E+00 1.35E+04 1.36E+08 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 9.42E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.98E+05 1.03E+05 2.41 E+07 5.97E+08 2.74E+07 0.OOE+00 2.24E+09 1.51 E+09 1.85E+08 5.77E+06 5.31 E+09 9.41 E+07 4.59E+09 5.78E+04 8.90E+04 1.30E+07 1.62E+04 2.31 E+04 LUNG 2.59E+03 1.80E+04 0.OOE+00 8.79E+04 0.OOE+00 1.47E+08 1.32E+08 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 2.03E+09 1.48E+07 1.78E+09 1.15E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 2.59E+03 1.80E+04 1.34E+08 1.03E+07 9.32E+08 1.OOE+08 9.91 E+08 6.01 E+08 3.24E+09 1.81E+08 6.23E+08 4.04E+07 1.80E+09 2.11E+10 3.22E+09 1.25E+09 4.56E+08 5.70E+08 1.48E+10 4.03E+09 4.37E+08 1.37E+09 1.36E+09 2.13E+07 2.49E+06 2.08E+08 1.39E+07 1.92E+08 2.15E+08 5.41 E+08 1.33E+10 2.30E+08 1.42E+08 CPSES -UNITS 1 AND 2- ODCM PART II12-35 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: VEGETATION ORGAN DOSE FACTORS NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-103 RU-1 06 AG-110M TE-125M TE-127M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-1 40 CE-141 CE-144 PR-143 ND-147 BONE O.OOE+00 2.17E+05 3.35E+09 0.OOE+00 0.OOE+00 8.01 E+08 3.98E+08 0.OOE+00 0.00E+00 3.95E+10 8.12E+08 0.OOE+00 3.60E+10 1.24E+12 1.87E+07 3.86E+06 4.11 E+05 1.53E+07 7.45E+08 3.21 E+07 3.51 E+08 1.32E+09 8.40E+08 1.43E+08 3.53E+06 1.60E+10 8.28E+07 2.39E+10 2.79E+08 6.57E+05 1.27E+08 1.45E+05 7.15E+04 LIVER 4.02E+03 4.34E+04 1.57E+08 0.OOE+00 6.65E+08 4.25E+08 6.44E+08 6.44E+07 3.78E+08 2.11E+09 2.16E+09 4.51E+08 0.OOE+00 0.OOE+00 0.OOE+00 8.48E+05 1.60E+05 0.OOE+00 0.00E+00 2.17E+07 9.50E+07 3.56E+08 2.35E+08 1.44E+08 4.37E+06 2.63E+10 2.28E+08 2.29E+10 2.44E+05 3.28E+05 3.99E+07 4.36E+04 5.79E+04 T. BODY 4.02E+03 4.34E+04 1.29E+08 1.17E+05 1.77E+08 1.32E+08 3.21 E+08 1.97E+08 1.12E+09 1.34E+09 1.35E+09 2.77E+08 1.03E+09 3.15E+1 1 4.99E+05 7.55E+05 1.14E+05 5.90E+06 9.30E+07 1.73E+07 4.67E+07 1.57E+08 1.30E+08 8.18E+07 1.65E+06 5.55E+09 1.47E+08 3.38E+09 1.63E+07 4.86E+04 6.79E+06 7.21 E+03 4.49E+03 THYROID 4.02E+03 4.34E+04 0.OOE+00 6.49E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.O0E+00 0.OOE+00 9.84E+07 3.16E+08 2.71 E+08 4.76E+10 8.12E+08 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 KIDNEY 4.02E+03 4.34E+04 0.OOE+00 1.77E+04 1.86E+08 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.36E+09 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.21 E+06 1.50E+05 3.86E+07 1.01 E+09 4.04E+07 0.OOE+00 3.77E+09 2.47E+09 2.36E+08 7.28E+06 8.15E+09 1.21 E+08 7.46E+09 7.96E+04 1.44E+05 2.21 E+07 2.36E+04 3.18E+04 LUNG 4.02E+03 4.34E+04 0.OOE+00 1.18E+05 0.OOE+00 2.40E+08 1.87E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 2.93E+09 1.81 E+07 2.68E+09 1.46E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 GI-LLI 4.02E+03 4.34E+04 9.25E+07 6.20E+06 5.58E+08 7.87E+07 6.71 E+08 3.76E+08 2.1OE+09 1.42E+08 3.80E+08 2.90E+07 1.39E+09 1.67E+10 2.49E+09 8.85E+08 2.96E+08 3.97E+08 1.16E+10 2.58E+09 3.38E+08 1.07E+09 1.02E+09 1.28E+07 1.76E+06 1.42E+08 8.OOE+06 1.43E+08 1.41 E+08 4.09E+08 1.04E+10 1.57E+08 9.18E+07 I CPSES -UNITS 1 AND 2- ODCM PART 11 2-36 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: VEGETATION ORGAN DOSE FACTORS NUCLIDE NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-i1 OM TE-125M TE-127M TE-1 29M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 LIVER 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 T. BODY 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.00E+00 THYROID 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00-0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 LUNG 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 