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{{#Wiki_filter:APPENDIX D OFFSITE DOSE CALCULATION MANUAL Revision 20 95 PVNGS ARERR 2005 OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 REVISION 20 Originator Louis Drinovsky--Date: _ _Tech. Reviewer Kevin Kutner Date: Director, Radiation Protection John Gaffney Date: PRB John Hesser Date: Effective Date: August 31, 2005 TABLE OF CONTENTS TITLE PAGE  
{{#Wiki_filter:APPENDIX D OFFSITE DOSE CALCULATION MANUAL Revision 20 95                 PVNGS ARERR 2005
 
OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 REVISION 20 Originator         Louis Drinovsky                 -- Date: _ _
Tech. Reviewer     Kevin Kutner                       Date:
Director, Radiation Protection         John Gaffney                       Date:
PRB                 John Hesser                         Date:
Effective Date: August 31, 2005
 
TABLE OF CONTENTS TITLE                                                                                   PAGE


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
1 1.1  Liquid Effluent Pathways                                                              I 1.2  Gaseous Effluent Pathways                                                            2 1.3  Nuisance Pathways                                                                    2 1.4  Meteorology                                                                          4 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS                                                        5
===2.1 Requirements===
Gaseous Monitors                                                        5 2.1.1    Surveillance Requirements                                                    5 2.1.2    Implementation of the Requirements                                          12 2.1.2.1    Equivalent Dose Factor Determination                            13 2.1.2.2 Site Release Rate Limit (QsrrF)                                    14 2.1.2.3    Unit Release Rate Limits (QUNIT)                                15 2.1.2.4 Setpoint Determination                                              15 2.1.2.5    Monitor Calibration                                              16 3.0 GASEOUS AND LIQUID EFFLUENT DOSE RATES                                                    17


1 1.1 Liquid Effluent Pathways I 1.2 Gaseous Effluent Pathways 2 1.3 Nuisance Pathways 2 1.4 Meteorology 4 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS 5 2.1 Requirements:
===3.1 Requirements===
Gaseous Monitors 5 2.1.1 Surveillance Requirements 5 2.1.2 Implementation of the Requirements 12 2.1.2.1 Equivalent Dose Factor Determination 13 2.1.2.2 Site Release Rate Limit (QsrrF) 14 2.1.2.3 Unit Release Rate Limits (QUNIT) 15 2.1.2.4 Setpoint Determination 15 2.1.2.5 Monitor Calibration 16 3.0 GASEOUS AND LIQUID EFFLUENT DOSE RATES 17 3.1 Requirements:
Gaseous Effluents                                                       17 3.1.1   Surveillance Requirements                                                   17 3.1.2 Implementation of the Requirements                                             18
Gaseous Effluents 17 3.1.1 Surveillance Requirements 17 3.1.2 Implementation of the Requirements 18 3.2 Requirements:
Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System -Concentration 26 3.2.1 Surveillance Requirements 26 3.2.2 Implementation of the Requirements 26 4.0 GASEOUS & LIQUID EFFLUENTS
-DOSE 31 4.1 Requirements:
Noble Gases 31 4.1.1 Surveillance Requirements 31 4.1.2 Implementation of the Requirement:
Noble Gas 32 4.2 Requirement:
Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 33 4.2.1 Surveillance Requirements 33 4.2.2 Implementation of the Requirement 34 4.3 Requirements:
Gaseous Radwaste Treatment 36 4.3.1 Surveillance Requirements 36 4.3.2 Implementation of the Requirement 37 4A Requirements:
Liquid Effluents 57 4.4.1 Surveillance Requirements 57 4.4.2 Implementation of the Requirements 57 i ODCM Rev. 20 TABLE OF CONTENTS TITLE 5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 5.1 Requirement:
Total Dose 5.1.1 Surveillance Requirements


====5.1.2 Implementation====
===3.2 Requirements===
Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System - Concentration                                            26 3.2.1     Surveillance Requirements                                                  26 3.2.2    Implementation   of the Requirements                                        26 4.0  GASEOUS & LIQUID EFFLUENTS - DOSE                                                        31


of the Requirement
===4.1 Requirements===
Noble Gases                                                            31 4.1.1    Surveillance Requirements                                                  31 4.1.2    Implementation of the Requirement: Noble Gas                                32


===6.0 RADIOLOGICAL===
===4.2 Requirement===
Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days                                              33 4.2.1    Surveillance Requirements                                                  33 4.2.2    Implementation of the Requirement                                          34


ENVIRONMENTAL MONITORING PROGRAM (REMP)6.1 Requirement:
===4.3 Requirements===
REMP 6.1.1 Surveillance Requirements
Gaseous Radwaste Treatment                                            36 4.3.1   Surveillance Requirements                                                  36 4.3.2 Implementation of the Requirement                                             37 4A  Requirements: Liquid Effluents                                                      57 4.4.1   Surveillance Requirements                                                   57 4.4.2    Implementation of the Requirements                                          57 i                                    ODCM Rev. 20


====6.1.2 Implementation====
TABLE OF CONTENTS TITLE                                                                                        PAGE 5.0  TOTAL DOSE AND DOSE TO PUBLIC ONSITE                                                          58


of the Requirements
===5.1 Requirement===
Total Dose                                                                    58 5.1.1 Surveillance Requirements                                                            58 5.1.2 Implementation of the Requirement                                                    58 6.0  RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)                                          62
 
===6.1 Requirement===
REMP                                                                          62 6.1.1    Surveillance Requirements                                                        63 6.1.2 Implementation of the Requirements                                                   63


===6.2 Requirement===
===6.2 Requirement===
Land Use Census                                                              71 6.2.1    Surveillance Requirements                                                        71 6.2.2 Implementation of the Requirements                                                  71


Land Use Census 6.2.1 Surveillance Requirements
===6.3 Requirement===
Interlaboratory Comparison Program                                            72 6.3.1   Surveillance Requirements                                                         72 6.3.2 Implementation of the Requirements                                                  72 7.0  RADIOLOGICAL REPORTS                                                                          83


====6.2.2 Implementation====
===7.1 Requirement===
Annual Radioactive Effluent Release Report                                    83


of the Requirements
===7.2 Requirement===
Annual Radiological Environmental Operating Report                            85 APPENDIX A    DETERMINATION OF CONTROLLING LOCATION                                                86 APPENDIX B    BASES  FOR REQUIREMENTS                                                              87 2.1    RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION                      87 3.1    GASEOUS EFFLUENT - DOSE RATE                                                87 3.2    SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - CONCENTRATION                                    88 4.1    GASEOUS EFFLUENT - DOSE, Noble Gases                                        88 4.2    GASEOUS EFFLUENT - DOSE - Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days89 4.3    GASEOUS RADWASTE TREATMENT                                                  89 4.4    SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - DOSE                                              90 5.1    TOTAL DOSE AND DOSE TO PUBLIC ONSITE                                        90 6.1    RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 91 6.2    LAND USE CENSUS                                                              91 6.3    INTERLABORATORY COMPARISON PROGRAM                                          91 APPENDIX C    DEFINITIONS                                                                          92 APPENDIX D    REFERENCES                                                                          96 ii                                    ODCM Rev. 20


===6.3 Requirement===
LIST OF TABLES TABLE                    TITLE                                                  PAGE 1-1  NUISANCE PATHWAYS                                                            3 2-1  RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION                      6 2-2  RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS                                                  10 3-1  RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM                    20 3-2  DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY                                                        23 3-3  DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS                                  24 3-4  Pi VALUES FOR THE INHALATION PATHWAY                                        25 3-5  RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM                      27 3-6  RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION                      30 3-7  RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS                                                  30 4-1  Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY                    39 4-2  Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - ADULT RECEPTOR      40 4-3  Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - TEEN RECEPTOR      41 4-4  Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR      42 4-5  Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - ADULT RECEPTOR 43 4-6  Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - TEEN RECEPTOR  44 4-7  Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILD RECEPTOR  45 4-8  Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - ADULT RECEPTOR  46 4-9  Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEEN RECEPTOR  47 4-10 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - CHILD RECEPTOR  48
                                          .. .                            ODCM Rev. 20
 
LIST OF TABLES TABLE                    TITLE                                                  PAGE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR 49 4-12 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - ADULT RECEPTOR      50 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -TEEN RECEPTOR        51 4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILD RECEPTOR      52 4-15 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTOR    53 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 1                                                54 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2                                                55 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3                                                56 6-1  RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM                              64 6-2  REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES                                                      68 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS                          69 6-4  RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS          73 C-1  FREQUENCY NOTATION                                                          95 iv                              ODCM Rev. 20


Interlaboratory Comparison Program 6.3.1 Surveillance Requirements
LIST OF FIGURES FIGURE                    TITLE                                              PAGE 6-1  RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-10 MILES  77 6-2  RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-35 MILES 78 6-3   DELETED                                                                79 6-4  SITE EXCLUSION AREA BOUNDARY                                            80 6-5  GASEOUS EFFLUENTS RELEASE POINTS                                        81 6-6  LOW POPULATION ZONE 0-5 MILES                                            82 v                              ODCM Rev. 20


====6.3.2 Implementation====
==1.0    INTRODUCTION==


of the Requirements
The Offsite Dose Calculation Manual (ODCM) implements the program elements which are required by the Administrative Controls section of the Technical Specifications. The ODCM contains the operational requirements, the surveillance requirements, and actions required if the operational requirements are not met for the Radioactive Effluent Controls Program and the Radiological Environmental Monitoring Program to assure compliance with 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. The Technical Specifications, Section 3.0, also apply to the ODCM. Substitute the word "Requirements" for "Limiting Condition for Operation." It should be noted that the hot and cold shutdown and operability requirements in Technical Specification 3.0.3 and 3.0.4 do not apply to any of the requirements contained in this ODCM. The ODCM also contains descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by the Technical Specifications.
The ODCM provides the parameters and methodology to be used in calculating offsite doses resulting from radioactive effluents, in the calculation of gaseous effluent monitor Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. Included are methods for determining air, whole body, and organ dose at the controlling location due to plant effluents to assure compliance with the regulatory requirements detailed in the ODCM. Methods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the ODCM. The ODCM utilizes information from NRC Regulatory Guide 1.109, "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," October 1977, and NRC NUREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"
October 1978. NUREG 0133 utilizes some of the key information in Regulatory Guide 1.109 to provide methods which were used in the preparation of the radiological effluent Technical Specifications and which have now been transferred to the ODCM in accordance with NRC Generic Letter 89-01, "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," January 31, 1989, and NUREG 1301, "Offsite Dose Calculation Manual Guidance:
Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01, Supplement No. 1, April 1991. Further guidance for the implementation of the new 10 CFR Part 20, effective January 1, 1994, was obtained from the Federal Register, Vol. 58, December 23, 1993. It is recognized that this is only draft guidance, however, it is the only guidance for referencing the new 10 CFR 20 in the ODCM.
1.1 Liquid Effluent Pathways Dose calculation methodology for radioactive liquid effluents is not included in this manual due to the desert location of the plant, the hydrology of the area, and the fact that there are no liquid releases to areas at or beyond the SITE BOUNDARY during normal operation. All liquid discharges to the onsite evaporation ponds are controlled by Section 3.2. The impact of postulated accidental seepages on the groundwater system, and in particular on the existing wells located in the 5-mile zone around the site area has been calculated and analyzed in Section 2.4.13.3 of the PVNGS FSAR.
If plant operating conditions become such that the likelihood of a liquid effluent pathway is created, then dose calculation methodology for this pathway will be added to this manual.
I                                          ODCM Rev. 20


===7.0 RADIOLOGICAL===
12 Gaseous Effluent Pathways All gaseous effluents are treated as ground level releases and are considered to be "long-term" as discussed in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." This includes the containment purge and Waste Gas Decay Tank releases as well as the normal ventilation system and condenser vacuum exhaust releases. All releases are either greater than 500 hours in duration or are made at random, not depending upon atmospheric conditions or time of day. The releases are lumped together and calculated as an entity. Historical annual average X/Q values are used throughout this manual for all gaseous effluent setpoint and dose calculations. Airborne releases are further subdivided into two subclasses:
1.2.1 Iodine-131, Iodine-133, Tritium and Radionuclides In Particulate Form with Half-lives Greater than Eight Days In this model, a controlling location is identified for assessing the maximum exposure to a MEMBER OF THE PUBLIC for the various pathways and to critical organs. Infant exposure occurs through inhalation and any actual milk pathway. Child, teenager and adult exposure derives from inhalation, consumed vegetation pathways, and any actual milk and meat pathways. Dose to each of the seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung and GI-LLI) are computed from individual nuclide contributions in each sector. The largest of the organ doses in any sector is compared to 10 CFR 50, Appendix I design objectives. The release rates of these nuclides will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.
1.2.2 Noble Gases The air dose from both the beta and gamma radiation component of the noble gases will be assessed and compared to the 10 CFR 50, Appendix I design objectives. The noble gas release rate will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.
Section 2.0 of this manual discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to assure compliance with the 10 CFR Part 20 limits as implemented in Section 3.0. Section 4.0 discusses the methods to assure releases are As Low As Reasonably Achievable (ALARA) in accordance with Appendix I to 10 CFR Part 50.
Methods are described in Section 5.0 for determining the annual cumulative dose to a MEMBER OF THE PUBLIC from gaseous effluents and direct radiation to assure compliance with 40 CFR Part 190.
The requirements for the Annual Radiological Effluent Release Report and the Radiological Environmental Monitoring Program, including the Annual Land Use Census and the Interlaboratory Comparison Program, and the Annual Environmental Report are described in Sections 6.0 and 7.0 of this manual.
13 Nuisance Pathways This section addresses the potential release pathways which should not contribute more than 10% of the doses evaluated in this manual. Table 1-1 lists examples of potential release pathways. The ODCM methodology for calculation of doses will be applied to an applicable release pathway if a likely potential arises for contributing more than 10% of the doses evaluated in this manual.
2                                      ODCM Rev. 20


REPORTS 7.1 Requirement:
TABLE 1-1 NUISANCE PATHWAYS (EXAMPLES)
Annual Radioactive Effluent Release Report 7.2 Requirement:
Evaporation Pond Cooling Towers Laundry/Decon Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents Dry Active Waste Processing and Storage (DAWPS) Building Respirator Cleaning Facility Secondary Side Decontamination Equipment Low Level Radioactive Material Storage Facility 3     ODCM Rev. 20
Annual Radiological Environmental Operating Report PAGE 58 58 58 58 62 62 63 63 71 71 71 72 72 72 83 83 85 APPENDIX A APPENDIX B APPENDIX C APPENDIX D DETERMINATION OF CONTROLLING LOCATION 86 BASES FOR REQUIREMENTS 87 2.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 87 3.1 GASEOUS EFFLUENT -DOSE RATE 87 3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS -CONCENTRATION 88 4.1 GASEOUS EFFLUENT -DOSE, Noble Gases 88 4.2 GASEOUS EFFLUENT -DOSE -Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days89 4.3 GASEOUS RADWASTE TREATMENT 89 4.4 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS -DOSE 90 5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 90 6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 91 6.2 LAND USE CENSUS 91 6.3 INTERLABORATORY COMPARISON PROGRAM 91 DEFINITIONS 92 REFERENCES 96 ii ODCM Rev. 20 LIST OF TABLES TABLE TITLE PAGE 1-1 NUISANCE PATHWAYS 3 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 6 2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 10 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 20 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY 23 3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 24 3-4 Pi VALUES FOR THE INHALATION PATHWAY 25 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 27 3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 30 3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 30 4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY 39 4-2 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY -ADULT RECEPTOR 40 4-3 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY -TEEN RECEPTOR 41 4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY -CHILD RECEPTOR 42 4-5 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY -ADULT RECEPTOR 43 4-6 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY -TEEN RECEPTOR 44 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY -CHILD RECEPTOR 45 4-8 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY -ADULT RECEPTOR 46 4-9 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY -TEEN RECEPTOR 47 4-10 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY -CHILD RECEPTOR 48.. .ODCM Rev. 20 LIST OF TABLES TABLE TITLE PAGE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY -INFANT RECEPTOR 49 4-12 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -ADULT RECEPTOR 50 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -TEEN RECEPTOR 51 4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -CHILD RECEPTOR 52 4-15 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -INFANT RECEPTOR 53 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 1 54 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 55 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 56 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 64 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 68 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS 69 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS 73 C-1 FREQUENCY NOTATION 95 iv ODCM Rev. 20 LIST OF FIGURES FIGURE TITLE PAGE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-10 MILES 77 6-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-35 MILES 78 6-3 DELETED 79 6-4 SITE EXCLUSION AREA BOUNDARY 80 6-5 GASEOUS EFFLUENTS RELEASE POINTS 81 6-6 LOW POPULATION ZONE 0-5 MILES 82 v ODCM Rev. 20  