CPSES -UNITS 1 AND 2 -ODCM PART I112-37 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: ADULT PATHWAY: INHALATION ORGAN DOSE FACTORS NUCLIDE NUCLIDE H-3 C-14 P-32 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-I IOM TE-1 25M TE-1 27M TE-1 29M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 PR-143 ND-147 BONE 0.00E+00 1.82E+04 1.32E+06 0.OOE+00 0.OOE+00 2.46E+04 1.18E+04 0.OOE+00 0.00E+00 4.32E+05 3.24E+04 0.OOE+00 3.04E+05 9.92E+07 4.62E+05 1.07E+05 1.41E+04 1.53E+03 6.91E+04 1.08E+04 3.42E+03 1.26E+04 9.76E+03 2.52E+04 8.64E+03 3.73E+05 3.90E+04 4.78E+05 3.90E+04 1.99E+04 3.43E+06 9.36E+03 5.27E+03 LIVER 1.26E+03 3.41 E+03 7.71 E+04 0.00E+00 3.96E+04 1.70E+04 2.78E+04 1.58E+03 1.15E+04 3.14E+04 1.03E+05 1.35E+05 0.OOE+00 0.OOE+00 0.00E+00 3.44E+04 7.82E+03 0.00E+00 0.OOE+00 1.OOE+04 1.58E+03 5.77E+03 4.67E+03 3.58E+04 1.48E+04 8.48E+05 1.46E+05 6.21 E+05 4.90E+01 1.35E+04 1.43E+06 3.75E+03 6.1OE+03 T. BODY 1.26E+03 3.41 E+03 5.01 E+04 1.OOE+02 6.30E+03 3.94E+03 1.06E+04 2.07E+03 1.48E+04 1.45E+04 4.66E+04 5.90E+04 8.72E+03 6.1OE+06 1.24E+04 2.33E+04 4.21 E+03 6.58E+02 8.72E+03 5.94E+03 4.67E+02 1.57E+03 1.58E+03 2.05E+04 4.52E+03 7.28E+05 1.10E+05 4.28E+05 2.57E+03 1.53E+03 1.84E+05 4.64E+02 3.65E+02 THYROID 1.26E+03 3.41 E+03 0.OOE+00 5.95E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.05E+03 3.29E+03 3.44E+03 1.19E+07 2.15E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KIDNEY 1.26E+03 3.41 E+03 0.OOE+00 2.28E+01 9.84E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.90E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 5.42E+04 7.74E+03 5.83E+03 1.34E+05 1.97E+04 1.24E+04 4.58E+04 3.66E+04 6.13E+04 2.58E+04 2.87E+05 8.56E+04 2.22E+05 1.67E+01 6.26E+03 8.48E+05 2.16E+03 3.56E+03 LUNG 1.26E+03 3.41 E+03 0.OOE+00 1.44E+04 1.40E+06 7.21 E+04 1.02E+06 9.28E+05 5.97E+06 1.78E+05 8.64E+05 0.OOE+00 1.40E+06 9.60E+06 1.70E+06 1.77E+06 5.05E+05 5.05E+05 9.36E+06 4.63E+06 3.14E+05 9.60E+05 1.16E+06 0.OOE+00 0.OOE+00 9.76E+04 1.20E+04 7.52E+04 1.27E+06 3.62E+05 7.78E+06 2.81E+05 2.21 E+05 GI-LLI 1.26E+03 3.41 E+03 8.64E+04 3.32E+03 7.74E+04 6.03E+03 1.88E+05 1.06E+05 2.85E+05 1.34E+04 5.34E+04 1.66E+04 3.50E+05 7.22E+05 3.85E+05 1.50E+05 1.04E+05 1.10E+05 9.12E+05 3.02E+05 7.06E+04 1.50E+05 3.83E+05 6.28E+03 8.88E+03 1.04E+04 1.17E+04 8.40E+03 2.18E+05 1.20E+05 8.16E+05 2.OOE+05 1.73E+05 CPSES -UNITS 1 AND 2- ODCM PART II12-38 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: TEEN PATHWAY: INHALATION NUCLIDE BONE H-3 0.OOE+00 C-14 2.60E+04 P-32 1.89E+06 CR-51 0.OOE+00 MN-54 0.OOE+00 FE-55 3.34E+04 FE-59 1.59E+04 CO-58 0.00E+00 CO-60 0.OOE+00 N 1-63 5.80E+05 ZN-65 3.86E+04 RB-86 0.OOE+00 SR-89 4.34E+05 SR-90 1.08E+08 Y-91 6.61 E+05 ZR-95 1.46E+05 NB-95 1.86E+04 RU-103 2.1OE+03 RU-106 9.84E+04 AG-11OM 1.38E+04 TE-125M 4.88E+03 TE-127M 1.80E+04 TE-1 29M 1.39E+04 1-131 3.54E+04 1-133 1.22E+04 CS-1 34 5.02E+05 CS-136 5.15E+04 CS-1 37 6.70E+05 BA-140 5.47E+04 CE-141 2.84E+04 CE-144 4.89E+06 PR-143 1.34E+04 ND-147 7.86E+03 ORGAN DOSE FACTORS LIVER 1.27E+03 4.87E+03 1.10E+05 0.OOE+00 5.11E+04 2.38E+04 3.70E+04 2.07E+03 1.51E+04 4.34E+04 1.34E+05 1.90E+05 0.OOE+00 0.00E+00 0.OOE+00 4.58E+04 1.03E+04 0.OOE+00 0.OOE+00 1.31 E+04 2.24E+03 8.16E+03 6.58E+03 4.91 E+04 2.05E+04 1.13E+06 1.94E+05 8.48E+05 6.70E+01 1.90E+04 2.02E+06 5.31 E+03 8.56E+03 T. BODY 1.27E+03 4.87E+03 7.16E+04 1.32E+02 8.40E+03 5.54E+03 1.43E+04 2.78E+03 1.98E+04 1.98E+04 6.24E+04 8.40E+04 1.25E+04 6.68E-+06 1.77E+04 3.15E+04 5.66E+03 8.96E+02 1.24E+04 7.99E+03 6.67E+02 2.18E+03 2.25E+03 2.64E+04 6.22E+03 5.49E+05 1.37E+05 3.11 E+05 3.52E+03 2.17E+03 2.62E+05 6.62E+02 5.13E+02 THYROID 1.27E+03 4.87E+03 0.OOE+00 7.50E+01 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.40E+03 4.38E+03 4.58E+03 1.46E+07 2.92E+06 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.0OE+00 0.OOE+00 O.OOE+00 O.OOE+00 KIDNEY 1.27E+03 4.87E+03 0.OOE+00 3.07E+01 1.27E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.64E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.74E+04 1.OOE+04 7.43E+03 1.90E+05 2.50E+04 0.OOE+00 6.54E+04 5.19E+04 8.40E+04 3.59E+04 3.75E+05 1.10E+05 3.04E+05 2.28E+01 8.88E+03 1.21E+06 3.09E+03 5.02E+03 LUNG 1.27E+03 4.87E+03 0.OOE+00 2.1OE+04 1.98E+06 1.24E+05 1.53E+06 1.34E+06 8.72E+06 3.07E+05 1.24E+06 O.OOE+00 2.42E+06 1.65E+07 2.94E+06 2.69E+06 7.51 E+05 7.83E+05 1.61E+07 6.75E+06 5.36E+05 1.66E+06 1.98E+06 O.OOE+00 O.OOE+00 1.46E+05 1.78E+04 1.21E+05 2.03E+06 6.14E+05 1.34E+07 4.83E+05 3.72E+05 GI-LLI 1.27E+03 4.87E+03 9.28E+04 3.OOE+03 6.68E+04 6.39E+03 1.78E+05 9.52E+04 2.59E+05 1.42E+04 4.66E+04 1.77E+04 3.71 E+05 7.65E+05 4.09E+05 1.49E+05 9.68E+04 1.09E+05 9.60E+05 2.73E+05 7.50E+04 1.59E+05 4.05E+05 6.49E+03 1.03E+04 9.76E+03 1.09E+04 8.48E+03 2.29E+05 1.26E+05 8.64E+05 2.14E+05 1.82E+05 I CPSES -UNITS 1 AND 2- ODCM PART 11 2-39 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: CHILD PATHWAY: INHALATION NUCLIDE BONE H-3 0.00E+00 C-14 3.59E+04 P-32 2.60E+06 CR-51 0.00E+00 MN-54 0.00E+00 FE-55 4.74E+04 FE-59 2.07E+04 CO-58 0.OOE+00 CO-60 0.00E+00 NI-63 8.21E+05 ZN-65 4.26E+04 RB-86 0.00E+00 SR-89 5.99E+05 SR-90 1.01E+08 Y-91 9.14E+05 ZR-95 1.90E+05 NB-95 2.35E+04 RU-1 03 2.79E+03 RU-106 1.36E+05 AG-1i1M 1.69E+04 TE-125M 6.73E+03 TE-127M 2.49E+04 TE-129M 1.92E+04 1-131 4.81 E+04 1-133 1.66E+04 CS-134 6.51E+05 CS-136 6.51E+04 CS-137 9.07E+05 BA-140 7.40E+04 CE-141 3.92E+04 CE-144 6.77E+06 PR-143 1.85E+04 ND-147 1.08E+04 ORGAN DOSE FACTORS LIVER T. BODY 1.12E+03 1.12E+03 6.73E+03 6.73E+03 1.14E+05 9.88E+04 0.OOE+00 1.54E+02 4.29E+04 9.51E+03 2.52E+04 7.77E+03 3.34E+04 1.67E+04 1.77E+03 3.16E+03 1.31E+04 2.26E+04 4.63E+04 2.80E+04 1.13E+05 7.03E+04 1.98E+05 1.14E+05 0.OOE+00 1.72E+04 0.00E+00 6.44E+06 0.00E+00 2.44E+04 4.18E+04 3.70E+04 9.18E+03 6.55E+03 0.00E+00 1.07E+03 0.OOE+00 1.69E+04 1.14E+04 9.14E+03 2.33E+03 9.14E+02 8.55E+03 3.02E+03 6.85E+03 3.04E+03 4.81E+04 2.73E+04 2.03E+04 7.70E+03 1.01E+06 2.25E+05 1.71E+05 1.16E+05 8.25E+05 1.28E+05 6.48E+01 4.33E+03 1.95E+04 2.90E+03 2.12E+06 3.61E+05 5.55E+03 9.14E+02 8.73E+03 6.81E+02 ORGAN DOSE FACTORS THYROID 1.12E+03 6.73E+03 0.00E+00 8.55E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.92E+03 6.07E+03 6.33E+03 1.62E+07 3.85E+06 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 KIDNEY 1.12E+03 6.73E+03 0.00E+00 2.43E+01 1.00E+04 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 7.14E+04 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 5.96E+04 8.62E+03 7.03E+03 1.84E+05 2.12E+04 0.00E+00 6.36E+04 5.03E+04 7.88E+04 3.38E+04 3.30E+05 9.55E+04 2.82E+05 2.11E+01 8.55E+03 1.17E+06 3.00E+03 4.81 E+03 LUNG 1.12E+03 6.73E+03 0.00E+00 1.70E+04 1.58E+06 1.11E+05 1.27E+06 1.11E+06 7.07E+06 2.75E+05 9.95E+05 0.OOE+00 2.16E+06 1.48E+07 2.63E+06 2.23E+06 6.14E+05 6.62E+05 1.43E+07 5.48E+06 4.77E+05 1.48E+06 1.76E+06 0.OOE+00 0.00E+00 1.21 E+05 1.45E+04 1.04E+05 1.74E+06 5.44E+05 1.20E+07 4.33E+05 3.28E+05 GI-LLI 1.12E+03 6.73E+03 4.22E+04 1.08E+03 2.29E+04 2.87E+03 7.07E+04 3.44E+04 9.62E+04 6.33E+03 1.63E+04 7.99E+03 1.67E+05 3.43E+05 1.84E+05 6.11E+04 3.70E+04 4.48E+04 4.29E+05 1.OOE+05 3.38E+04 7.14E+04 1.82E+05 2.84E+03 5.48E+03 3.85E+03 4.18E+03 3.62E+03 1.02E+05 5.66E+04 3.89E+05 9.73E+04 8.21 E+04 CPSES -UNITS 1 AND 2- ODCM PART II12-40 Rev. 32 