==1.0 INTRODUCTION==
1A Meteorology Historical annual average atmospheric dispersion (X/Q) and deposition (D/Q) data, based on nine years of meteorological data, and given in Table 3-2 for each of the three nuclear generating units are used to demonstrate compliance with the ODCM Requirements. These Requirements include:
Section 2.0              Gaseous Effluent Monitor Setpoints; Section 3.0             Gaseous and Liquid Effluent - Dose Rate Section 4.0              Gaseous and Liquid Effluent - Dose Section 5.0              Total Dose and Dose to Public Onsite Sections 2.0 and 3.0 specify utilizing the highest X/Q or D/Q meteorological dispersion parameter at the Site Boundary for any of the three units as applicable. Using the highest dispersion parameter for any of the units provides a conservative assumption to assure compliance with the higher 10 CFR Part 20 limits.
Section 4.0 specifies utilizing the highest X/Q at the Site Boundary for the particular unit, from Table 3-2 for noble gases. The highest XIQ and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathway's location (site boundary using Table 3-2 or other controlling locations using Table 4-16, 4-17, or 4-18).
Section 5.0 specifies utilizing the highest X/Q for the particular unit's releases at the controlling location from Table 4-16,4-17, or 4-18, for noble gases. The highest X/Q and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases at the controlling pathway's location using Table 4-16, 4-17, or 4-18.
Section 7.0 requires that 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.
4                                      ODCM Rev. 20


The Offsite Dose Calculation Manual (ODCM) implements the program elements which are required by the Administrative Controls section of the Technical Specifications.
2.0 GASEOUS EFFLUENT MONITOR SETPOINTS
The ODCM contains the operational requirements, the surveillance requirements, and actions required if the operational requirements are not met for the Radioactive Effluent Controls Program and the Radiological Environmental Monitoring Program to assure compliance with 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. The Technical Specifications, Section 3.0, also apply to the ODCM. Substitute the word "Requirements" for "Limiting Condition for Operation." It should be noted that the hot and cold shutdown and operability requirements in Technical Specification 3.0.3 and 3.0.4 do not apply to any of the requirements contained in this ODCM. The ODCM also contains descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by the Technical Specifications.
The ODCM provides the parameters and methodology to be used in calculating offsite doses resulting from radioactive effluents, in the calculation of gaseous effluent monitor Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. Included are methods for determining air, whole body, and organ dose at the controlling location due to plant effluents to assure compliance with the regulatory requirements detailed in the ODCM. Methods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the ODCM. The ODCM utilizes information from NRC Regulatory Guide 1.109,"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," October 1977, and NRC NUREG 0133,"Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978. NUREG 0133 utilizes some of the key information in Regulatory Guide 1.109 to provide methods which were used in the preparation of the radiological effluent Technical Specifications and which have now been transferred to the ODCM in accordance with NRC Generic Letter 89-01, "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," January 31, 1989, and NUREG 1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01, Supplement No. 1, April 1991. Further guidance for the implementation of the new 10 CFR Part 20, effective January 1, 1994, was obtained from the Federal Register, Vol. 58, December 23, 1993. It is recognized that this is only draft guidance, however, it is the only guidance for referencing the new 10 CFR 20 in the ODCM.1.1 Liquid Effluent Pathways Dose calculation methodology for radioactive liquid effluents is not included in this manual due to the desert location of the plant, the hydrology of the area, and the fact that there are no liquid releases to areas at or beyond the SITE BOUNDARY during normal operation.
All liquid discharges to the onsite evaporation ponds are controlled by Section 3.2. The impact of postulated accidental seepages on the groundwater system, and in particular on the existing wells located in the 5-mile zone around the site area has been calculated and analyzed in Section 2.4.13.3 of the PVNGS FSAR.If plant operating conditions become such that the likelihood of a liquid effluent pathway is created, then dose calculation methodology for this pathway will be added to this manual.I ODCM Rev. 20 12 Gaseous Effluent Pathways All gaseous effluents are treated as ground level releases and are considered to be "long-term" as discussed in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." This includes the containment purge and Waste Gas Decay Tank releases as well as the normal ventilation system and condenser vacuum exhaust releases.
All releases are either greater than 500 hours in duration or are made at random, not depending upon atmospheric conditions or time of day. The releases are lumped together and calculated as an entity. Historical annual average X/Q values are used throughout this manual for all gaseous effluent setpoint and dose calculations.
Airborne releases are further subdivided into two subclasses:
1.2.1 Iodine-131, Iodine-133, Tritium and Radionuclides In Particulate Form with Half-lives Greater than Eight Days In this model, a controlling location is identified for assessing the maximum exposure to a MEMBER OF THE PUBLIC for the various pathways and to critical organs. Infant exposure occurs through inhalation and any actual milk pathway. Child, teenager and adult exposure derives from inhalation, consumed vegetation pathways, and any actual milk and meat pathways.
Dose to each of the seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung and GI-LLI) are computed from individual nuclide contributions in each sector. The largest of the organ doses in any sector is compared to 10 CFR 50, Appendix I design objectives.
The release rates of these nuclides will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.1.2.2 Noble Gases The air dose from both the beta and gamma radiation component of the noble gases will be assessed and compared to the 10 CFR 50, Appendix I design objectives.
The noble gas release rate will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.Section 2.0 of this manual discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to assure compliance with the 10 CFR Part 20 limits as implemented in Section 3.0. Section 4.0 discusses the methods to assure releases are As Low As Reasonably Achievable (ALARA) in accordance with Appendix I to 10 CFR Part 50.Methods are described in Section 5.0 for determining the annual cumulative dose to a MEMBER OF THE PUBLIC from gaseous effluents and direct radiation to assure compliance with 40 CFR Part 190.The requirements for the Annual Radiological Effluent Release Report and the Radiological Environmental Monitoring Program, including the Annual Land Use Census and the Interlaboratory Comparison Program, and the Annual Environmental Report are described in Sections 6.0 and 7.0 of this manual.13 Nuisance Pathways This section addresses the potential release pathways which should not contribute more than 10% of the doses evaluated in this manual. Table 1-1 lists examples of potential release pathways.
The ODCM methodology for calculation of doses will be applied to an applicable release pathway if a likely potential arises for contributing more than 10% of the doses evaluated in this manual.2 ODCM Rev. 20 TABLE 1-1 NUISANCE PATHWAYS (EXAMPLES)
Evaporation Pond Cooling Towers Laundry/Decon Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents Dry Active Waste Processing and Storage (DAWPS) Building Respirator Cleaning Facility Secondary Side Decontamination Equipment Low Level Radioactive Material Storage Facility 3 ODCM Rev. 20 1A Meteorology Historical annual average atmospheric dispersion (X/Q) and deposition (D/Q) data, based on nine years of meteorological data, and given in Table 3-2 for each of the three nuclear generating units are used to demonstrate compliance with the ODCM Requirements.
These Requirements include: Section 2.0 Gaseous Effluent Monitor Setpoints; Section 3.0 Gaseous and Liquid Effluent -Dose Rate Section 4.0 Gaseous and Liquid Effluent -Dose Section 5.0 Total Dose and Dose to Public Onsite Sections 2.0 and 3.0 specify utilizing the highest X/Q or D/Q meteorological dispersion parameter at the Site Boundary for any of the three units as applicable.
Using the highest dispersion parameter for any of the units provides a conservative assumption to assure compliance with the higher 10 CFR Part 20 limits.Section 4.0 specifies utilizing the highest X/Q at the Site Boundary for the particular unit, from Table 3-2 for noble gases. The highest XIQ and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathway's location (site boundary using Table 3-2 or other controlling locations using Table 4-16, 4-17, or 4-18).Section 5.0 specifies utilizing the highest X/Q for the particular unit's releases at the controlling location from Table 4-16,4-17, or 4-18, for noble gases. The highest X/Q and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases at the controlling pathway's location using Table 4-16, 4-17, or 4-18.Section 7.0 requires that 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.4 ODCM Rev. 20


===2.0 GASEOUS===
===2.1 Requirements===
EFFLUENT MONITOR SETPOINTS 2.1 Requirements:
Gaseous Monitors The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.0 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 2.1.2.
Gaseous Monitors The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.0 are not exceeded.
Applicability:     As shown in Table 2-1.
The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 2.1.2.Applicability:
Action:
As shown in Table 2-1.Action: a. With the low range radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Requirement, 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.
: a. With the low range radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Requirement, 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 2-1. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.
: b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.
2.1.1 Surveillance Requirements
: a. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2.
5s                                    ODCM Rev. 20


====2.1.1 Surveillance====
TABLE 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT                              OPERABLE    APPLICABILITY ACTION
: 1. GASEOUS RADWASTE SYSTEM
: a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release #RU- 12                                          35
: b. Flow Rate Monitor                                                                36
: 2. NOT USED
: 3. DELETED
: 4. PLANT VENT SYSTEM A. Low Range Monitors ON
: a. Noble Gas Activity Monitor #RU-143
* 37
: b. Iodine Sampler
* 40
: c. Particulate Sampler                                                          40
: d. Flow Rate Monitor
* 36
: e. Sampler Flow Rate Measuring Device
* 36 B. High Range Monitors
: a. Noble Gas Activity Monitor #RU-144
* 42
: b. Iodine Sampler
* 42 C      c. Particulate Sampler
* 42
: d. Sampler Flow Rate Measuring Device
* 42 0


Requirements
: a. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2.5s ODCM Rev. 20 TABLE 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS ON INSTRUMENT
: 1. GASEOUS RADWASTE SYSTEM a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release #RU- 12 b. Flow Rate Monitor 2. NOT USED 3. DELETED 4. PLANT VENT SYSTEM A. Low Range Monitors a. Noble Gas Activity Monitor #RU-143 b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Measuring Device B. High Range Monitors a. Noble Gas Activity Monitor #RU-144 b. Iodine Sampler c. Particulate Sampler d. Sampler Flow Rate Measuring Device OPERABLE APPLICABILITY 35 36 ACTION*****37 40 40 36 36***42 42 42 42 C 0*
TABLE 2-1 (Continued)
TABLE 2-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT                         OPERABLE       APPLICABILITY ACTION
: 5. FUEL BUILDING VENTILATION SYSTEM A. Low Range Monitors a. Noble Gas Activity Monitor #RU- 145 1 b. Iodine Sampler 1 ##c. Particulate Sample 1 #4 d. Flow Rate Monitor 1 ##e. Sampler Flow Rate Measuring Device 1 ##B. High Range Monitors a. Noble Gas Activity Monitor #RU-146 1 ##b. Iodine Sampler 1 4*c. Particulate Sample 1 ##d. Sampler Flow Rate Measuring Device 1 #I ACTION 37,41 40 40 36 36 42 42 42 42 0 to 0 Table 2-1 (Continued)
: 5. FUEL BUILDING VENTILATION SYSTEM A. Low Range Monitors
TABLE NOTATION* At all times.** During GASEOUS RADWASTE SYSTEM operation*** Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).
: a. Noble Gas Activity Monitor #RU- 145             1                         37,41
# During waste gas release.## In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.ACTION 35 -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. At least two independent samples of the tanks contents are analyzed, and b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup;Otherwise, suspend release of radioactive effluents via this pathway.ACTION 36 -ACTION 37 -ACTION 38 -ACTION 39 -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.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (a) or (b) or (c) are performed:
: b. Iodine Sampler                                 1               ##       40
: c. Particulate Sample                             1               #4       40
: d. Flow Rate Monitor                               1               ##       36
: e. Sampler Flow Rate Measuring Device             1               ##       36 B. High Range Monitors
: a. Noble Gas Activity Monitor #RU-146             1               ##       42
: b. Iodine Sampler                                 1               4*       42
: c. Particulate Sample                             1               ##       42
: d. Sampler Flow Rate Measuring Device               1               #I       42 0
to 0
 
Table 2-1 (Continued)
TABLE NOTATION
* At all times.
**   During GASEOUS RADWASTE SYSTEM operation
*** Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).
#     During waste gas release.
##   In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.
ACTION 35 -     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. At least two independent samples of the tanks contents are analyzed, and
: b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 36 -     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.
ACTION 37 -    With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (a) or (b) or (c) are performed:
: a. Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s).
: a. Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s).
: b. Place moveable air monitors in-line.c. Either take grab samples at least once per 12 hours, OR obtain gas channel monitor readings locally at least once per 12 hours if the channel is functional locally but inoperable due to loss of communication with the minicomputer.
: b. Place moveable air monitors in-line.
The surveillance requirements of Section 2.1.1 must be performed at the required frequencies for the channel to be functional locally.NOT USED NOT USED ACTION 40 -ACTION 41 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 3-1 within one hour after the channel has been declared inoperable.
: c. Either take grab samples at least once per 12 hours, OR obtain gas channel monitor readings locally at least once per 12 hours if the channel is functional locally but inoperable due to loss of communication with the minicomputer. The surveillance requirements of Section 2.1.1 must be performed at the required frequencies for the channel to be functional locally.
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, comply with Technical Requirements Manual TLCO 3.3.108.8 ODCM Rev. 20 Table 2-1 (Continued)
ACTION 38 -    NOT USED ACTION 39 - NOT USED ACTION 40 -     With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 3-1 within one hour after the channel has been declared inoperable.
TABLE NOTATION ACTION 42 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement restore the channel to OPERABLE status within 72 hours or: a. Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) when it is needed.b. Prepare and submit a Special Report to the Commission within 30 days following the event outlining the action(s) taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.9 ODCM Rev. 20 TABLE 2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 0 0 0 INSTRUMENT
ACTION 41 -      With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, comply with Technical Requirements Manual TLCO 3.3.108.
: 1. GASEOUS RADWASTE SYSTEM a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release RU-12 b. Flow Rate Monitor 2. DELETED 3. DELETED 4. PLANT VENT SYSTEM (RU-143 and RU-144)a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sampler d. Flow Rate Monitor e. Sampler Flow Rate Measuring Device 5. FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)a. Noble Gas Activity Monitor b. Iodine Sampler c. Particulate Sample d. Flow Rate Monitor e. Sampler Flow Rate Measuring Device CHANNEL CHECK p P D(5)N.A.N.A.D(6)D(6)D(5)N.A.N.A.D(6)D(6)SOURCE CHECK P(7)N.A.M(7)N.A.N.A.N.A.N.A.M(7)N.A.N.A.N.A.N.A.CHANNEL CALIBRATION R(3)R R(3)N.A.N.A.R R R(3)N.A.N.A.R R CHANNEL MODE IN WHICH FUNCTIONAL SURVEILLANCE TEST IS REQUIRED Q(I),(2),P####
8                                   ODCM Rev. 20
Q,P###Q(2)N.A.N.A.Q Q*****Q(2)N.A.N.A.Q Q Table 2-2 (Continued)
 
TABLE NOTATION* At all times.** During GASEOUS RADWASTE SYSTEM operation*** Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).
Table 2-1 (Continued)
# During waste gas release.## In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.### Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.
TABLE NOTATION ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement restore the channel to OPERABLE status within 72 hours or:
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured levels above the alarm setpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(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 may be used in lieu of the reference standards associated with the initial calibration.
: a. Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) when it is needed.
: b. Prepare and submit a Special Report to the Commission within 30 days following the event outlining the action(s) taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.
9                                   ODCM Rev. 20
 