TABLE 2.4 PATHWAY DOSE FACTORS AGE GROUP: INFANT PATHWAY: INHALATION NUCLIDE BONE H-3 0.00E+00 C-14 2.65E+04 P-32 2.03E+06 CR-51 0.00E+00 MN-54 0.00E+00 FE-55 1.97E+04 FE-59 1.36E+04 CO-58 0.00E+00 CO-60 0.OOE+00 NI-63 3.39E+05 ZN-65 1.93E+04 RB-86 0.00E+00 SR-89 3.98E+05 SR-90 4.09E+07 Y-91 5.88E+05 ZR-95 1.15E+05 NB-95 1.57E+04 RU-1 03 2.02E+03 RU-106 8.68E+04 AG-110M 9.98E+03 TE-125M 4.76E+03 TE-1 27M 1.67E+04 TE-129M 1.41EE+04 1-131 3.79E+04 1-133 1.32E+04 CS-1 34 3.96E+05 CS-1 36 4.83E+04 CS-1 37 5.49E+05 BA-140 5.60E+04 CE-141 2.77E+04 CE-144 3.19E+06 PR-143 1.40E+04 ND-147 7.94E+03 ORGAN DOSE FACTORS LIVER 6.47E+02 5.31 E+03 1.12E+05 0.00E+00 2.53E+04 1.17E+04 2.35E+04 1.22E+03 8.02E+03 2.04E+04 6.26E+04 1.90E+05 0.00E+00 0.OOE+00 0.OOE+00 2.79E+04 6.43E+03 0.OOE+00 0.OOE+00 7.22E+03 1.99E+03 6.90E+03 6.09E+03 4.44E+04 1.92E+04 7.03E+05 1.35E+05 6.12E+05 5.60E+01 1.67E+04 1.21 E+06 5.24E+03 8.13E+03 T. BODY 6.47E+02 5.31 E+03 7.74E+04 8.95E+01 4.98E+03 3.33E+03 9.48E+03 1.82E+03 1.18E+04 1.16E+04 3.11 E+04 8.82E+04 1.14E+04 2.59E+06 1.57E+04 2.03E+04 3.78E+03 6.79E+02 1.09E+04 5.OOE+03 6.58E+02 2.07E+03 2.23E+03 1.96E+04 5.60E+03 7.45E+04 5.29E+04 4.55E+04 2.90E+03 1.99E+03 1.76E+05 6.99E+02 5.OOE+02 THYROID 6.47E+02 5.31 E+03 0.OOE+00 5.75E+01 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 1.62E+03 4.87E+03 5.47E+03 1.48E+07 3.56E+06 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 KIDNEY 6.47E+02 5.31 E+03 0.OOE+00 1.32E+01 4.98E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 3.25E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 3.11 E+04 4.72E+03 4.24E+03 1.07E+05 1.09E+04 0.00E+00 3.75E+04 3.18E+04 5.18E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 1.34E+01 5.25E+03 5.38E+05 1.97E+03 3.15E+03 LUNG 6.47E+02 5.31E+03 0.OOE+00 1.28E+04 1.OOE+06 8.69E+04 1.02E+06 7.77E+05 4.51 E+06 2.09E+05 6.47E+05 0.OOE+00 2.03E+06 1.12E+07 2.45E+06 1.75E+06 4.79E+05 5.52E+05 1.16E+07 3.67E+06 4.47E+05 1.31 E+06 1.68E+06 0.OOE+00 0.OOE+00 7.97E+04 1.18E+04 7.13E+04 1.60E+06 5.17E+05 9.84E+06 4.33E+05 3.22E+05 GI-LLI 6.47E+02 5.31E+03 1.61E+04 3.57E+02 7.06E+03 1.09E+03 2.48E+04 1.11E+04 3.19E+04 2.42E+03 5.14E+04 3.04E+03 6.40E+04 1.31E+05 7.03E+04 2.17E+04 1.27E+04 1.61 E+04 1.64E+05 3.30E+04 1.29E+04 2.73E+04 6.90E+04 1.06E+03 2.16E+03 1.33E+03 1.43E+03 1.33E+03 3.84E+04 2.16E+04 1.48E+05 3.72E+04 3.12E+04 I CPSES -UNITS 1 AND 2- ODCM PART II12-41 Rev. 32 TABLE 2.5 (Sheet 1)CONTROLLING RECEPTOR PATHWAYS AND LOCATIONS (NOTE 1), AND ATMOSPHERIC DISPERSION PARAMETERS (FOR DOSE CALCULATIONS REQUIRED BY RADIOLOGICAL EFFLUENT CONTROL 3/4.11.2.3)
TABLE RELOCATED; CURRENT INFORMATION LISTED AND MAINTAINED CURRENT IN RESULTS OF ANNUAL LAND USE CENSUS CPSES -UNITS 1 AND 2- ODCM PART 112-42 Rev. 23 GASEOUS WASTE PROCESSING SYSTEM FIGURE 2.1 (Simplified diagram)DISCHARGE TO ATMOSPHERE DISCHARGE TO ATMOSPHERE 14 t1I FLOW DIAGRAMr.:
SFUEL UILDIN MM1-0269 & MI-0270 AUxIUARYBUILDING 1RE-2959 CONDENSE OFFGAS (5) In addition to HI-Red. cdrcult failure. loas of counts, loss of flow or channel out of service will Initiate the contral functions.(a) Filters are present between the AIR INTAKE PLENUM AND EXHAUST AIR PLENUM.. Them are sixteen banks of filters divided Into TRAIN A and TRAIN B. Each bank consists of a carbon filter, 2HEPA filter, a carbon filter. and a HEPA filter In series.(1) VIde Range Gas Monitor. Hi-Rad Indication closes valve HCV-014 (Waste Gas Release).(2) HI-Red Indication by monitor closes valve-(3) HI-Red Indication Initiates containment Isolation.
(4) Eight gaseous decay tank& can be Individually purged (There am two additional tanka for shutdown).