TABLE 2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL        MODE IN WHICH CHANNEL    SOURCE    CHANNEL  FUNCTIONAL      SURVEILLANCE INSTRUMENT                         CHECK      CHECK  CALIBRATION    TEST        IS REQUIRED
: 1. GASEOUS RADWASTE SYSTEM
: a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release RU-12       p        P(7)    R(3)    Q(I),(2),P####
: b. Flow Rate Monitor                               P          N.A.      R        Q,P###
: 2. DELETED
: 3. DELETED
: 4. PLANT VENT SYSTEM (RU-143 and RU-144) 0                                                                                                          *
: a. Noble Gas Activity Monitor                     D(5)        M(7)    R(3)          Q(2)
: b. Iodine Sampler                                 N.A.        N.A. N.A.          N.A.
: c. Particulate Sampler                           N.A.        N.A. N.A.          N.A.
: d. Flow Rate Monitor                             D(6)        N.A.      R            Q
: e. Sampler Flow Rate Measuring Device             D(6)        N.A.      R            Q
: 5. FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)
: a. Noble Gas Activity Monitor                     D(5)       M(7)     R(3)         Q(2)
: b. Iodine Sampler                                N.A.       N.A. N.A.         N.A.
0    c. Particulate Sample                            N.A.       N.A. N.A.         N.A.
: d. Flow Rate Monitor                              D(6)       N.A.       R           Q 0
: e. Sampler Flow Rate Measuring Device            D(6)       N.A.       R            Q
 
Table 2-2 (Continued)
TABLE NOTATION
* At all times.
** During GASEOUS RADWASTE SYSTEM operation
*** Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).
#   During waste gas release.
## In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.
### Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
: 1.     Instrument indicates measured levels above the alarm setpoint.
: 2.     Circuit failure.
: 3.     Instrument indicates a downscale failure.
: 4.     Instrument controls not set in operate mode.
(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 may be used in lieu of the reference standards associated with the initial calibration.
(4) NOT USED (5) The channel check for channels in standby status shall consist of verification that the channel is on-line and reachable.
(4) NOT USED (5) The channel check for channels in standby status shall consist of verification that the channel is on-line and reachable.
(6) Daily channel check not required for flow monitors in standby status.(7) LED may be utilized as the check source in lieu of a source of increased activity.I1I ODCM Rev. 20  
(6) Daily channel check not required for flow monitors in standby status.
(7) LED may be utilized as the check source in lieu of a source of increased activity.
I1I                                         ODCM Rev. 20
 
2.1.2 Implementation of the Requirements The general methodology for establishing low range gaseous effluent monitor setpoints is based upon a site release rate limit in iLCO/sec derived from site specific meteorological dispersion conditions, radioisotopic distribution, and whole body and skin dose factors. The high alarm of the low range monitors will alarm/trip when the release rate from an individual vent will result in exceeding the limits in Section 3.1. 80% of Section 3.1 limits is considered to be the site release rate limit. The site release rate limit will be allocated among the licensed units' release points. The unit release rate limit will then be utilized for the determination of gaseous effluent monitor setpoints. A fraction of the unit release rate limit is then allotted to each release point and its monitor alert setpoint (gCi/cc) is derived using actual or fan design flow rates.
Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be reviewed based on actual release data.
For the purpose of implementation of Section 2.1, the alarm setpoint levels for low range effluent noble gas monitors are established to ensure that personnel are alerted when the noble gas releases are at a rate such that if the releases would continue for the year they would approach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose in Section 3.1.
The equations in Section 3.1 of this manual provide the methodology for calculating the gaseous effluent dose rate.
The evaluation of doses due to releases of radioactive material can be simplified by the use of equivalent dose factors as defined in Section 2.1.2. 1.
The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is being used for the dose equivalent value.
12                                        ODCM Rev. 20
 
2.1.2.1 Equivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows:
Keq = Ej[(Ki)(fi)]                                                                (2-1)
Where:
Keq            = the equivalent whole body dose factor weighted by historical radionuclide distribution in releases in mremlyr per g+/-Ci/m 3 .
Ki            = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per g Ci/m3 from Table 3-3.
fi            = the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.
The equivalent skin dose factor is calculated as follows:
(L + l.lM)eq = Ei[(Li + 1-.Mi)(fi)]                                            (2-2)
Where:
(L+1.lM)eq = the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases in mrem/yr per gCi/m 3.
Li            = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per gCi/m3 from Table 3-3.
Mi            = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per g+/-Ci/m 3 from Table 3-3.
fi            = the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.
1.1          = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.
13                                      ODCM Rev. 20
 
2.1.2.2 Site Release Rate Limit (QsrrF)
The release rates corresponding to 80% of the whole body (QWB) and skin (QSK) dose rate limits are calculated using the equivalent dose factors defined in Section 2.1.2.1.
The site release rate limit (QSffE) is the lower Of QWB or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded.
The QSrrE is established as follows:
QSITEWB          (DWB)(08)                                                        (2-3)
(Keq)(X/Q)SITE Where:
QSrrE,WB        = the site release rate, in jiCi/sec, that would deliver a dose rate 80% of the whole body dose rate limit, DWB.
DWB            = whole body dose rate limit of 500 mrem/yr.
3 Keq            =  equivalent whole body dose factor, in mrem/yr per pCi/M weighted by the historical radionuclide distribution.
(X/Q)SrrE      = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/M3 , at the Site Boundary for any of the 3 units, from Table 3-2.
0.8            = administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.
QSIT SK =            (DSK)(O. 8 )                                                  (24)
QsIE~s =(L    + 1-IM)eq(X/Q)SITE(2)
Where:
QSrrE,SK      = the site release rate limit, in pCi/sec, that would deliver a dose rate 80% of the skin dose rate limit, DSK.
DSK            = skin dose rate limit of 3000 mrem/yr.
3 (L+ l.lM),q = equivalent skin dose factor, in mrem/yr per glCi/m , weighted by the radionuclide distribution.
(/Q)SrrE      = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/n 3 , at the Site Boundary for any of the three units, from Table 3-2.
0.8          = administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.
After determination of the QSrE whole body and skin dose rates (equations 2-3 and 2-4, respectively), the most conservative result will be used as QsITE, the site release rate limit.
14                                        ODCM Rev. 20


====2.1.2 Implementation====
2.1.23 Unit Release Rate Limits (QuNrr)
Typically QSrrE will be divided equally among operating units. If operational history dictates a larger fraction of the QsrrE be assigned to a specific unit then a weighted average of each unit's contribution to the QSrrE will be utilized to determine the QUNrr.
QUNIT          = (uNrr) (QSiTE)                                                        (2-5)
Where:
QUNIT          = unit release rate limit, in pCi/sec.
fUNIT          = the fraction (* 1) of noble gas historically released from a specific operating unit to the total of all noble gas released from the site.
QsrrE          = the site release rate limit, in gCi/sec determined in Section 2.1.2.2.
2.1.2.4 Setpoint Determination To comply with the requirements in Section 2.1, the alarm/trip setpoints can now be established using the unit release rate limit (QUNrT) to ensure that the noble gas releases do not exceed the dose rate limits.
To allow for multiple sources of releases from different or common release points, the effluent monitor setpoint includes an administrative factor which allocates a percentage of the unit release rate limit to each of the release sources. Monitor setpoints will also be adjusted in accordance with Nuclear Administrative and Technical Manual procedures to account for monitor-specific characteristics.
Monitors RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-143 and RU-145 is calculated as follows:
Monitor        (QUNIT)(a)
Setpoint    (472)(Flow Rate)                                                        (2-6)
Where:
Monitor Setpoint      = the setpoint for the effluent monitor, in pCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
QUNIT          = unit release rate limit, in pCi/sec, as determined in Section 2.1.2.3.
Flow Rate      = the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration.
472            = conversion factor, cubic centimeter/second per cubic feet/minute.
a              = fraction of QUNPr allocated for a specific release point. The sum of these administrative values shall be less than or equal to one.
15                                      ODCM Rev. 20


of the Requirements The general methodology for establishing low range gaseous effluent monitor setpoints is based upon a site release rate limit in iLCO/sec derived from site specific meteorological dispersion conditions, radioisotopic distribution, and whole body and skin dose factors. The high alarm of the low range monitors will alarm/trip when the release rate from an individual vent will result in exceeding the limits in Section 3.1. 80% of Section 3.1 limits is considered to be the site release rate limit. The site release rate limit will be allocated among the licensed units' release points. The unit release rate limit will then be utilized for the determination of gaseous effluent monitor setpoints.
Monitor RU- 2 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:
A fraction of the unit release rate limit is then allotted to each release point and its monitor alert setpoint (gCi/cc) is derived using actual or fan design flow rates.Administrative values are used to reduce each setpoint to account for the potential activity in other releases.
Monitor < [(QUNIT)(a)(O. 9 ) - (H)(PF)(472)]                                     (2-7) setpoint             (Flow Rate)(472)
These administrative values shall be reviewed based on actual release data.For the purpose of implementation of Section 2.1, the alarm setpoint levels for low range effluent noble gas monitors are established to ensure that personnel are alerted when the noble gas releases are at a rate such that if the releases would continue for the year they would approach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose in Section 3.1.The equations in Section 3.1 of this manual provide the methodology for calculating the gaseous effluent dose rate.The evaluation of doses due to releases of radioactive material can be simplified by the use of equivalent dose factors as defined in Section 2.1.2. 1.The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is being used for the dose equivalent value.12 ODCM Rev. 20 2.1.2.1 Equivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows: Keq = Ej[(Ki)(fi)]
Where:
(2-1)Where: Keq = the equivalent whole body dose factor weighted by historical radionuclide distribution in releases in mremlyr per g+/-Ci/m 3.Ki = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per g Ci/m 3 from Table 3-3.fi = the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.The equivalent skin dose factor is calculated as follows: (L + l.lM)eq = Ei[(Li + 1-.Mi)(fi)]
Monitor Setpoint       = the setpoint for the monitor, in tCi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
(2-2)Where: (L+1.lM)eq
QUNIT         = unit release rate limit, in tCilsec, as determined in Section 2.1.2.3.
= the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases in mrem/yr per gCi/m 3.Li = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per gCi/m 3 from Table 3-3.Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per g+/-Ci/m 3 from Table 3-3.fi = the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.1.1 = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.13 ODCM Rev. 20 2.1.2.2 Site Release Rate Limit (QsrrF)The release rates corresponding to 80% of the whole body (QWB) and skin (QSK) dose rate limits are calculated using the equivalent dose factors defined in Section 2.1.2.1.The site release rate limit (QSffE) is the lower Of QWB or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded.The QSrrE is established as follows: QSITEWB (DWB)(08)
Flow Rate     = flow rate, in cfm at STP at which the tank will be released.
(2-3)(Keq)(X/Q)SITE Where: QSrrE,WB = the site release rate, in jiCi/sec, that would deliver a dose rate 80% of the whole body dose rate limit, DWB.DWB = whole body dose rate limit of 500 mrem/yr.Keq = equivalent whole body dose factor, in mrem/yr per pCi/M 3 weighted by the historical radionuclide distribution.(X/Q)SrrE
PF             = the current process flow of the plant vent in CFM.
= 8.91E-06, the highest calculated annual average dispersion parameter, in sec/M 3 , at the Site Boundary for any of the 3 units, from Table 3-2.0.8 = administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.QSIT = SK (DSK)(O.8) (24)QsIE~s =(L + 1-IM)eq(X/Q)SITE(2)
H             = the current plant vent monitor concentration in pCi/cc.
Where: QSrrE,SK = the site release rate limit, in pCi/sec, that would deliver a dose rate 80% of the skin dose rate limit, DSK.DSK = skin dose rate limit of 3000 mrem/yr.(L+ l. lM),q = equivalent skin dose factor, in mrem/yr per glCi/m 3 , weighted by the radionuclide distribution.
a             = fraction of QUNri       allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.
(/Q)SrrE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/n 3 , at the Site Boundary for any of the three units, from Table 3-2.0.8 = administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.After determination of the QSrE whole body and skin dose rates (equations 2-3 and 2-4, respectively), the most conservative result will be used as QsITE, the site release rate limit.14 ODCM Rev. 20 2.1.23 Unit Release Rate Limits (QuNrr)Typically QSrrE will be divided equally among operating units. If operational history dictates a larger fraction of the QsrrE be assigned to a specific unit then a weighted average of each unit's contribution to the QSrrE will be utilized to determine the QUNrr.QUNIT = (uNrr) (QSiTE) (2-5)Where: QUNIT = unit release rate limit, in pCi/sec.fUNIT = the fraction ( 1) of noble gas historically released from a specific operating unit to the total of all noble gas released from the site.QsrrE = the site release rate limit, in gCi/sec determined in Section 2.1.2.2.2.1.2.4 Setpoint Determination To comply with the requirements in Section 2.1, the alarm/trip setpoints can now be established using the unit release rate limit (QUNrT) to ensure that the noble gas releases do not exceed the dose rate limits.To allow for multiple sources of releases from different or common release points, the effluent monitor setpoint includes an administrative factor which allocates a percentage of the unit release rate limit to each of the release sources. Monitor setpoints will also be adjusted in accordance with Nuclear Administrative and Technical Manual procedures to account for monitor-specific characteristics.
0.9           = an administrative value to account for potential increases in activity from other contributors to the same release point.
Monitors RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-143 and RU-145 is calculated as follows: Monitor (QUNIT)(a)
472           = conversion factor, cubic centimeter/second per cubic feettminute.
Setpoint (472)(Flow Rate) (2-6)Where: Monitor Setpoint = the setpoint for the effluent monitor, in pCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.QUNIT = unit release rate limit, in pCi/sec, as determined in Section 2.1.2.3.Flow Rate = the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration.
If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms, and yet assure an alarm should an inadvertent release occur.
472 = conversion factor, cubic centimeter/second per cubic feet/minute.
2.1.2.5 Monitor Calibration The Radiation Level Conversion Factor (RLF) for each monitor is entered into the Radiation Monitoring System Database and may change whenever the monitor is calibrated. Calibration is performed in accordance with Nuclear Administrative and Technical Manual procedures.
a = fraction of QUNPr allocated for a specific release point. The sum of these administrative values shall be less than or equal to one.15 ODCM Rev. 20 Monitor RU- 2 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows: Monitor < [(QUNIT)(a)(O.
16                                       ODCM Rev. 20
: 9) -(H)(PF)(472)]  
(2-7)setpoint (Flow Rate)(472)
Where: Monitor Setpoint = the setpoint for the monitor, in tCi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.QUNIT = unit release rate limit, in tCilsec, as determined in Section 2.1.2.3.Flow Rate = flow rate, in cfm at STP at which the tank will be released.PF = the current process flow of the plant vent in CFM.H = the current plant vent monitor concentration in pCi/cc.a = fraction of QUNri allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.0.9 = an administrative value to account for potential increases in activity from other contributors to the same release point.472 = conversion factor, cubic centimeter/second per cubic feettminute.
If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms, and yet assure an alarm should an inadvertent release occur.2.1.2.5 Monitor Calibration The Radiation Level Conversion Factor (RLF) for each monitor is entered into the Radiation Monitoring System Database and may change whenever the monitor is calibrated.
Calibration is performed in accordance with Nuclear Administrative and Technical Manual procedures.
16 ODCM Rev. 20  


===3.0 GASEOUS===
3.0   GASEOUS AND LIQUID EFFLUENT DOSE RATES
AND LIQUID EFFLUENT DOSE RATES 3.1 Requirements:
 
===3.1 Requirements===
Gaseous Effluents The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 6-4 and Figure 6-5) shall be limited to the following:
Gaseous Effluents The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 6-4 and Figure 6-5) shall be limited to the following:
: a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b. For 1-131 and 1-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.Applicability:
: a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
At all times.Action: With the dose rate(s) exceeding the above limits, immediately decrease the release rate to within the above limits(s).
: b. For 1-131 and 1-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
Applicability:   At all times.
Action:
With the dose rate(s) exceeding the above limits, immediately decrease the release rate to within the above limits(s).
3.1.1 Surveillance Requirements
: a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2.
: b. The dose rate due to I-131, I-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1.
17                                      ODCM Rev. 20


====3.1.1 Surveillance====
3.1.2 Implementation of the Requirements Noble Gases Noble gas activity monitor setpoints are established at release rates which permit corrective action to be taken before exceeding the 10 CFR 20 annual dose limits as described in Section 2.0. The requirements for sampling and analysis of continuous and batch effluent releases are given in Table 3-1. The methods for sampling and analysis of continuous and batch effluent releases are given in the Nuclear Administrative and Technical Manual procedures. The dose rate in unrestricted areas shall be determined using the following equations.
For whole body dose rate:
DWB = Y [(K,)(X/Q)SITE(Ql)]                                                          (3-1)
For skin dose rate:
DSK = Zj[(Lj + l.lMi)(X/Q)s1TE(Qi)]                                                  (3-2)
Where:
Ki            = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per iVCi/m 3 from Table 3-3.
Qi            = the release rate of radionuclide i, in CO/sec.
(X/Q)SrrE    = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3, for any of the three units, from Table 3-2.
DWB          = the annual whole body dose rate (mrem/yr.).
Li            = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per tCi/m3 from Table 3-3.
Mi            = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per VCi/m 3 from Table 3-3.
DSK          = the annual skin dose rate (mrem/yr).
1.1          = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.
18                                  ODCM Rev. 20


Requirements
1-131. 1-133. tritium and radionuclides in particulate form with half-lives greater than 8 days The methods for sampling and analysis of continuous and batch releases for I-131, I-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, are given in the applicable Nuclear Administrative and Technical Manual procedures. Additional monthly and quarterly analyses shall be performed in accordance with Table 3-1. The total organ dose rate in unrestricted areas shall be determined by the following equation:
: a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2.b. The dose rate due to I-131, I-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1.17 ODCM Rev. 20  
Do = Ei[(PI)(X/Q)SITE(Qi)                                                                (3-3)
Where:
Pi            = the dose factor, in mrem/yr per ,pCi/m3, for radionuclide i, for the inhalation pathway, from Table 3-4.
(X/Q)SrrE      = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3 , at the Site Boundary, for any of the three units, Qi            = the release rate of radionuclide i, in .tCi/sec Do            = the total organ dose rate (mrem/yr).
19                                  ODCM Rev. 20


====3.1.2 Implementation====
TABLE 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM                            LOWER LIMIT SAMPLING      ANALYSIS            TYPE OF        OF DETECTION GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS                      (LLD) (IpCVdm)'
A. Waste Gas Storage        P              P            Principal Gamma            1.0E-04 Each Tank Grab Each Tank    Emitters9 Sample B. Containment Purge        P              P            Principal Gamma            1.OE-04 Each Purgebc  Each Purgebsc Emitters Grab Sample                  H-3 H-3              1.OE-06 C. 1. DELETED                Mb,e          Mb            Principal Gamma            1.OE-04
: 2. Plant Vent            Grab Sample                  Emittersg
: 3. Fuel Bldg. Exhaust                                  H-3                        1OE-06 Continuousf    4/Md          I-131                      1.OE-12 Charcoal Sample        I-133                      L.OE-10 continuousf    4/Md          Principal Gamma            .OE- II Particulate  Emittersg Sample        (I-13 1, Others)
Continuousf    M            Gross Alpha                1.OE- I1 Composite Particulate Sample Continuousf    Q            Sr-89, Sr-90              1.OE-l 1 Composite Particulate Sample D. All Radwaste Teypes as    Continuousf    Noble Gas    Noble Gases Gross Beta    1.OE-06 listed in A., B., and C.,                Monitor      or Gamma above.
20                              ODCM Rev. 20


of the Requirements Noble Gases Noble gas activity monitor setpoints are established at release rates which permit corrective action to be taken before exceeding the 10 CFR 20 annual dose limits as described in Section 2.0. The requirements for sampling and analysis of continuous and batch effluent releases are given in Table 3-1. The methods for sampling and analysis of continuous and batch effluent releases are given in the Nuclear Administrative and Technical Manual procedures.
Table 3-1 (Continued)
The dose rate in unrestricted areas shall be determined using the following equations.
TABLE NOTATION a The LLD is 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 whole body dose rate: DWB = Y [(K,)(X/Q)SITE(Ql)]
For a particular measurement system (which may include radiochemical separation):
(3-1)For skin dose rate: DSK = Zj[(Lj + l.lMi)(X/Q)s1TE(Qi)]
LD =               4.66 sb LL     =E
(3-2)Where: Ki = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per iVCi/m 3 from Table 3-3.Qi = the release rate of radionuclide i, in CO/sec.(X/Q)SrrE
= 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3 , for any of the three units, from Table 3-2.DWB = the annual whole body dose rate (mrem/yr.).
Li = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per tCi/m 3 from Table 3-3.Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per VCi/m 3 from Table 3-3.DSK = the annual skin dose rate (mrem/yr).
1.1 = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.18 ODCM Rev. 20 1-131. 1-133. tritium and radionuclides in particulate form with half-lives greater than 8 days The methods for sampling and analysis of continuous and batch releases for I-131, I-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, are given in the applicable Nuclear Administrative and Technical Manual procedures.
Additional monthly and quarterly analyses shall be performed in accordance with Table 3-1. The total organ dose rate in unrestricted areas shall be determined by the following equation: Do = Ei[(PI)(X/Q)SITE(Qi)
(3-3)Where: Pi = the dose factor, in mrem/yr per ,pCi/m 3 , for radionuclide i, for the inhalation pathway, from Table 3-4.(X/Q)SrrE
= 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3 , at the Site Boundary, for any of the three units, Qi = the release rate of radionuclide i, in .tCi/sec Do = the total organ dose rate (mrem/yr).
19 ODCM Rev. 20 TABLE 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT SAMPLING ANALYSIS TYPE OF OF DETECTION GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (LLD) (IpCVdm)'A. Waste Gas Storage P P Principal Gamma 1.0E-04 Each Tank Grab Each Tank Emitters9 Sample B. Containment Purge P P Principal Gamma 1.OE-04 Each Purgebc Each Purgebsc Emitters Grab Sample H-3 H-3 1.OE-06 C. 1. DELETED Mb,e Mb Principal Gamma 1.OE-04 2. Plant Vent Grab Sample Emittersg 3. Fuel Bldg. Exhaust H-3 1OE-06 Continuousf 4/Md I-131 1.OE-12 Charcoal Sample I-133 L.OE-10 continuousf 4/Md Principal Gamma .OE- II Particulate Emittersg Sample (I-13 1, Others)Continuousf M Gross Alpha 1.OE- I1 Composite Particulate Sample Continuousf Q Sr-89, Sr-90 1.OE-l 1 Composite Particulate Sample D. All Radwaste Teypes as Continuousf listed in A., B., and C., above.Noble Gas Noble Gases Gross Beta Monitor or Gamma 1.OE-06 20 ODCM Rev. 20 Table 3-1 (Continued)
TABLE NOTATION a The LLD is 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):
LD = 4.66 sb LL =E
* V
* V
* 2.22E6
* 2.22E6
* Y
* Y
* exp(-XAt)Where: LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume). Current literature defines the LLD as the detection capability for the instrumentation only and the MDC minimum detectable concentration, as the detection capability for a given instrument, procedure and type of sample.Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22E6 is the number of transformations per minute per microcurie, Y is the fractional radiocheniical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between the midpoint of sample collection and time of counting (for plant effluents, not environmental samples).The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
* exp(-XAt)
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and At should be used in the calculation.
Where:
LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume). Current literature defines the LLD as the detection capability for the instrumentation only and the MDC minimum detectable concentration, as the detection capability for a given instrument, procedure and type of sample.
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22E6 is the number of transformations per minute per microcurie, Y is the fractional radiocheniical yield (when applicable),
X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between the midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples. 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.
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.
21 ODCM Rev. 20 Table 3-1 (Continued)
21                                     ODCM Rev. 20
TABLE NOTATION b Analyses shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1-hour period if 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3;and 2) the noble gas activity monitor on the plant vent shows that effluent activity has increased by more than a factor of 3. If the associated noble gas vent monitor is inoperable, samples must be obtained as soon as possible.
 
Analyses shall be performed within a four-hour period. This requirement does not apply to the Fuel Building Exhaust.c Sampling and analyses shall also be performed at least once per 31 days when purging time exceeds 30 days continuous.
Table 3-1 (Continued)
d Samples shall be changed at least 4 times a month and analyses shall be completed within 48 hours after changing (or after removal from sampler).
TABLE NOTATION b Analyses shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1-hour period if 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3; and 2) the noble gas activity monitor on the plant vent shows that effluent activity has increased by more than a factor of 3. If the associated noble gas vent monitor is inoperable, samples must be obtained as soon as possible. Analyses shall be performed within a four-hour period. This requirement does not apply to the Fuel Building Exhaust.
When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10.e Tritium grab samples shall be taken at least monthly from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.f 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 Requirements 3.1, 4.1 and 4.2 of the ODCM.g The principal gamma emitters for which the LLD specification applies include the following radionuclides:
c Sampling and analyses shall also be performed at least once per 31 days when purging time exceeds 30 days continuous.
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
d Samples shall be changed at least 4 times a month and analyses shall be completed within 48 hours after changing (or after removal from sampler). When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10.
This list does not mean that only these nuclides are to be detected and reported.
e Tritium grab samples shall be taken at least monthly from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported in the Annual Radioactive Effluent Release Report.22 ODCM Rev. 20 TABLE 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW DISTANCE (METERS)1037 1057 2206 1967 1927 1967 2049 2730 3006 2258 1487 1251 1225 1244 1254 1069 UNIT 1 XIQ (SEC/m 3)4.93E-06 4.14E-06 2.84E-06 2.51E-06 2.56E-06 2.61E-06 3.56E-06 3.80E-06 5.07E-06 6.52E-06 7.47E-06 4.52E-06 4.73E-06 3.76E-06 3.43E-06 3.70E-06 D/Q (mw 2)9.24E-09 1.19E-08 6.84E-09 4.43E-09 3.24E-09 2.46E-09 2.36E-09 1.58E-09 1.78E-09 3.20E-09 5.65E-09 5.93E-09 9.49E-09 6.76E-09 5.87E-09 7.26E-09 UNIT 2 DISTANCE (METERS)1318 1342 2545 2206 2163 2067 2101 3026 2699 1836 1208 1014 993 1010 1191 1342 X/Q (SEC/m3)3.85E-06 3.18E-06 2.42E-06 2.22E-06 2.27E-06 2.32E-06 3.47E-06 3.43E-06 5.16E-06 7.90E-06 7.72E-06 5.55E-06 5.86E-06 4.67E-06 3.62E-06 2.85E-06 UNIT 3 D/Q DISTANCE (mr2) (METERS)6.17E-09 7.93E-09 5.34E-09 3.64E-09 2.66E-09 2.11E-09 2.26E-09 1.32E-09 1.97E-09 4.56E-09 6.88E-09 8.44E-09 1.34E-08 9.60E-09 6.40E-09 4.87E-09 1661 1693 2756 2337 2290 2023 2256 2786 2346 1607 1057 889 871 885 1045 1561 XIQ (SEC/m3)3.54E-06 2.86E-06 2.21E-06 2.08E-06 2.14E-06 2.37E-06 3.24E-06 3.72E-06 5.90E-06 8.91E-06 8.68E-06 5.34E-06 6.72E-06 5.37E-06 4.17E-06 2.93E-06 D/Q (m 2)4.86E-09 6.23E-09 4.65E-09 3.30E-09 2.41E-09 2.10E-09 2.00E-09 1.52E-09 2.51E-09 5.73E-09 8.61E-09 8.83E-09 1.67E-08 1. 19E-08 7.98E-09 4.58E-09 0 0
f 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 Requirements 3.1, 4.1 and 4.2 of the ODCM.
g 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 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported in the Annual Radioactive Effluent Release Report.
22                                       ODCM Rev. 20
 
TABLE 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY UNIT 1                    UNIT 2                                      UNIT 3 DISTANCE            XIQ        D/Q        DISTANCE            X/Q          D/Q      DISTANCE          XIQ            D/Q DIRECTION (METERS)           (SEC/m3 )    (mw2 )      (METERS)        (SEC/m3)        (mr2)      (METERS)      (SEC/m3)          (m 2)
N        1037          4.93E-06   9.24E-09          1318          3.85E-06     6.17E-09        1661        3.54E-06       4.86E-09 NNE        1057          4.14E-06   1.19E-08          1342          3.18E-06     7.93E-09        1693        2.86E-06       6.23E-09 NE        2206          2.84E-06   6.84E-09        2545          2.42E-06     5.34E-09        2756        2.21E-06       4.65E-09 ENE        1967          2.51E-06  4.43E-09         2206          2.22E-06    3.64E-09       2337        2.08E-06      3.30E-09 E        1927          2.56E-06  3.24E-09         2163          2.27E-06    2.66E-09       2290        2.14E-06      2.41E-09 ESE        1967          2.61E-06  2.46E-09         2067          2.32E-06     2.11E-09        2023        2.37E-06       2.10E-09 SE        2049          3.56E-06   2.36E-09        2101          3.47E-06     2.26E-09        2256        3.24E-06       2.00E-09 SSE        2730          3.80E-06   1.58E-09          3026          3.43E-06     1.32E-09        2786        3.72E-06       1.52E-09 S        3006          5.07E-06  1.78E-09         2699          5.16E-06    1.97E-09       2346        5.90E-06      2.51E-09 SSW        2258          6.52E-06  3.20E-09         1836          7.90E-06    4.56E-09         1607        8.91E-06      5.73E-09 SW          1487        7.47E-06  5.65E-09         1208          7.72E-06    6.88E-09         1057       8.68E-06       8.61E-09 WSW          1251        4.52E-06   5.93E-09          1014          5.55E-06     8.44E-09          889        5.34E-06       8.83E-09 W          1225        4.73E-06   9.49E-09          993          5.86E-06     1.34E-08          871        6.72E-06       1.67E-08 WNW          1244        3.76E-06   6.76E-09          1010          4.67E-06    9.60E-09         885        5.37E-06        1.19E-08 NW          1254        3.43E-06  5.87E-09         1191          3.62E-06    6.40E-09         1045        4.17E-06      7.98E-09 NNW          1069        3.70E-06  7.26E-09         1342          2.85E-06    4.87E-09        1561        2.93E-06      4.58E-09 0


==Reference:==
==Reference:==
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.
0


Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.
TABLE 3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Whole Body           Skin    Gamma Air Dose Factor      Dose Factor Dose Factor Beta Air Dose Ki              Li         Mi      Factor Ni mrernm 3        mrem-m3     mrad-m3      mrad-m3 Radionuclide              yr-jiCi         yr-pCi      yr-pCi      yr-I+/-Ci Kr-83m                  7.56E-02                   1.93E+01    2.88E+02 Kr-85m                  1.17E+03       1.46E+03    1.23E+03    1.97E+03 Kr-85                  1.61E+01       1.34E+03   1.72E+01    1.95E+03 Kr-87                  5.92E+03       9.73E+03   6.17E+03     1.03E+04 Kr-88                  1.47E+04        2.37E+03   1.52E+04     2.93E+03 Kr-89                  1.66E+04        1.01E3+04  1.73E+04    1.06E+04 Kr-90                  1.56E+04        7.29E+03   1.63E+04     7.83E+03 Xe-131m                9.15E+01        4.76E+02    1.56E+02    1.1 lE+03 Xe-133m                2.5 1E+02      9.94E+02    3.27E+02    1.48E+03 Xe-133                  2.94E+02       3.06E+02   3.53E+02     1.05E+03 Xe-135m                3.12E+03       7.1 lE+02  3.36E+03     7.39E+02 Xe-135                  1.81E+03       1.86E+03   1.92E+03     2.46E+03 Xe-137                  1.42E+03       1.22E+04   1.5 1E+03   1.27E+04 Xe-138                  8.83E+03       4.13E+03   9.21E+03     4.75E+03 Ar-41                  8.84E+03        2.69E+03   9.30E+03     3.28E+03
TABLE 3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Whole Body Dose Factor Ki Skin Dose Factor Li mrem-m3 yr-pCi mrernm 3 yr-jiCi Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.5 1E+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 1.01E3+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.1 lE+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 Gamma Air Dose Factor Mi mrad-m 3 yr-pCi 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 1.5 1E+03 9.21E+03 9.30E+03 Beta Air Dose Factor Ni mrad-m 3 yr-I+/-Ci 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.1 lE+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03  


==Reference:==
==Reference:==
Regulatory Guide 1.109, Table B-I.
24                              ODCM Rev. 20