CPSES -UNITS 1 AND 2- ODCM PART 112-43 Rev. 23 alA Z ZE zL 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.1 1.0 10.0 PLUME TRAVEL DISTAN]E IKILOMETERS)
Figure 2.2Plume Depletion Effect for Ground-Level Releases 100.0 200.0 CPSES -UNITS 1 AND 2- ODCM PART II12-44 Rev. 23 i mn I I 1111/-, ...... .-I I I III I;a cc us-w a,'I 100-00/OF 00010 0 G" 0.1 1.0 10 100 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 MODIFIED FOR CERTAIN TYPES OF TERRAIN AND/OR CLIMATIC CONDITIONS (E.G., VALLEY, DESERT, OVER WATER)Figure 2.3 CPSES -UNITS 1 AND 2- ODCM PART 1I12-45 Rev. 23 I I&4 S I I C IA'I,..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 CPSES -UNITS 1 AND 2 -ODCM PART II12-46 Rev. 23 z 01.0 U -- I III- --0.11L -0.1 1.0 DISTANCE (KILOMETERS)
Open Terrain Correction Factor Figure 2.5 CPSES -UNITS 1 AND 2- ODCMP 2 PART II12-47 Rev. 23 SECTION 3.0RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 SAMPLING LOCATIONS Sampling locations as required in Radiological Effluent Control 3/4.12.1, Table 3.12-1 are listed and maintained current in the results of the annual Land Use Census.NOTE: For the purpose of implementing Radiological Effluent Control 3/4.12.1, sampling locations will be modified as required to reflect the findings of the Land Use Census. Dose calculations used in making this determination will be performed as specified in Section 2.5.The sampling locations maintained in the results of the annual Land Use Census are the minimum locations required for compliance with Radiological Effluent Control 3/4.12.1.
If desired, additional locations may be monitored as special studies to evaluate potential pathways of exposure without adding such locations to the monitoring program.3.2 INTERLABORATORY COMPARISON PROGRAM For the purpose of implementing Radiological Effluent Control 3/4.12.3, TXU Power has contracted with an outside laboratory to provide radiological environmental analytical services with required participation in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program is conducted by a third-party laboratory which supplies environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing laboratory but not to the participant laboratories.
The purpose of the program is to provide an independent check on the participant laboratory's analytical procedures and to alert the participants to any possible problems.
Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing laboratory.
Several months later, the issuing laboratory reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. TXU Power's contracted outside laboratory participates in an environmental sample crosscheck program for representative sample media. The results of the program are included in the Annual Radiological Environmental Operating Report, as required by CPSES ODCM Section 6.9.1.3.CPSES- UNITS 1 AND 2- ODCM PART 1I13-1 Rev. 23 TABLE 3.1 ENVIRONMENTAL SAMPLING LOCATIONS TABLE RELOCATED; ENVIRONMENTAL SAMPLING LOCATIONS ARE LISTED AND MAINTAINED CURRENT IN THE RESULTS OF THE ANNUAL LAND USE CENSUS CPSES- UNITS 1 AND 2- ODCM PART II13-2 Rev. 23 FIGURE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS FIGURE RELOCATED; RADIOLOGICAL ENVIRONMENTAL MONITIORING LOCATIONS ARE LISTED AND MAINTAINED CURRENT IN THE RESULTS OF THE ANNUAL LAND USE CENSUS CPSES -UNITS 1 AND 2- ODCM PART II13-3 Rev. 23 APPENDIX A PATHWAY DOSE RATE PARAMETER Pi (inhalation)
= K' (BR) DFAi [Eq. A-i]Where: Pi = Pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem/yr per microcurie/m 3.The dose factors are based on the critical individual organ for the child age group.K' = Conversion factor, 106 pCi/microcurie BR = 3700 m 3/yr, breathing rate for child (Ref. 2, Table E-5)DFAi = Maximum organ inhalation dose factor for the child age group for the ith radionuclide (mRem/pCi).
Values are taken from Table E-9, Reg. Guide 1.109 (Ref. 2).Resolution of the units yields: Pi (inhalation)
= 3.7 x 10 9 DFAi (mRem/yr per uCi/m 3) [Eq. A-2]The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.CPSES -UNITS 1 AND 2- ODCM PART 11 A-1 Rev. 23 APPENDIX B INHALATION PATHWAY DOSE FACTOR (R'i,a,o)Rli,a,o = k' (BR) (DFAiao) (mrem/yr per microcurie/m
- 3) [Eq. B-i]Where: k' = Conversion factor, 106 pCi/microcurie BR = Breathing rate, 1400, 3700, 8000, and 8000 m 3/yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2, Table E-5)DFAi,a,o = Inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi.
The total body is considered as an organ in the selection of DFAi,a,o.
Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Ref. 2).CPSES -UNITS 1 AND 2- ODCM PARTII1B-1 Rev. 23 APPENDIX C GROUND PLANE PATHWAY DOSE FACTOR (RGi)RG = k' k" (SF)DFGi [(1 -e-'it)/xi]
[Eq. C-1]Where: k' = Conversion factor, 106 pCi/microcurie k"l = Conversion factor, 8760 hr/yr?,j = Decay constant for the ith radionuclide, sec-1 t = Exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs)DFG = Ground plane dose conversion factor for the ith radionuclide (mrem/hr per pCi/m 2). Values are taken from Table E-6, Reg. Guide 1.109 (Ref. 2). These values apply to all age groups. Dose factors are provided for the total body and skin only. Doses to all other organs are assumed equal to the total body dose.SF 0.7, shielding factor, from Table E-15, Reg. Guide 1.109 (Ref. 2).CPSES -UNITS 1 AND 2- ODCM PART 11 C-1 Rev. 23 APPENDIX D GRASS-COW-MILK PATHWAY DOSE FACTOR (RCiao)R ia,o = k'[(QF X UAP)/(X1 + Xw)] x (Fro) x (r) x (DFLiao)x
[Eq. D-1][(p x fs)/Yp) + ((1 -fp x fs)e-x ith)/Ys]e-Xitf Where: k' = Conversion factor, 106 picocurie/microcurie (pCi/uci)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109)YP = Agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG-0133)
YS = Agricultural productivity by unit area of stored feed, 2.0 kg/m 2 (NUREG-01 33)Fm = Stable element transfer coefficient (Table E-1, R.G. 1.109)r = Fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, R.G. 1.109)DFLi,a,o = Ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)=i Decay constant for the ith radionuclide, sec-1 kLw = Decay constant for weathering, 5.73 x 10-7 sec" 1 (NUREG-01 33)tf = 1.73 x 105 sec, Transport time from pasture to cow to milk to receptor (Table E-15, R.G. 1.109)th = 7.78 x 106 sec, Transport time from pasture to harvest to cow to milk to receptor (Table E-15, R.G. 1.109)fp = 1.0, Fraction of the year that the cow is on pasture fs = 1.0, 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, Rci is based on (X/Q): C Rt,a,o =k k"' Fm QF UAp DFLt,a,o (.75(.5/H))
[Eq. D-2]CPSES -UNITS 1 AND 2- ODCM PART 11 D-1 Rev. 32 APPENDIX D (CONTINUED)
Where: k"' = 10 3 grams/kg H = 8 grams/m 3 , Absolute humidity of the atmosphere
.75 = Fraction of total feed grass mass that is water.5 = Ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG-0133)
DFLt,a,o = Ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, R.G. 1.109).All other parameters and values are as given above.NOTE: Goat-milk pathway factor, Rci,a,o will be computed using the cow-milk pathway factor equation.