Regulatory Guide 1.109, Table B-I.24 ODCM Rev. 20 TABLE 3-4 Pi VALUES FOR THE INHALATION PATHWAY (mremlyr/pCCVm 3)NUCLIDE Age Group Organ Pi H-3 TEEN LIVER 1.27E+03 CR-51 TEEN LUNG 2.10E+04 MN-54 TEEN LUNG 1.98E+06 FE-59 TEEN LUNG 1.53E+06 CO-58 TEEN LUNG 1.34E+06 CO-60 TEEN LUNG 8.72E+06 ZN-65 TEEN LUNG 1.24E+06 SR-89 TEEN LUNG 2.42E+06 SR-90 TEEN BONE 1.08E+08 ZR-95 TEEN LUNG 2.69E+06 SB-124 TEEN LUNG 3.85E+06 1-131 CHILD THYROID 1.62E+07 I-133 CHILD THYROID 3.85E+06 CS-134 TEEN LIVER 1.13E+06 CS-137 CHILD BONE 9.07E+05 BA- 140 TEEN LUNG 2.03E+06 CE-141 TEEN LUNG 6.14E+05 CE-144 TEEN LUNG 1.34E+07 25 ODCM Rev. 20  
TABLE 3-4 Pi VALUES FOR THE INHALATION PATHWAY (mremlyr/pCCVm3 )
NUCLIDE       Age Group       Organ       Pi H-3           TEEN           LIVER   1.27E+03 CR-51           TEEN           LUNG   2.10E+04 MN-54           TEEN           LUNG   1.98E+06 FE-59         TEEN           LUNG   1.53E+06 CO-58           TEEN           LUNG   1.34E+06 CO-60           TEEN           LUNG   8.72E+06 ZN-65           TEEN           LUNG   1.24E+06 SR-89         TEEN           LUNG   2.42E+06 SR-90         TEEN           BONE   1.08E+08 ZR-95           TEEN           LUNG   2.69E+06 SB-124         TEEN           LUNG   3.85E+06 1-131         CHILD         THYROID 1.62E+07 I-133         CHILD         THYROID 3.85E+06 CS-134         TEEN           LIVER   1.13E+06 CS-137         CHILD           BONE   9.07E+05 BA- 140         TEEN           LUNG   2.03E+06 CE-141         TEEN           LUNG   6.14E+05 CE-144         TEEN           LUNG   1.34E+07 25                   ODCM Rev. 20


===3.2 Requirements===
===3.2 Requirements===
Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System - Concentration The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:
5.OE-07 pCi/ml for the principal gamma emitters (except Ce-144) 3.OE-06 piCi/ml for Ce-144 1.OE-06 piCi/ml for I-131 L.OE-03 piCi/ml for H-3 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to:
2.0E-06 ipCi/ml for Cs-134 2.0E-06 pCi/ml for Cs-137 The concentrations specified in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, for all other isotopes Applicability:    At all times.
Action:
When any secondary system liquid waste discharge pathway concentration determined in accordance with the surveillance requirements given below exceeds the above Requirements, divert that discharge pathway to the liquid radwaste system without delay or terminate the discharge.
3.2.1 Surveillance Requirements
: a. Secondary system liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 3-5.
3.2.2 Implementation of the Requirements This requirement is implemented by Nuclear Administrative and Technical Manual procedures.
26                                    ODCM Rev. 20


Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System -Concentration The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to: 5.OE-07 pCi/ml for the principal gamma emitters (except Ce-144)3.OE-06 piCi/ml for Ce-144 1.OE-06 piCi/ml for I-131 L.OE-03 piCi/ml for H-3 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to: 2.0E-06 ipCi/ml for Cs-134 2.0E-06 pCi/ml for Cs-137 The concentrations specified in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, for all other isotopes Applicability:
TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release                          Sampling &                    Type Of            (LLD)*
At all times.Action: When any secondary system liquid waste discharge pathway concentration determined in accordance with the surveillance requirements given below exceeds the above Requirements, divert that discharge pathway to the liquid radwaste system without delay or terminate the discharge.
Pathway                    Destination  Analysis Frequency Notes      Activity Analysis    (11Ciml)
: 1. Chemical Waste Neutralizer    retention basin    P  Each Batch            Principal Gamma Emittersc  5.OE-07 Tank (CWNT)b                  liquid radwaste        N. A.                1-131                      1.OE-06 H-3                        1.01E-05
: 2. Steam Generator Blowdown      circ. water         P  Each Batch      1    Principal Gamma Emittersc  5.0E-07 Low TDS Sumpb                CWNT                  N. A.                1-131                      1.0E-06 H-3                        1.0E-05
: 3. Condensate
: a. Condensate Polishing Low  circ. water        P  Each Batch      3    Principal Gamma Emittersc  5.OE-07 TDS Sumpb                  CWNT                  N. A.                1-131                       1.0E-06 H-3                         1.0E-05 N%)
: b. Initial Backwash          (low TDS sump) to   P  Each Discharge        Principal Gamma Emittersc  5.0E-07 circ. water                                  1-131                        1.0E-06 (low TDS sump) to     N. A.                H-3                          I.0E-05 CWNT
: c. Pre-service rinse effluent  retention basin    P  Each Discharge 2     Principal Gamma Emintersc  5.0E-07 through SC-N-V069                            -131                        1.OE-06 condenser through    N. A.                H-3                          1.0E-05 SC-N-UV232
: d. Overboard condensate        circ water through P  Each Discharge        Principal Gamma Emittersc    5.OE-07 CD-N-V194                                  1-131                        1.0E-06 retention basin    P  Each Discharge 2     H-3                          1.0E-05 through SC-N-V079
: 4. Turbine Building Sump'        retention basin    D Grab Sample    3    Principal Gamma Emittersc    5.OE-07 0
CWNT                  N. A.                1-131                        1.OE-06 H-3                          1.0E-05
;0 0


====3.2.1 Surveillance====
TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release                                Sampling &                        Type Of                  (LLD)"
Pathway                        Destination    Analysis Frequency Notes          Activity Analysis          (RCi/ml)
: 5. North & South Condenser Area retention basin              D Grab Sample      3        Principal Gamma Emittersc        5.OE-07 Sumpsd                            CWNT                    N. A.                    I-131                            1.OE-06 H-3                              1.OE-05
: 6. Steam Generator Blowdown to        retention basin      P  Each Discharge 2         Principal Gamma Emitters'        5.OE-07 Retention Basin                    through SC-N-V064                                1-131                            1.OE-06 H-3                              1.OE-05
: 7. Retention Basin to Evaporation    evaporation pond    P  Each Batch                Principal Gamma Emitters'        5.OE-07 Pond                                                                                1-131                            1.OE-06 H-3                              1.OE-05 00 1 Sampling and analysis are required only when concentration for chemical waste neutralizer tank or steam generator activity exceeds the requirement 2 RU-200 shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3-6. The Alarm/Trip setpoints for RU-200 are set to ensure that the concentrations in the retention basins do not exceed the Requirement 3 Sampling and analysis are required only when concentration for chemical waste neutralizer tank or condensate activity exceeds the requirement 0
0


Requirements
Table 3-5 (Continued)
: a. Secondary system liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 3-5.3.2.2 Implementation of the Requirements This requirement is implemented by Nuclear Administrative and Technical Manual procedures.
TABLE NOTATION a The LLD is defined 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.
26 ODCM Rev. 20 TABLE 3-5 N%)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling & Type Of (LLD)*Pathway Destination Analysis Frequency Notes Activity Analysis (11Ciml)1. Chemical Waste Neutralizer retention basin P Each Batch Principal Gamma Emittersc 5.OE-07 Tank (CWNT)b liquid radwaste N. A. 1-131 1.OE-06 H-3 1.01E-05 2. Steam Generator Blowdown circ. water P Each Batch 1 Principal Gamma Emittersc 5.0E-07 Low TDS Sumpb CWNT N. A. 1-131 1.0E-06 H-3 1.0E-05 3. Condensate
For a particular measurement system which may include radiochemical separation:
: a. Condensate Polishing Low circ. water P Each Batch 3 Principal Gamma Emittersc 5.OE-07 TDS Sumpb CWNT N. A. 1-131 1.0E-06 H-3 1.0E-05 b. Initial Backwash (low TDS sump) to P Each Discharge Principal Gamma Emittersc 5.0E-07 circ. water 1-131 1.0E-06 (low TDS sump) to N. A. H-3 I.0E-05 CWNT c. Pre-service rinse effluent retention basin P Each Discharge 2 Principal Gamma Emintersc 5.0E-07 through SC-N-V069
-131 1.OE-06 condenser through N. A. H-3 1.0E-05 SC-N-UV232
: d. Overboard condensate circ water through P Each Discharge Principal Gamma Emittersc 5.OE-07 CD-N-V194 1-131 1.0E-06 retention basin P Each Discharge 2 H-3 1.0E-05 through SC-N-V079 4. Turbine Building Sump' retention basin D Grab Sample 3 Principal Gamma Emittersc 5.OE-07 CWNT N. A. 1-131 1.OE-06 H-3 1.0E-05 0;0 0 TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling & Type Of (LLD)" Pathway Destination Analysis Frequency Notes Activity Analysis (RCi/ml)5. North & South Condenser Area retention basin D Grab Sample 3 Principal Gamma Emittersc 5.OE-07 Sumpsd CWNT N. A. I-131 1.OE-06 H-3 1.OE-05 6. Steam Generator Blowdown to retention basin P Each Discharge 2 Principal Gamma Emitters' 5.OE-07 Retention Basin through SC-N-V064 1-131 1.OE-06 H-3 1.OE-05 7. Retention Basin to Evaporation evaporation pond P Each Batch Principal Gamma Emitters' 5.OE-07 Pond 1-131 1.OE-06 H-3 1.OE-05 1 Sampling and analysis are required only when concentration for chemical waste neutralizer tank or steam generator activity exceeds the requirement 2 RU-200 shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3-6. The Alarm/Trip setpoints for RU-200 are set to ensure that the concentrations in the retention basins do not exceed the Requirement 3 Sampling and analysis are required only when concentration for chemical waste neutralizer tank or condensate activity exceeds the requirement 00 0 0 Table 3-5 (Continued)
TABLE NOTATION a The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system which may include radiochemical separation:
4.66 Sb LLD = E
4.66 Sb LLD = E
* V
* V
* 2.22E6
* 2.22E6
* Y
* Y
* exp(-XAt)Where: LLD is the "a priori" lower limit of detection as defined above as microcuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate as counts per minute, E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield when applicable, X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.TIypical values of E, V, Y, and At should be used in the calculation.
* exp(-XAt)
Where:
LLD is the "a priori" lower limit of detection as defined above as microcuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate as counts per minute, E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield when applicable, X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.
TIypical 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 posterori (after the fact) limit for a particular measurement.
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 posterori (after the fact) limit for a particular measurement.
b 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 to assure representative sampling.c The principal gamma emitters for which the LLD specification applies include the following radionuclides:
b   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 to assure representative sampling.
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 3.OE-06. This list does not mean that only these nuclides are to be considered.
c   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. Ce-144 shall also be measured, but with an LLD of 3.OE-06. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.d 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 29 ODCM Rev. 20 TABLE 3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Channel Mode in which Channel Source Channel Functional Surveillance is Instrument Check Check Calibration Test Required RU-200 P N. A. R Q See Table 3-7 TABLE 3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Mode In which Surveillance Secondary System Liquid Release Pathway is Required Action if RU-200 Is inoperable Obtain grab sample at least once per 12 hours and analyze in accordance Pre-service rinse to retention basins At All Times with section 3.2 Obtain grab sample at least once per 12 hours and analyses in accordance Condensate overboard to retention basins 1-4 with section 3.2 Modes 1-4: Suspend the release Steam Generator Blowdown/Drain to retention At All Times Modes 5,6 & defueled:
d 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 29                                     ODCM Rev. 20
Obtain grab basins sample at least once per 12 hours and analyze in accordance with sec-tion 3.2 30 ODCM Rev. 20  


===4.0 GASEOUS===
TABLE 3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Channel      Mode in which Channel          Source      Channel      Functional      Surveillance is Instrument        Check            Check      Calibration      Test            Required RU-200              P            N. A.          R            Q            See Table 3-7 TABLE 3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Mode In which Surveillance Secondary System Liquid Release Pathway          is Required      Action if RU-200 Is inoperable Obtain grab sample at least once per 12 hours and analyze in accordance Pre-service rinse to retention basins        At All Times    with section 3.2 Obtain grab sample at least once per 12 hours and analyses in accordance Condensate overboard to retention basins            1-4      with section 3.2 Modes 1-4: Suspend the release Steam Generator Blowdown/Drain to retention      At All Times    Modes 5,6 & defueled: Obtain grab basins                                        sample at least once per 12 hours and analyze in accordance with sec-tion 3.2 30                                      ODCM Rev. 20
& LIQUID EFFLUENTS  
 
-DOSE 4.1 Requirements:
4.0 GASEOUS & LIQUID EFFLUENTS - DOSE
 
===4.1 Requirements===
Noble Gases The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITM BOUNDARY (see Figure 6-4 and Figure 6-5) shall be limited to the following:
Noble Gases The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITM BOUNDARY (see Figure 6-4 and Figure 6-5) 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.
: 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,
Applicability:
: 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.
At all times.Action: With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.4.1.1 Surveillance Requirements
Applicability:   At all times.
: a. Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology contained in Section 4.1.2 at least once per 31 days.31 ODCM Rev. 20  
Action:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
4.1.1 Surveillance Requirements
: a. Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology contained in Section 4.1.2 at least once per 31 days.
31                                       ODCM Rev. 20


====4.1.2 Implementation====
4.1.2 Implementation of the Requirement: Noble Gas The air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from each unit during any specified time period shall be determined by the following equations:
 
of the Requirement:
Noble Gas The air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from each unit during any specified time period shall be determined by the following equations:
For gamma radiation:
For gamma radiation:
D yu = (3.17E-08)
D yu         = (3.17E-08) Fj[(M 1) (Q).UN(Q,)]                                             (4-1)
Fj[(M 1) (Q).UN(Q,)]  
For beta radiation:
(4-1)For beta radiation:
D A.         = (3.17E-08) Hi [(N1) (XIQ)Ur<Qi)]                                           (4-2)
D A. = (3.17E-08)
Where:
Hi [(N 1) (XIQ)Ur<Qi)]  
Mi           = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per iVCitm 3 from Table 3-3.
(4-2)Where: Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per iVCitm 3 from Table 3-3.Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per pCi/M 3 from Table 3-3.(X/Q)uNI = the highest calculated annual average dispersion parameter, in sec/m 3 , at the site boundary for the particular Unit, from Table 3-2. Optionally, the highest value may be used for any Unit calculation.
Ni           = the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per pCi/M3 from Table 3-3.
=7.47E-06 from Unit I=7.90E-06 from Unit 2=8.91E-06 from Unit 3 D yu = the total gamma air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.D Pu = the total beta air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.Qi = the integrated release, from the particular unit, in IiCi, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period.3.17E-08 = the inverse of seconds in a year (yr/sec).The cumulative gamma air dose and beta air dose for a quarterly or annual evaluation shall be based on the calculated dose contribution from each specified time period occurring during the reporting time period.32 ODCM Rev. 20  
3 (X/Q)uNI     = the highest calculated annual average dispersion parameter, in sec/m , at the site boundary for the particular Unit, from Table 3-2. Optionally, the highest value may be used for any Unit calculation.
                        =7.47E-06 from Unit I
                        =7.90E-06 from Unit 2
                        =8.91E-06 from Unit 3 D yu         = the total gamma air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.
D Pu         = the total beta air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.
Qi           = the integrated release, from the particular unit, in IiCi, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period.
3.17E-08     = the inverse of seconds in a year (yr/sec).
The cumulative gamma air dose and beta air dose for a quarterly or annual evaluation shall be based on the calculated dose contribution from each specified time period occurring during the reporting time period.
32                                         ODCM Rev. 20


===4.2 Requirement===
===4.2 Requirement===
Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-
: 5) shall be limited to the following:
: a. During any calendar quarter: Less than or equal to 7.5 inrems to any organ and,
: b. During any calendar year: Less than or equal to 15 mrems to any organ.
Applicability:    At all times.
Action:
With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit 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.
4.2.1 Surveillance Requirements
: a. Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters contained in Section 4.2.2 at least once per 31 days.
33                                        ODCM Rev. 20


Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-5) shall be limited to the following:
4.2.2 Implementation of the Requirement The organ dose to an individual from I-131, I-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:
: a. During any calendar quarter: Less than or equal to 7.5 inrems to any organ and, b. During any calendar year: Less than or equal to 15 mrems to any organ.Applicability:
Dou          = (3.17E-08) Zi      [k (Rik Wk) (Qi)]                                          (4-3)
At all times.Action: With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit 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.4.2.1 Surveillance Requirements
Where:
: a. Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters contained in Section 4.2.2 at least once per 31 days.33 ODCM Rev. 20  
Do.          = the total accumulated organ dose from gaseous effluents for a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.
Qi            = the quantity of radionuclide i, in gCi, released in gaseous effluents from a particular unit.
Rik          = the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mremlyr per pCi/m3 and for the food and ground plane pathways in m2 _ mrem/yr per piCi/sec, except H-3, which has units of mrem/yr per iVCi/m 3 ) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.
3.17E-08      = the inverse of seconds per year (yr/sec).
Wk            = the highest annual average dispersion or deposition parameter for the particular Unit, used for estimating the dose at the site boundary or to a MEMBER OF THE PUBLIC at the controlling location for the particular Unit. Optionally, the highest value may be used for any Unit calculation.
                    = (X/Q)UNrIP      in sec/M3 for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table 3-2.
                        =7.47E-06 from Unit I
                        =7.90E-06 from Unit 2
                        =8.91E-06 from Unit 3
                    =    (X/Q)UNrr, in sec/m3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17 or 4-18.
                        =2.92E-06 from Unit 1
                        =2.19E-06 from Unit 2
                        =2.31E-06 from Unit 3
                    = (D/Q)UNrr, in m-2 , for the food and ground plane pathways, for organ dose at the site boundary, from Table 3-2.
                        =1.19E-08 from Unit 1
                        =1.34E-08 from Unit 2
                        =1.67E-08 from Unit 3 34                                        ODCM Rev. 20


====4.2.2 Implementation====
              =   (D/Q)uNrD in m-2 , for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18.
                  =3.25E-09 from Unit I
                  =3.88E-10 from Unit 2
                  =4.21E-10 from Unit 3 Residences, vegetable gardens and milk animals located within 5 miles of the site will be identified during the annual land use census. The controlling pathway and location will be identified and will be used for all MEMBER OF THE PUBLIC dose evaluations.
The R; values were calculated in accordance with the methodologies in NUREG-0133. The following site specific information was used to calculate R,:
Yalue The length of the grazing season for milk animals (Q.
Ref. ER-OL, Section 2.1.3.4.3                                                        0.75 The length of the grazing season for meat animals (f8).
Ref. ER-OL, Section 2.1.3.4.4                                                        0.25 The fraction of daily feed derived from pasture while on pasture for milk animals (fp).
Ref. ER-OL, Section 2.1.3.4.3                                                        0.35 The fraction of daily feed derived from pasture while on pasture for meat animals (fp).
Ref. ER-OL, Section 2.1.3.4.3                                                        0.05 The fraction of year vegetables are grown, (fl) approximation.
Ref. ER-OL, Section 2.1.3.4, Table 2.1-8.                                            0.667 The annual absolute humidity (g/m3 ), H, Ref. UFSAR, Table 2.3-16                                                            6 35                                  ODCM Rev. 20


of the Requirement The organ dose to an individual from I-131, I-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:
43 Requirements: Gaseous Radwaste Treatment The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figure 6-4 and Figure 6-5) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-5) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
Dou = (3.17E-08)
Applicability:     At all times:
Zi [k (Rik Wk) (Qi)] (4-3)Where: Do. = the total accumulated organ dose from gaseous effluents for a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.Qi = the quantity of radionuclide i, in gCi, released in gaseous effluents from a particular unit.Rik = the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mremlyr per pCi/m 3 and for the food and ground plane pathways in m 2 _ mrem/yr per piCi/sec, except H-3, which has units of mrem/yr per iVCi/m 3) at the controlling location.
Action:
The Rik's for each age group are given in Tables 4-1 through 4-15.3.17E-08 = the inverse of seconds per year (yr/sec).Wk = the highest annual average dispersion or deposition parameter for the particular Unit, used for estimating the dose at the site boundary or to a MEMBER OF THE PUBLIC at the controlling location for the particular Unit. Optionally, the highest value may be used for any Unit calculation.
With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a Special Report which includes the following information:
= (X/Q)UNrIP in sec/M 3 for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table 3-2.=7.47E-06 from Unit I=7.90E-06 from Unit 2=8.91E-06 from Unit 3= (X/Q)UNrr, in sec/m 3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17 or 4-18.=2.92E-06 from Unit 1=2.19E-06 from Unit 2=2.31E-06 from Unit 3= (D/Q)UNrr, in m-2 , for the food and ground plane pathways, for organ dose at the site boundary, from Table 3-2.=1.19E-08 from Unit 1=1.34E-08 from Unit 2=1.67E-08 from Unit 3 34 ODCM Rev. 20
: a. Identification of the inoperable equipment or subsystems and the reason for inoperability,
= (D/Q)uNrD in m-2 , for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18.=3.25E-09 from Unit I=3.88E-10 from Unit 2=4.21E-10 from Unit 3 Residences, vegetable gardens and milk animals located within 5 miles of the site will be identified during the annual land use census. The controlling pathway and location will be identified and will be used for all MEMBER OF THE PUBLIC dose evaluations.
: b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
The R; values were calculated in accordance with the methodologies in NUREG-0133.
: c. Summary description of action(s) taken to prevent a recurrence.
The following site specific information was used to calculate R,: Yalue The length of the grazing season for milk animals (Q.Ref. ER-OL, Section 2.1.3.4.3 0.75 The length of the grazing season for meat animals (f 8).Ref. ER-OL, Section 2.1.3.4.4 0.25 The fraction of daily feed derived from pasture while on pasture for milk animals (fp).Ref. ER-OL, Section 2.1.3.4.3 0.35 The fraction of daily feed derived from pasture while on pasture for meat animals (fp).Ref. ER-OL, Section 2.1.3.4.3 0.05 The fraction of year vegetables are grown, (fl) approximation.
Ref. ER-OL, Section 2.1.3.4, Table 2.1-8. 0.667 The annual absolute humidity (g/m 3), H, Ref. UFSAR, Table 2.3-16 6 35 ODCM Rev. 20 43 Requirements:
Gaseous Radwaste Treatment The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figure 6-4 and Figure 6-5) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-5) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.Applicability:
At all times: Action: With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a Special Report which includes the following information:
: a. Identification of the inoperable equipment or subsystems and the reason for inoperability, b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and c. Summary description of action(s) taken to prevent a recurrence.
43.1 Surveillance Requirements
43.1 Surveillance Requirements
: a. Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 4.3.2.36 ODCM Rev. 20 432 Implementation of the Requirement Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.
: a. Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 4.3.2.
Dose Projection  
36                                       ODCM Rev. 20
-Noble Gases The air dose, in mrads is determined using the methodology described in Section 4.1.2 of this manual. This information is used to determine an air dose projection for the next 31 days using the following equations:
 
432 Implementation of the Requirement Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.
Dose Projection - Noble Gases The air dose, in mrads is determined using the methodology described in Section 4.1.2 of this manual. This information is used to determine an air dose projection for the next 31 days using the following equations:
For gamma radiation:
For gamma radiation:
31 day y =
31 day y      = Dy+/- CDy                                                                  (4-4)
For beta radiation:
31 day        =  Do +/- CDP                                                                (4-5)
Where:
Dy            =  the total gamma air dose in


==References:==
==References:==
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
CD


1984 Land Use Census (letter ANPM-21221-JRM/LEB).
TABLE 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 X/Q       RESIDENCE(b)           D/Q           XIQ       GARDEN(h)       D/Q     XIQ   MILK(b)           D/7 DIRECTION         (Sec/r 3 )     Dist. Miles       (mr2 )       (Sec/m3 )     Dist Miles   (m- 2) (Sec/m 3) Dist. Miles       (m7 )
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
N         2.73E-06             1.5        2.92E-09      2.39E-06           1.7    2.35E-09 7.03E-07     (a)    3.48E-10 NNE          2.20E-06             1.5        3.87E-09      2.20E-06           1.5    3.87E-09 4.70E-07     (a)    4.04E-10 NE          1.85E-06           2.0         3.55E-09      1.57E-06          2.3   2.78E-09 5.77E-07      (a)     6.51E-10 ENE          1.03E-06            2.7          1.08E-09       1.03E-06          2.7    1.08E-09 3.86E-07      (a)    2.86E-10 E          8.80E-07            3.0          6.06E-10       3.71E-07          (a)    1.87E-10 3.71E-07      (a)    1.87E-10 ESE          6.25E-07            3.7          2.76E-10      3.96E-07          4.7    1.51E-10 3.96E-07     4.7    1.5 IE-10 goat SE        9.06E-07             4.0          2.72E-10      9.06E-07           4.0    2.72E-10 5.84E-07     (a)    1.52E-10 Ut        SSE          1.34E-06            4.5         2.811E-10      1.09E-06          (a)   2.15E-10 1.09E-06      (a)     2.15E-10 S        2.63E-06            4.5          5.01E-10       2.19E-06          5.0    3.88E-10 2.19E-06      5.0    3.88E-10 cow SSW          3.48E-06            3.2          9.19E-10       2.28E-06          (a)    4.53E-10 2.28E-06      (a)    4.53E-10 SW          2.93E-06            2.7         9.75E-10      1.58E-06          (a)    3.56E-10 1.58E-06      (a)    3.566E-10 WSW          2.01E-06           2.5          1.16E-09      8.55E-07         (a)    3.18E-10 8.55E-07     (a)    3.18E-10 W          7.54E-07             (a)         4.44E-10      7.54E-07          (a)   4.44E-10 7.54E-07      (a)     4.44E-10 WNW          6.03E-07            (a)         3.25E-10      6.03E-07          (a)   3.25E-10 6.03E-07      (a)     3.25E-10 NW          7.84E-07            4.0          4.88E-10       7.84E-07          4.0    4.88E-10 6.02E-07      (a)    3.27E-10 NNW          1.46E-06            2.0        1.47E-09      5.20E-07          5.0    3.04E-10 5.20E-07      (a)    3.04E-10 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.
CD TABLE 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 X/Q RESIDENCE(b)
0 (b) Controlling locations are discussed in Appendix A.
D/Q XIQ GARDEN(h)
0
D/Q XIQ MILK(b) D/7 DIRECTION (Sec/r 3) Dist. Miles (mr 2) (Sec/m 3) Dist Miles (m-2) (Sec/m 3) Dist. Miles (m7 )Ut N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 2.73E-06 2.20E-06 1.85E-06 1.03E-06 8.80E-07 6.25E-07 9.06E-07 1.34E-06 2.63E-06 3.48E-06 2.93E-06 2.01E-06 7.54E-07 6.03E-07 7.84E-07 1.46E-06 1.5 1.5 2.0 2.7 3.0 3.7 4.0 4.5 4.5 3.2 2.7 2.5 (a)(a)4.0 2.0 2.92E-09 3.87E-09 3.55E-09 1.08E-09 6.06E-10 2.76E-10 2.72E-10 2.811E-10 5.01E-10 9.19E-10 9.75E-10 1.16E-09 4.44E-10 3.25E-10 4.88E-10 1.47E-09 2.39E-06 2.20E-06 1.57E-06 1.03E-06 3.71E-07 3.96E-07 9.06E-07 1.09E-06 2.19E-06 2.28E-06 1.58E-06 8.55E-07 7.54E-07 6.03E-07 7.84E-07 5.20E-07 1.7 1.5 2.3 2.7 (a)4.7 4.0 (a)5.0 (a)(a)(a)(a)(a)4.0 5.0 2.35E-09 3.87E-09 2.78E-09 1.08E-09 1.87E-10 1.51E-10 2.72E-10 2.15E-10 3.88E-10 4.53E-10 3.56E-10 3.18E-10 4.44E-10 3.25E-10 4.88E-10 3.04E-10 7.03E-07 4.70E-07 5.77E-07 3.86E-07 3.71E-07 3.96E-07 5.84E-07 1.09E-06 2.19E-06 2.28E-06 1.58E-06 8.55E-07 7.54E-07 6.03E-07 6.02E-07 5.20E-07 (a)(a)(a)(a)(a)4.7 (a)(a)5.0 (a)(a)(a)(a)(a)(a)(a)3.48E-10 4.04E-10 6.51E-10 2.86E-10 1.87E-10 1.5 IE-10 goat 1.52E-10 2.15E-10 3.88E-10 cow 4.53E-10 3.566E-10 3.18E-10 4.44E-10 3.25E-10 3.27E-10 3.04E-10 0 0 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.(b) Controlling locations are discussed in Appendix A.


==References:==
==References:==
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.


1984 Land Use Census (letter ANPM-21221-JRM/LEB).
TABLE 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 X/Q       RESIDENCE(b)           D/Q           X/Q       GARDEN(b)       D/Q     X/Q   MILK(b)           D/Q DIRECTION         (Sec/r 3 )     Dist. Miles         (mr2 )     (Sec/m3 )     Dist. Miles   (m )   (Sec/m3 ) Dist. Miles     (rn 2 )
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
N           2.58E-06           1.8          2.47E-09      2.42E-06           1.9    2.22E-09 7.03E-07       (a)    3.48E-10 NNE          1.85E-06           1.7          2.97E-09      1.85E-06           1.7    2.97E-09 4.70E-07       (a)    4.04E-10 NE          1.66E-06           2.2         3.OOE-09      I1.48E-06        2.4     2.54E-09 5.77E-07      (a)   6.51E-10 ENE          8.75E-07            2.9          8.86E-10       8.75E-07          2.9    8.86E-10 3.86E-07      (a)    2.86E-10 E          8.90E-07            3.0          6.17E-10     4.06E-07          4.6    2.15E-10 4.25E-07      4.5    2.31E-10 goat ESE          6.37E-07            3.7          2.84E-10      5.80E-07         4.0    2.46E-10 3.73E-07      (a)    1.37E-10 SE          5.84E-07           (a)          1.52E-10      5.84E-07           (a)    1.52E-10 5.84E-07       (a)    1.52E-10 LA ON SSE          1.36E-06            4.4         2.88E-10      I1.09E-06          (a)   2.15E-10 1.09E-06      (a)   2.151E-10 S          2.65E-06            4.2         5.25E-10       2.25E-06          4.9    4.06E-10 2.3 1E-06      4.8    4.21E-10 cow SSW          3.64E-06            3.1          9.82E-10       2.28E-06          (a)    4.53E-10 2.28E-06      (a)    4.53E-10 SW          3.19E-06            2.5          1.1IE-09      1.58E-06          (a)    3.56E-10 1.58E-06      (a)    3.56E-10 WSW          2.12E-06           2.4          1.26E-09      8.55E-07           (a)    3.18E-10 8.55E-07       (a)    3.18E-10 W          7.54E-07             (a)         4.44E-10      7.54E-07          (a)   4.44E-10 7.54E-10      (a)   4.44E-10 WNW          6.03E-07            (a)         3.25E-10      6.03E-07          (a)   3.25E-10 6.03E-07      (a)   3.25E-10 NW          6.83E-07            4.3          4.05E-10       6.82E-07          4.3    4.05E-10 6.02E-07      (a)    3.27E-10 NNW          1.34E-06            2.2          1.26E-09      5. 16E-07          5.0    3.01E-10 5.20E-07      (a)    3.04E-10 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.
TABLE 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 X/Q RESIDENCE(b)
(b) Controlling locations are discussed in Appendix A.
D/Q X/Q GARDEN(b)
0
D/Q X/Q MILK(b) D/Q DIRECTION (Sec/r 3) Dist. Miles (mr 2) (Sec/m 3) Dist. Miles (m ) (Sec/m 3) Dist. Miles (rn 2)LA ON N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 2.58E-06 1.85E-06 1.66E-06 8.75E-07 8.90E-07 6.37E-07 5.84E-07 1.36E-06 2.65E-06 3.64E-06 3.19E-06 2.12E-06 7.54E-07 6.03E-07 6.83E-07 1.34E-06 1.8 1.7 2.2 2.9 3.0 3.7 (a)4.4 4.2 3.1 2.5 2.4 (a)(a)4.3 2.2 2.47E-09 2.97E-09 3.OOE-09 8.86E-10 6.17E-10 2.84E-10 1.52E-10 2.88E-10 5.25E-10 9.82E-10 1.1 IE-09 1.26E-09 4.44E-10 3.25E-10 4.05E-10 1.26E-09 2.42E-06 1 .85E-06 I1.48E-06 8.75E-07 4.06E-07 5.80E-07 5.84E-07 I1.09E-06 2.25E-06 2.28E-06 1 .58E-06 8.55E-07 7.54E-07 6.03E-07 6.82E-07 5. 16E-07 1.9 1.7 2.4 2.9 4.6 4.0 (a)(a)4.9 (a)(a)(a)(a)(a)4.3 5.0 2.22E-09 2.97E-09 2.54E-09 8.86E-10 2.15E-10 2.46E-10 1.52E-10 2.15E-10 4.06E-10 4.53E-10 3.56E-10 3.18E-10 4.44E-10 3.25E-10 4.05E-10 3.01E-10 7.03E-07 4.70E-07 5.77E-07 3.86E-07 4.25E-07 3.73E-07 5.84E-07 1.09E-06 2.3 1E-06 2.28E-06 1.58E-06 8.55E-07 7.54E-10 6.03E-07 6.02E-07 5.20E-07 (a)(a)(a)(a)4.5 (a)(a)(a)4.8 (a)(a)(a)(a)(a)(a)(a)3.48E-10 4.04E-10 6.51E-10 2.86E-10 2.31E-10 goat 1.37E-10 1.52E-10 2.151E-10 4.21E-10 cow 4.53E-10 3.56E-10 3.18E-10 4.44E-10 3.25E-10 3.27E-10 3.04E-10 0 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.(b) Controlling locations are discussed in Appendix A.