Fm factor for goat-milk will be from Table E-2, R.G. 1.109. QF for goats is 6 kg/day from Table E-3, R.G. 1.109.CPSES -UNITS 1 AND 2- ODCM PART I I D-2 Rev. 32 APPENDIX D (CONTINUED)
The concentration of C-14 in milk is based on the airborne concentration rather than deposition.
Therefore, Rc. is based on (X/Q)RCc,a,o = k' k"' Fm QF UAp DFLc,a,o [0.11/0.16] (p) (f) [Eq. D-3]Where: k' = Units conversion factor pCi!/Ci (106)k,, = Units conversion factor gm/kg (103)Fm = Stable element transfer coefficient (Table E-1, R.G. 1.1 09)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (R.G. 1.109)DFLc,a,o = Ingestion dose conversion factor for C-14, organ o, and age group a, (Tables E-11 to E-14, R.G. 1.109) (mrem/pCi) 0.11 = Fraction of total plant mass consisting of natural carbon (R.G. 1.109)0.16 = Concentration of natural carbon in the atmosphere (gm/m 3) (R.G. 1.109)p = Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is established to be 0.31, based on 70% of C-14 releases being from wGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series. 421,"Management of Waste Containing Tritium and Carbon-14", 2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.NOTE: Goat-milk pathway factor, RCc,a,o will be computed using the cow-milk pathway factor equation.
Fm factor for goat-milk will be from Table E-2, R.G. 1.109 QF for goats is 6 kg/day from Table E-3, R.G. 1.109.CPSES- UNITS 1 AND 2- ODCM PART 11 D-3 Rev. 32 APPENDIX E COW-MEAT PATHWAY DOSE FACTOR (RMi,a,o)M =k R i,a,o [(QF x UAp)/(Xl + x (Ff) x (r) x (DFLi 8 Q) x[((fp x fs)/Yp) + ((1 -fpfs)e- ith)/Ys] x e-Xitf [Eq. E-l]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, child, teenager, and adult age groups, respectively (R.G. 1.109)Ff = Stable element transfer coefficients, days/kg (Table E-1, R.G. 1.109)r = Fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, R.G. 1.109)DFLia,o = Ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)x'i = Decay constant for radionuclide i, sec" 1 XW= Decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-01 33)tf = 1.73 x 106 sec, Transport time from pasture to receptor (NUREG-0133) th = 7.78 x 106 sec, Transport time from crop to receptor (NUREG-0133)
YP = Agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG-0133)
YS = Agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) fp = 1.0, Fraction of the year that the cow is on pasture fs = 1.0, Fraction of the cow feed that is pasture grass while the cow is on pasture.CPSES -UNITS 1 AND 2- ODCM PART 11 E-1 Rev. 32 APPENDIX E (CONTINUED)
The concentration of tritium in meat is based on its airborne concentration rather than the deposition.
Therefore RMi is based on (X/Q): Rta,o = k' k"' Ff QF UAP (DFLtao) x 0.75 x (0.5/H),[Eq.
E-2]Where: All terms are as defined above and in Appendix D.CPSES -UNITS 1 AND 2- ODCM PART 11 E-2 Rev. 32 APPENDIX E (CONTINUED)
The concentration of C-14 in meat is based on the airborne concentration rather than deposition.
Therefore, RMc is based on (X/Q)RMc,a,o k' k"' FfQF UAp DFLc,a,o[0.11/0.16] (p) (f) [Eq. E-3]Where: k' = Units conversion factor pCi/pci (106)k, = Units conversion factor gm/kg (103)Ff = Stable element transfer coefficient (Table E-1, R.G. 1.109)QF = Cow consumption rate, 50 kg/day (R.G. 1.109)UAP = Consumption rate of cow meat for age group a (kg/yr) (R.G. 1.109)DFLca,o = Ingestion dose conversion factor for C-14, organ o, and age group a, (Tables E-11 to E-14, R.G. 1.109) (mrem/pCi) 0.11 = Fraction of total plant mass consisting of natural carbon (R.G. 1.109)0.16 = Concentration of natural carbon in the atmosphere (gm/m 3) (R.G. 1.109)p = Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is established to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series. 421,"Management of Waste Containing Tritium and Carbon-14", 2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.CPSES -UNITS 1 AND 2- ODCM PART 11 E-3 Rev. 32 APPENDIX F VEGETATION PATHWAY DOSE FACTOR (RVia,o)V L -Xt S X Ri,a,o = k' x [r/ (Yv(oi + kw))] x (DFkIa,0) x [(u A)fL e- i L + U A fg e-ith] [Eq. F-1]Where: k' = 106 picocurie/microcurie (pCi/uCi)UL A = Consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenager, or adult age groups, respectively (R.G. 1.109)usA = Consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenager, or adult age groups respectively (R.G. 1.109)fL Fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 (NUREG-0133) fg = Fraction of the stored vegetation grown locally .76 (NUREG-0133) tL = Average time between harvest of leafy vegetation and its consumption, 8.6 x 10 4 seconds (Table E-15, R.G. 1.109 (24 hrs))th = 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))Yv = Vegetation areal density, 2.0 kg/m 2 (Table. E-15, R.G. 1.109)All other parameters are as previously defined.The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.
Therefore, RVi is based on (X/Q)Rt,a,o = k' k.' [UA fL + UA fg] (DFLt,a,o)
(.75 (.5/H)) [Eq. F-2]Where: All terms are as defined above and in Appendix D.CPSES -UNITS 1 AND 2- ODCM PART 11 F-1 Rev. 32 APPENDIX F (CONTINUED)
The concentration of C-14 in vegetation is based on the airborne concentration rather than deposition.
Therefore, RVi is based on (X/Q)RVc,a,o = k' k"' [ULA fL + USAfg] DFLc,a,o [0.11/0.16] (p) (f) [Eq. F-3]Where: k' = Units conversion factor pCi/gci (106)k,. = Units conversion factor gm/kg (103)jL A = Comsumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenage, or adult age groups, respectively (R.G. 1.109) i us A = Consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teenage, or adult age groups, respectively (R.G. 1.109) f fL Fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 (NUREG-0133) fg = Fraction of the stored vegetation grown locally .76 (NUREG-0133)
DFLc,a,o = Ingestion dose conversion factor for C-14, organ o, and age group a, (Tables E-11 to E-14, R.G. 1.109) (mrem/pCi) 0.11 = Fraction of total plant mass consisting of natural carbon (R.G. 1.109)0.16 = Concentration of natural carbon in the atmosphere (gm/m 3) (R.G. 1.109)p = Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is established to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series. 421,"Management of Waste Containing Tritium and Carbon-14", 2004).f =The fraction of C-14 assumed to be in inorganic form (e.g., C02). Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.CPSES -UNITS 1 AND 2- ODCM PART 11 F-2 Rev. 32 APPENDIX G SUPPLEMENTAL GUIDANCE STATEMENTS HAVE BEEN DELETED CPSES -UNITS 1 AND 2- ODCM PART 11 G-1 Rev. 23 CPSES/ODCM COMANCHE PEAK STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL (ODCM)EFFECTIVE LISTING FOR SECTIONS, TABLES, AND FIGURES BELOW IS A LEGEND FOR THE EFFECTIVE LISTING OF SECTIONS, TABLES, AND FIGURES: Revision 0 (TXX-89118)
Revision 1 (TXX-89595)
Revision 2 (TXX-8971 1)Revision 3 Revision 4 Revision 5 Revision 6 Revision 7 Revision 7A Revision 8 (Unit 2 Operations)
Revision 9 Revision 10 Revision 11 Revision 12 Revision 13 Revision 14 Revision 15 Revision 16 Revision 17 Revision 18 Revision 19 Revision 20 Revision 21 Revision 22 Revision 23 Revision 24 Revision 25 Revision 26 Revision 27 Revision 28 Revision 29 Revision 30 Revision 31 Revision 32 Revision 33 Submitted to the NRC March 2, 1989 Submitted to the NRC August 25, 1989 Submitted to the NRC November 27, 1989 April 10, 1990 October 9, 1990 December 20, 1990 July 3, 1991 December 4, 1991 August 6, 1992 January 1, 1993 September 28, 1994 April 22, 1994 November 7, 1994 December 8, 1995 February 14, 1996 October 1, 1996 March 3, 1999 July 27, 1999 October 7, 1999 December 20, 1999 October 16, 2001 July 8, 2002 March 23, 2004 December 8, 2004 January 31, 2006 March 13, 2006 June 1, 2006 December 12, 2006 July 24, 2007 September 11, 2008 February 26, 2009 September 1, 2009 April 4, 2011 April 4, 2011 January 31, 2013 Table of Contents Cross-Reference References CPSES/ODCM Revision 32 Revision 23 Revision 31 EL-1 Revision 33 CPSES/ODCM PART I Section 1 Table 1.1 Table 1.2 Section 2 Section 3/4 Bases 3/4 Section 5 Figure 5.1-3 Section 6 PART II Section 1 Table 1.1 Table 1.2 Figure 1.1 Figure 1.2 Figure 1.3 Section 2 Table 2.1 Table 2.2 Table 2.3 Table 2.4 Table 2.5 Figure 2.1 Figure 2.2 Figure 2.3 Figure 2.4 Figure 2.5 Section 3 Table 3.1 Figure 3.1 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G CPSES/ODCM Revision 28 Revision 27 Revision 27 Revision 23 Revision 33 Revision 23 Revision 23 Revision 23 Revision 31 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 33 Revision 26 Revision 23 Revision 32 Revision 32 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 23 Revision 32 Revision 32 Revision 32 Revision 23 EL-2 Revision 33 cPSESIODCM Revision 33 Revision 33 Revision 33 EL-1 EL-2 EL-3 Revisionl 33 EL-3 CpSES/ODCM OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 23 LDCR-OD-2006-2 (CPSES-200600206) (RJK): Revision 23 updates the entire ODCM to reflect the following changes: The electronic files have been converted from Microsoft Word to Adobe Framemaker and published in Adobe Portable Document Format (PDF).The type of changes include changes such as:-Correction of spelling errors-Correction of inadvertent word processing errors from previous changes-Style guide changes (e.g., changing from a numbered bullet list to an alphabetized bullet list and vice versa, change numbering of footnote naming scheme)-Administrative change only and contain no technical changes.This change maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
The entire ODCM will be reissued as Revision 23. For the text and tables there will be no change bars in the page margins for editorial changes. The list of effective pages is being replaced with a list of effective section, tables, and figure Sections Revised: All Tables Revised: All Figures Revised: All REVISION 24 LDCR-OD-2005-1 (EVAL-2005-003863-02) (GLM): Revision 24 updates ODCM Section 3/4 to reflect the following changes:* Delete the requirement to submit a special report outlining the cause of the malfunction and the plans for restoring the channel(s) to operable status.* Adds the requirement to initiate actions in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical.