==References:==
==References:==
1984 Land Use Census (letter ANPM-21221-JRMALEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
===4.4 Requirements===
Liquid Efuents The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See Figure 6-4 and Figure 6-5) shall be limited:
: a. During any calendar quarter to less than or equal to 1.5 mrems to the total 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 total body and to less than or equal to 10 mrems to any organ.
Applicability:    At all times.
Action:
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
4.4.1 Surveillance Requirements 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 the ODCM at least once per 31 days.
4.4.2 Implementation of the Requirements This Requirement does not require implementation guidance. There are no offsite liquid effluent releases.
57                                        ODCM Rev. 20
5.0    TOTAL DOSE AND DOSE TO PUBLIC ONSITE


1984 Land Use Census (letter ANPM-21221-JRMALEB).
===5.1 Requirement===
NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.  
Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to direct 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:
With the calculated doses from the release of radioactive materials in liquid and gaseous effluents exceeding twice the limits of Section 4.4a, 4.4b, 4.1a, 4.1b, 4.2a or 4.2b calculations shall be made including direct radiation contributions from the reactor units (including outside storage tanks, etc.) to determine whether the above limits of Section 5.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203(a)(4), 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 concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report within 30 days is considered a timely request, and a variance is granted until staff action on the request is complete.
5.1.1 Surveillance Requirements
: a. Cumulative dose contributions from the gaseous effluents shall be determined in accordance with the surveillance requirements of Section 4.4.1, 4.1.1 and 4.2.1 and in accordance with the methodology and parameters contained in Section 5.1.2.
: b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Section 5.1.2. This requirement is applicable only under conditions set forth in Section 5.1, Action.
5.1.2 Implementation of the Requirement Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered.
The total dose to any MEMBER OF THE PUBLIC will be determined based on a sum of the doses from all three units' releases and doses from direct radiation from PVNGS.
58                                      ODCM Rev. 20


===4.4 Requirements===
This dose evaluation is performed annually and submitted with the Annual Radioactive Effluent Release Report to assure compliance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. NUREG-0543, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), February 1980, provides a discussion on compliance with 40 CFR Part 190 in relation to the Radiological Environmental Technical Specifications for sites of up to four nuclear power reactors. The NUREG concludes that as long as a nuclear plant site operates at a level below the 10 CFR Part 50, Appendix I reporting requirements, and there is no significant source of direct radiation from the site, no extra analysis is required to demonstrate compliance with 40 CFR Part 190. As a result, this dose evaluation will also be performed whenever calculated doses associated with effluent releases exceed twice the limits of Section 4.4a, 4.4b, 4.1a, 4.lb, 4.2a or 4.2b.
Dose Contribution from Liquid and Gaseous Effluents The annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noble gases released in gaseous effluents is determined by using the following equation:
DWB            = (3.17E-08) Zi [(Ki) (X/Q)UNIT (Q1)]                                        (5-1)
Where:
K-            = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per jiCi/m 3 from Table 3-3.
Qi            = the integrated release of radionuclide i, in pCi for the previous calendar year.
(X/Q)UNrr      = the highest calculated annual average dispersion parameter, in sec/m3 , for a particular unit, at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.
                  =2.92E-06 from Unit 1
                  =2.19E-06 from Unit 2
                  =2.31E-06 from Unit 3 DWB            = the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.
3.17E-08      = the inverse of seconds in a year (yr/sec).
59                                      ODCM Rev. 20


Liquid Efuents The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See Figure 6-4 and Figure 6-5) shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrems to the total 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 total body and to less than or equal to 10 mrems to any organ.Applicability:
The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-1 31, iodine- 133, tritium and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents is determined by using the following equation:
At all times.Action: With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.4.4.1 Surveillance Requirements 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 the ODCM at least once per 31 days.4.4.2 Implementation of the Requirements This Requirement does not require implementation guidance.
Do            = (3.17E-08) Zi [Ek(RikWk) (Qi)]                                              (5-2)
There are no offsite liquid effluent releases.57 ODCM Rev. 20  
Where:
Do            = the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location.
Qi            = the integrated release of radionuclide i, in pCi, for the previous calendar year.
Rik            = the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per pCi/M3 and for the food and ground plane pathways in m2 -mrem/yr per gCi/sec) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.
WK            =  the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the total annual organ dose to a MEMBER OF THE PUBLIC at the controlling location for the particular unit.
              = (X/Q)UNrrm in sec/M3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.
                  =2.92E-06 from Unit I
                  =2.19E-06 from Unit 2
                  =2.31E-06 from Unit 3
              = (D/Q)uNrr, in m-2, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.
                  =3.25E-09 from Unit I
                  =3.88E-10 from Unit 2
                  =4.21E-10 from Unit 3 3.17E-08      = the inverse of seconds in a year (yr/sec).
60                                        ODCM Rev. 20


===5.0 TOTAL===
Dose Due to Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be evaluated by first determining the direct radiation dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling location by the inverse square law of distance.
DOSE AND DOSE TO PUBLIC ONSITE 5.1 Requirement:
Dose from Radioactive Liquid and Gaseous Effluents to MEMBERS OF THE PUBLIC due to their activities within the SITE BOUNDARY.
Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to direct 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:
These activities have been determined to be limited to the vicinity of the Energy Information Center (EIC) located inside the SITE BOUNDARY. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location.
At all times.Action: With the calculated doses from the release of radioactive materials in liquid and gaseous effluents exceeding twice the limits of Section 4.4a, 4.4b, 4.1a, 4.1b, 4.2a or 4.2b calculations shall be made including direct radiation contributions from the reactor units (including outside storage tanks, etc.) to determine whether the above limits of Section 5.1 have been exceeded.
However this calculation has been historically performed assuming an occupancy factor of one (implying continuous occupancy over the entire year).
If such is the case, prepare and submit to the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203(a)(4), 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 concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
A X/Q, determined for the Energy Information Center, will be used for this assessment.
If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report within 30 days is considered a timely request, and a variance is granted until staff action on the request is complete.5.1.1 Surveillance Requirements
: a. Cumulative dose contributions from the gaseous effluents shall be determined in accordance with the surveillance requirements of Section 4.4.1, 4.1.1 and 4.2.1 and in accordance with the methodology and parameters contained in Section 5.1.2.b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Section 5.1.2. This requirement is applicable only under conditions set forth in Section 5.1, Action.5.1.2 Implementation of the Requirement Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered.
The total dose to any MEMBER OF THE PUBLIC will be determined based on a sum of the doses from all three units' releases and doses from direct radiation from PVNGS.58 ODCM Rev. 20 This dose evaluation is performed annually and submitted with the Annual Radioactive Effluent Release Report to assure compliance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
NUREG-0543, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), February 1980, provides a discussion on compliance with 40 CFR Part 190 in relation to the Radiological Environmental Technical Specifications for sites of up to four nuclear power reactors.
The NUREG concludes that as long as a nuclear plant site operates at a level below the 10 CFR Part 50, Appendix I reporting requirements, and there is no significant source of direct radiation from the site, no extra analysis is required to demonstrate compliance with 40 CFR Part 190. As a result, this dose evaluation will also be performed whenever calculated doses associated with effluent releases exceed twice the limits of Section 4.4a, 4.4b, 4.1a, 4.lb, 4.2a or 4.2b.Dose Contribution from Liquid and Gaseous Effluents The annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noble gases released in gaseous effluents is determined by using the following equation: DWB = (3.17E-08)
Zi [(Ki) (X/Q)UNIT (Q 1)] (5-1)Where: K- = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per jiCi/m 3 from Table 3-3.Qi = the integrated release of radionuclide i, in pCi for the previous calendar year.(X/Q)UNrr
= the highest calculated annual average dispersion parameter, in sec/m 3 , for a particular unit, at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.
=2.92E-06 from Unit 1=2.19E-06 from Unit 2=2.31E-06 from Unit 3 DWB = the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.
3.17E-08 = the inverse of seconds in a year (yr/sec).59 ODCM Rev. 20 The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-1 31, iodine- 133, tritium and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents is determined by using the following equation: Do = (3.17E-08)
Zi [Ek(RikWk) (Qi)] (5-2)Where: Do = the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location.Qi = the integrated release of radionuclide i, in pCi, for the previous calendar year.Rik = the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per pCi/M 3 and for the food and ground plane pathways in m 2-mrem/yr per gCi/sec) at the controlling location.
The Rik's for each age group are given in Tables 4-1 through 4-15.WK = the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the total annual organ dose to a MEMBER OF THE PUBLIC at the controlling location for the particular unit.= (X/Q)UNrrm in sec/M 3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.
=2.92E-06 from Unit I=2.19E-06 from Unit 2=2.31E-06 from Unit 3= (D/Q)uNrr, in m-2 , for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.
=3.25E-09 from Unit I=3.88E-10 from Unit 2=4.21E-10 from Unit 3 3.17E-08 = the inverse of seconds in a year (yr/sec).60 ODCM Rev. 20 Dose Due to Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be evaluated by first determining the direct radiation dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling location by the inverse square law of distance.Dose from Radioactive Liquid and Gaseous Effluents to MEMBERS OF THE PUBLIC due to their activities within the SITE BOUNDARY.These activities have been determined to be limited to the vicinity of the Energy Information Center (EIC) located inside the SITE BOUNDARY.
An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location.However this calculation has been historically performed assuming an occupancy factor of one (implying continuous occupancy over the entire year).A X/Q, determined for the Energy Information Center, will be used for this assessment.
Equations 5-1 and 5-2 in Section 5.1.2 should be used for this assessment.
Equations 5-1 and 5-2 in Section 5.1.2 should be used for this assessment.
61 ODCM Rev. 20  
61                                       ODCM Rev. 20
-6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)6.1 Requirement:
 
REMP The radiological environmental monitoring program shall be conducted as specified in Table 6-1, based on locations determined using data from the pre-operational monitoring period; and/or the operational monitoring period indicating a need to make changes in the program.Applicability:
6.0   RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
At all times.Action: a. With the radiological environmental monitoring program not being conducted as specified in Table 6-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, as required by Section 7.2, a description of the reasons for not conducting the program as required and the plans 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 6-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to A MEMBER OF THE PUBLIC is less than the calendar year limits of Section 4.4, 4.1 and 4.2. When more than one of the radionuclides in Table 6-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) + concentration (2) + 2 1.0 reporting level (l) reporting level (2) ...When radionuclides other than those in Table 6-2 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 is equal to or greater than the calendar year limits of Section 4.4, 4.1 and 4.2. 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.c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 6-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.* The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.62 ODCM Rev. 20  
===6.1 Requirement===
-6.1.1 Surveillance Requirements
REMP The radiological environmental monitoring program shall be conducted as specified in Table 6-1, based on locations determined using data from the pre-operational monitoring period; and/or the operational monitoring period indicating a need to make changes in the program.
: a. The radiological environmental monitoring samples shall be collected pursuant to Table 6-1 from the specific locations given in Table 6-4 and Figure 6-1 and Figure 6-2 and shall be analyzed pursuant to the requirements of Table 6-1, and the detection capabilities required by Table 6-3.6.1.2 Implementation of the Requirements The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected based on the effluent measurements and modeling of the environmental exposure pathways.Thus the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from station operation.
Applicability:   At all times.
Action:
: a. With the radiological environmental monitoring program not being conducted as specified in Table 6-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, as required by Section 7.2, a description of the reasons for not conducting the program as required and the plans 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 6-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to A MEMBER OF THE PUBLIC is less than the calendar year limits of Section 4.4, 4.1 and 4.2. When more than one of the radionuclides in Table 6-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) +           2 1.0 reporting level (l)   reporting   level (2) . ..
When radionuclides other than those in Table 6-2 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 is equal to or greater than the calendar year limits of Section 4.4, 4.1 and 4.2. 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.
: c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 6-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
* The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
62                                       ODCM Rev. 20
 
6.1.1 Surveillance Requirements
: a. The radiological environmental monitoring samples shall be collected pursuant to Table 6-1 from the specific locations given in Table 6-4 and Figure 6-1 and Figure 6-2 and shall be analyzed pursuant to the requirements of Table 6-1, and the detection capabilities required by Table 6-3.
6.1.2 Implementation of the Requirements The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected based on the effluent measurements and modeling of the environmental exposure pathways.
Thus the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from station operation.
This requirement is implemented by Nuclear Administrative and Technical Manual procedures.
This requirement is implemented by Nuclear Administrative and Technical Manual procedures.
63 ODCM Rev. 20 TABLE 6-1 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations' Collection Frequency' of Analyslsd A1rborn Samples from 5 locations:
63                                       ODCM Rev. 20
4 Continuous sampling Gross beta weeklyc, samples at or near the SITE collected weekly, or I-131 weekly; gamma Radioiodine and BOUNDARIES  
 
(#14A, 15,29,40) more frequently if isotopic analysis of particulates including 3 different sectors of the required by dust composite (by highest calculated annual average loading. location) quarterly.
TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway           Number of Representative             Sampling and     Type and Frequency and/or Sample       Samples and Sample Locations'         Collection Frequency'     of Analyslsd A1rborn               Samples from 5 locations: 4           Continuous sampling   Gross beta weeklyc, samples at or near the SITE           collected weekly, or   I-131 weekly; gamma Radioiodine and       BOUNDARIES (#14A, 15,29,40)           more frequently if     isotopic analysis of particulates           including 3 different sectors of the required by dust       composite (by highest calculated annual average     loading.               location) quarterly.
ground level D/Q.*I sample (#40) from areas of special interest, which is from the vicinity of a community having the highest calculated annual average D/Q.I sample (#6A) from a control location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.'
ground level D/Q.*
Direct radiationb Forty (40) routine monitoring Quarterly Gamma dose stations (#5-40, #42, #44, #46, #50) quarterly.
I sample (#40) from areas of special interest, which is from the vicinity of a community having the highest calculated annual average D/Q.
either with 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 (16 locations);
I sample (#6A) from a control I                        location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.'
An outer ring of stations, one in each meteorological sector in the 6-8 km (4-5 mi) range from the site (16 locations);
Direct radiationb     Forty (40) routine monitoring         Quarterly             Gamma dose stations (#5-40, #42, #44, #46, #50)                         quarterly.
and The balance of the stations (8 locations) 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.* D/Q refers to average annual relative ground deposition rate.64 ODCM Rev. 20 TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequencya of Analysisd Waterborne Surface Water storage reservoir  
either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
(#60) Monthly composite of Gamma isotopic Evaporation pond #1 (#59) weekly grab sample. analysis monthly;Evaporation pond #2 (#63) tritium quarterly.
An inner ring of stations, one in each meteorological sector in the general area of the site boundary (16 locations);
Ground 2 onsite wells' (#57, #58) Quarterly grab sample Tritium and gamma isotopic analysis quarterly.
An outer ring of stations, one in each meteorological sector in the 6-8 km (4-5 mi) range from the site (16 locations); and The balance of the stations (8 locations) 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.
Drinking (well) 3 wells from surrounding Composite sample of I-131 analysis on each residences  
* D/Q refers to average annual relative ground deposition rate.
(#46, #48, #49) that weekly grab samples composite when the would be affected by its discharge.
64                                   ODCM Rev. 20
over 2-week period dose calculated for when 1-131 analysis is the consumption of performed, monthly the water is greater composite of weekly than I mrem per grab samples otherwise year.9 Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.
 