CPSES/ODCM DOC-1 OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 24 (continued)
LDCR-OD-2005-1 (EVAL-2005-003863-02) (GLM) (continued):
The CPSES Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance.
The minimum set of conditions required by law to be reported to the NRC are contained in the Code Of Federal Regulations (10CFR50.73, 10CFR50.72, 10CFR73, etc.). This ODCM special report is not required by the CFRs, and there is no regulatory basis for this special report. There is no Technical Specification action, regulation, license condition, order, or commitment that requires this ODCM special report. The meteorological monitoring system is governed by Regulatory Guide 1.23, "Onsite Meteorological Programs", and this Regulatory Guide contains no requirement for a special report to the NRC. Based on the above, this ODCM special report is only an administrative requirement and therefore it can be deleted.Sections Revised: 3/4 Tables Revised: None Figures Revised: None REVISION 25 LDCR-OD-2006-3 (EVAL-2006-000932-01) (RJK): Revision 25 updates ODCM Section 3/4 to reflect the following changes: The 7 day allowance for planned and/or scheduled channel maintenance (similar to the TS COMPLETION TIME) was removed in error by Revision 24 of the ODCM (LDCR-OD-2005-01).
That revision intended only to remove the requirement to issue a Special Report to the NRC if the 7 days allowance was exceeded.This LDCR restores an acceptable outage duration for planned and/or scheduled work commensurate with the safety significance of this item.This change also maintains the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
Sections Revised: 3/4 Tables Revised: None Figures Revised: None CPSES/ODCM DOC-2 OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 26 LDCR-OD-2006-5 (EVAL-2006-002463-01) (RJK): Engineering evaluation ME-CA-0000-5326 assessed the potential gaseous effluent release from a planned decontamination facility on site. The evaluation also provides for operational controls on any similar facility to limit the source term and assess the effluents.
The proposed changes to the ODCM provide the framework to identify, control, and monitor any gaseous effluent pathway. The results of the monitoring are reported in the Radioactive Effluent Release Report, pursuant to ODCM Control 6.9.1.4.LDCR-OD-2006-6 (EVAL-2006-001766-01) (RJK): Revise Action Statement 37 (applicable to WRGM skid iodine and particulate channels)to add "If the number of channels OPERABLE is less than required by the "minimum Channels OPERABLE" requirement due to loss of heat tracing, then declare the Iodine &Particulate samplers INOPERABLE.
Restore the heat tracing within 7 days and declare the samplers OPERABLE or initiate action in accordance with the Corrective Action Program to restore the channel(s) to operable status as soon as practical." These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2, Type/Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways.
This 7 day period for entry into the CPSES Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance.
REVISION 27 LDCR-OD-2006-1 (EVAL-2005-001822-07) (GLM): Revise definition of DOSE EQUIVALENT IODINE 131 and add new definition for DOSE EQUIVALENT XENON 133.LAR 06-001 revises TS 3.4.16 to eliminate E-bar and adopt DOSE EQUIVALENT XE-1 33 for monitoring RCS gross specific activity.
This change makes the ODCM definition consistent with the revised TS definition.
REVISION 28 LDCR-OD-2007-1 (EVAL-2006-003080-05) (JDS): Revise Definition of Rated Thermal Power to reflect 4.5% increase on Units 1 and 2 as issued by the NRC in Amendment 146 to the Operating Licenses and Technical Specifications.
CPSES/ODCM DOG-3 OFFSITE DOSE CALCULATION MANUAL -Description of Changes REVISION 29 LDCR-OD-2007-2 (EVAL-2007-002019-01) (SCD): Revise Table 3.3-8 ACTION and associated statements to clarify necessary actions in the event of a loss of heat tracing or sample lines to the WRGM sampling skid. These particulate and iodine channels are USNRC Regulatory Guide 1.97, Revision 2, Type/Category E3 variables that provide backup information to estimate magnitude of release of radioactive materials to identify pathways.
This 7 day period for entry into the CPNPP Corrective Action Program is adequate to track the actions needed to restore the channel(s) to an operable status in a time commensurate with their safety significance.
REVISION 30 LDCR-OD-2009-1 (EVAL-2008-002039-03) (SCD): LDCR OD-2009-001 (tracked by SMF EVAL-2008-002039-03) changes Note 2 of Table 3.12-1 and Note 2 of Table 4.12-1 from thermo luminescent dosimeters (TLDs) to Optically Stimulated Luminescence (OSL) Badges. Also replace "thermoluminescent dosimeter" with "optically stimulated luminescence (OSL) badge" in section 2.5. This change acknowledges the recent switch from TLDs to OSLs.REVISION 31 LDCR-OD-201 1-1 (EV-CR-2010-010410-37) (SCD): Dose limits at the site boundary require monitoring to demonstrate compliance with the limits of 10 CFR 72 as a result of direct radiation exposure emitted by the facility.
The limits for the ISFSI are the same as the existing limits specified by 10 CFR 50 and therefore there are no changes to the monitoring criteria outlined in the ODCM.REVISION 32 LDCR-OD-2010-1 (EV-CR-2010-011250-1) (SCD): Revise the ODCM to incorporate the Carbon-14 isotope dose considerations into the CPNPP Radioactive Effluent Release Report in accordance with the new revision 2 of REGULATORY GUIDE 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste" This change is applicable to units 1 and 2.REVISION 33 LDCR-OD-2012-1 (EV-CR-2012-010400-2) (SCD): Administrative revision change references from OSL (Optically Stimulated Luminescence) to TLD (Thermoluminescent Dosimeter)
CPSES/ODCM DOC-4