Ingestko Samples from milking animals in Semimonthly for Gamma isotopic and 3 locations within 5 km distant animals on pasture; I-131 analysis Milk having the highest dose potential.
TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway       Number of Representative             Sampling and     Type and Frequency and/or Sample     Samples and Sample Locationsa     Collection Frequencya       of Analysisd Waterborne Surface           Water storage reservoir (#60)       Monthly composite of   Gamma isotopic Evaporation pond #1 (#59)           weekly grab sample. analysis monthly; Evaporation pond #2 (#63)                                 tritium quarterly.
otherwise, monthly. semimonthly when If there are none, 1 sample from animals are on pasture milking animals in each of three or monthly at other areas between 5 and 8 km (3-5 mi) times.distant (#51, #54) where doses are calculated to be greater than 1 mrem per year.9 One sample from milking animals at a control location 15 to 30 km (9-18 mi) distant (#53) and in the least prevalent wind direction.
Ground             2 onsite wells' (#57, #58)         Quarterly grab sample Tritium and gamma isotopic analysis quarterly.
I I 65 ODCM Rev. 20 TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequencya of Analyslsd Food Producitsj 2 samples (#47, #52) of 3 types of Monthly during Gamma isotopic broad leaf vegetation (as available) growing season. analysis.from locations identified per the criteria of Section 6.2b. of this manual.I control sample (#62) of 3 types Monthly during Gamma isotopic of broad leaf vegetation (as growing season. analysis.available) grown 15 to 30 km (9-18 mi) distant in the least prevalent wind direction.e
Drinking (well)   3 wells from surrounding           Composite sample of   I-131 analysis on each residences (#46, #48, #49) that     weekly grab samples   composite when the would be affected by its discharge. over 2-week period     dose calculated for when 1-131 analysis is the consumption of performed, monthly     the water is greater composite of weekly   than I mrem per grab samples otherwise year.9 Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.
Ingestko           Samples from milking animals in Semimonthly for           Gamma isotopic and 3 locations within 5 km distant     animals on pasture;   I-131 analysis I Milk               having the highest dose potential. otherwise, monthly. semimonthly when If there are none, 1 sample from                           animals are on pasture milking animals in each of three                           or monthly at other areas between 5 and 8 km (3-5 mi)                         times.
I                    distant (#51, #54) where doses are calculated to be greater than 1 mrem per year.9 One sample from milking animals at a control location 15 to 30 km (9-18 mi) distant (#53) and in the least prevalent wind direction.
65                                 ODCM Rev. 20
 
TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway         Number of Representative             Sampling and         Type and Frequency and/or Sample       Samples and Sample Locationsa       Collection Frequencya         of Analyslsd Food Producitsj     2 samples (#47, #52) of 3 types of Monthly during               Gamma isotopic broad leaf vegetation (as available) growing season.             analysis.
from locations identified per the criteria of Section 6.2b. of this manual.
I control sample (#62) of 3 types   Monthly during             Gamma isotopic of broad leaf vegetation (as         growing season.           analysis.
available) grown 15 to 30 km (9-18 mi) distant in the least prevalent wind direction.e
* When broad leaf vegetation samples are not available, reports from 4 existing supplemental airborne radioiodine sample locations will be substituted.
* When broad leaf vegetation samples are not available, reports from 4 existing supplemental airborne radioiodine sample locations will be substituted.
66 ODCM Rev. 20 TABLE 6-1 (Continued)
66                                   ODCM Rev. 20
TABLE NOTATION a The number, media, frequency, and location of sampling may vary from site to site. It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question.
 
Actual locations (distance and direction) from the site shall be provided in Table 6-4 and Figure 6-1 or Figure 6-2 in the ODCM. Refer to Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants." b Regulatory Guide 4.13 provides guidance for thermoluminescence dosimetry (TLD) systems used for environmental monitoring.
TABLE 6-1 (Continued)
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.
TABLE NOTATION a The number, media, frequency, and location of sampling may vary from site to site. It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question. Actual locations (distance and direction) from the site shall be provided in Table 6-4 and Figure 6-1 or Figure 6-2 in the ODCM. Refer to Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants."
For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor, and two or more phosphors in a packet may be considered as two or more dosimeters.
b Regulatory Guide 4.13 provides guidance for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. 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.
Film badges should not be used for measuring direct radiation.
For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor, and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.
c Particulate sample filters shall be analyzed for gross beta 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than 10 times the yearly mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.d Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.e The purpose of this sample is to obtain background information.
c Particulate sample filters shall be analyzed for gross beta 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than 10 times the yearly mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.
If it is not practical to establish control locations in accordance with the wind direction and distance criteria, other sites that provide valid background data may be substituted.
d Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
f Groundwater samples should 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.
e The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the wind direction and distance criteria, other sites that provide valid background data may be substituted.
g The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.67 ODCM Rev. 20 TABLE 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/I) or Gas (pCi/ni) Will) (pCi/kg, wet)H-3 20,000 *Mn-54 1,000 Fe-59 400 Co-58 1,000 Co-60 300 Zn-65 300 Zr-Nb-95 400 I-131 2** 0.9 3 100 Cs-134 30 10 60 1,000 Cs-137 50 20 70 2,000 Ba-La-140 200 300* For drinking water samples. This is a 40 CFR 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.*
f Groundwater samples should 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.
* If no drinking water pathway exists, a reporting level of 20 pCi/I may be used.68 ODCM Rev. 20 TABLE 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS a Lower Limit of Detection (LLD)b Airborne Particulate Fresh Milk Food Products Analysis Water (pCiI) or Gas (pCVM 3) (pCiL) (pCi/kg, wet)Gross Beta 4 0.01 H-3 2000*Mn-54 15 Fe-59 30 Co-58, -60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 15 60 Cs-137 18 0.06 18 80 Ba-140 60 60 La-140 15 15 NOTE: This list does not mean that only these nuclides are to be detected and reported.
g The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.* 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.69 ODCM Rev. 20 Table 6-3 (Continued)
67                                       ODCM Rev. 20
TABLE NOTATION a Guidance for detection capabilities for thermoluminescent dosimeters used for environmental measurements is given in Regulatory Guide 4.13.b Table 6-3 indicates acceptable detection capabilities for radioactive materials in environmental samples.These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, 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 4.66s,, LLDE
TABLE 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate         Fresh Milk     Food Products Analysis         Water (pCi/I)         or Gas (pCi/ni)               Will)         (pCi/kg, wet)
H-3             20,000
* Mn-54               1,000 Fe-59                 400 Co-58               1,000 Co-60                 300 Zn-65                 300 Zr-Nb-95               400 I-131               2**                     0.9                     3                 100 Cs-134                 30                     10                     60               1,000 Cs-137                 50                     20                     70               2,000 Ba-La-140               200                                             300
* For drinking water samples. This is a 40 CFR 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 reporting level of 20 pCi/I may be used.
68                                   ODCM Rev. 20
 
TABLE 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS a Lower Limit of Detection (LLD)b Airborne Particulate         Fresh Milk         Food Products Analysis         Water (pCiI)           or Gas (pCVM3 )             (pCiL)             (pCi/kg, wet)
Gross Beta               4                     0.01 H-3               2000*
Mn-54                 15 Fe-59                 30 Co-58, -60               15 Zn-65                 30 Zr-95                 30 Nb-95                 15 I-131                 1**                   0.07                       1                   60 Cs-134                 15                     0.05                     15                   60 Cs-137                 18                     0.06                     18                   80 Ba-140                 60                                               60 La-140                 15                                               15 NOTE: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
* 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.
69                                       ODCM Rev. 20
 
Table 6-3 (Continued)
TABLE NOTATION a Guidance for detection capabilities for thermoluminescent dosimeters used for environmental measurements is given in Regulatory Guide 4.13.
b Table 6-3 indicates acceptable detection capabilities for radioactive materials in environmental samples.
These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, 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               4.66s,,
LLDE
* V
* V
* 2.22
* 2.22
* Y
* Y
* exp(-XAt)Where: LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume), Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
* exp(-XAt)
Typical values of E, V, Y, and At should be used in the calculation.
Where:
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.
LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume),
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
E is the counting efficiency (as counts per disintegration),
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.70 ODCM Rev. 20  
V is the sample size (in units of mass or volume),
2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
X is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples (e.g.,
potassium-40 in milk samples). 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. 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 LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
70                                       ODCM Rev. 20


===6.2 Requirement===
===6.2 Requirement===
Land Use Census A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.
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 Section 4.2.1, identify the new location(s) in the next Annual Radioactive Effluent Release Report, pursuant to Section 7.1.
: 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 Section 6.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may then be deleted from the monitoring program.
6.2.1 Surveillance Requirements
: a. The land use census shall be conducted during the growing season annually 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 Section 7.2.
6.2.2 Implementation of the Requirements The above Requirement is implemented by Nuclear Administrative and Technical Manual procedures.
* 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 6-1 shall be followed, including analysis of control samples.
71                                      ODCM Rev. 20
63 Requirement: Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 6-1, as applicable.
Applicability:  At all times.
Action:
: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.
63.1 Surveillance Requirements
: a. A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the methodology and parameters in this manual shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.
63.2 Implementation of the Requirements PVNGS laboratories or contract laboratories which perform analyses for the Radiological Environmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program. The participation includes all of the determinations (sample medium-radionuclide combinations) that are included in the monitoring program.
If deviation from specified limits is identified an investigation is made to determine the reason for the deviation and corrective actions are taken as necessary. The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report.
72                                        ODCM Rev. 20
TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE  SAMPLE    NOTE  DESIGNATION SITE    TYPE        (d)        (a)            LOCATION DESCRIPTION (c) 1      TLD      SUP        E30      Goodyear 2      TLD      SUP      ENE24      Scott-Libby School 3      TLD      SUP        E21      Liberty School 4      TLD      SUP        E16      Buckeye 4      Air      SUP        E16      Same as TLD S    TLD (b)    SP      ESE1 1    Palo Verde School 6    TLD (b)  Control    SSE31      APS Gila Bend substation 6A    Air (b)  Control    SSE13      Old US 80 7    TLD (b)    SP        SE7      Old US 80 and Arlington School Rd.
I    7A      Air      SUP        ESE3      Arlington School 8    TLD (b)    OR        SSE4      Southern Pacific Pipeline Rd.
9    TLD (b)    OR          S5      Southern Pacific Pipeline Rd.
10    TLD (b)    OR        SE5      355th Ave. and Elliot Rd.
11    TLD (b)    OR        ESE5      339th Ave. and Dobbins Rd.
12    TLD (b)    OR          E5      339th Ave. and Buckeye-Salome Rd.
13    TLD (b)      IR        N1      N site boundary 14    TLD (b)      IR      NNE2      NNE site boundary 14A    Air (b)              NNE2      371st Ave. and Buckeye-Salome Rd.
15    TLD (b)      IR        NE2      NE site boundary, WRF access road 15    Air (b)              NE2      Same as TLD 16    TLD (b)      IR      ENE2      ENE site boundary 17    TLD (b)      JR        E2      E site boundary 17A      Air      SUP          E3      351st Ave.
18    TLD (b)      IR      ESE2      ESE site boundary 19    TLD (b)      IR        SE2      SE site boundary 20    TLD (b)      IR      SSE2      SSE site boundary 73                                ODCM Rev. 20
TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE  SAMPLE    NOTE    DESIGNATION SITE    TYPE      (d)        (a)            LOCATION DESCRIPTION (c) 21    TLD (b)    IR        S3      S site boundary 21      Air    SUP          S3      Same as TLD 22    TLD (b)    IR      SSW3      SSW site boundary 23    TLD (b)    OR        W5        N of Elliot Rd 24    TLD (b)    OR        SW4      N of Elliot Rd.
25    TLD (b)    OR        WSW5      N of Elliot Rd.
26    TLD (b)    OR        SSW4      Duke Property 27    TLD (b)    IR        SWi      SW site boundary 28    TLD (b)    IR      WSW1      WSW site boundary 29    TLD (b)    IR        WI      W site boundary 29    Air (b)              WI      Same as TLD 30    TLD (b)    IR      WNWI      WNW site boundary 31    TLD (b)    IR      NWI        NW site boundary 32    TLD (b)    IR      NNW1      NNW site boundary 33    TLD (b)    OR        NW4        S of Buckeye Rd.
34    TLD (b)    OR        NNW5      395th Ave. and Van Buren St.
35    TLD (b)    SP      NNW8      Tonopah 35      Air    SUP        NNW8      Same as TLD 36    TLD (b)    OR          N5      Wintersburg Rd. and Van Buren St.
37    TLD (b)    OR        NNE5      363rd Ave. and Van Buren St.
38    TLD (b)    OR        NE5      355th Ave. and Buckeye Rd.
39    TLD (b)    OR      ENE5      343rd Ave. N of Broadway Rd.
40    TLD (b)    SP        N2      Wintersburg 40    Air (b)              N2      Same as TLD 41      TLD      SUP        ESE3      Arlington School 42    TLD (b)    SP          N8      Ruth Fisher School 44    TLD (b)  Control    ENE35      El Mirage 74                                ODCM Rev. 20
TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE  SAMPLE        NOTE    DESIGNATION SITE      TYPE          (d)        (a)            LOCATION DESCRIPTION (c)
SUP Transit 45        TLD        Control    ONSITE      Central lab, lead pig 46      TLD (b)        SP        ENE30      Litchfield Park School 46      Water (b)    WD          NW9      Local farm 47        TLD        SUP          E35      Littleton School 47    Vegetation (b)            ESE4      Local residence 48        TLD        SUP          E24      Jackrabbit Trail 48      Water (b)    WD          SWi      Local residence 49        TLD        SUP        ENEI 1    Palo Verde Rd.
49      Water (b)    WD          N2      Local residence 50    TLD (b)        OR      WNW5        S of Buckeye-Salome Rd.
51    Milk (b)                  NE4      Local residence (goats) 52  Vegetation (b)            NNE2      Local residence 53    Milk (b)      Control    NE36      Local residence (goats)
I 54    Milk (b)                  NNE4      Local residence (goats)
WD 55    Water          SUP        SW3      Local residence Ground Water 57        (b)        WG        onsite    Well 27ddc Ground Water 58        (b)        WG        onsite    Well 34abb Surface Water 59        (b)        WS        onsite    Evaporation Pond #1 Surface Water 60        (b)        WS        onsite    Reservoir 62  Vegetation (b) Control    ENE26      Commercial produce company Surface Water 63        (b)        WS        onsite    Evaporation Pond #2 75                              ODCM Rev. 20
NOTES: (a) Distance and direction are relative to the Unit 2 containment, rounded to the nearest mile.
(b) These samples fulfill the requirements of the ODCM, Table 6-1.
(c) Refer to Figure 6-1 and Figure 6-2 for relative locations of sample sites.
(d) IR - inner ring OR - outer ring SP - school or population center WS - waterborne surface WG - waterborne ground WD - waterborne drinking SUP -designated supplemental sampling location 76                                      ODCM Rev. 20
Graphic Scale In Miles    d 0 1  2  3  4    5
        ,      v      .      [NNE I              -1E e7 NW                        ~x ~
          -~ ~    Ib7-WNW 1f    ~                  C      -                              T Palo Verde Nuclear Generating Station Figure 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-10 MILES 77                                        ODCM Rev. 20
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Figure 6-3 DELETED 79    ODCM Rev. 20
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4f  Airstrip 82                              ODCM Rev. 20
7.0    RADIOLOGICAL REPORTS
===7.1 Requirement===
Annual Radioactive Effluent Release Report
* Routine Annual Radioactive Effluent Release Reports covering the operation of the units during the previous calendar year shall be submitted in accordance with Technical Specification 5.6.3.
The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Annual 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 6-4) 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. 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 the ODCM.
The Annual 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 contributions are given Section 5.0 and Regulatory Guide 1.109 Rev. 1, October 1977.
The Annual Radioactive Effluent Release Report shall also include information required by the Technical Requirements Manual, Section 5.0.600.1.
* A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
      **  In lieu of submission with the Annual 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.
83                                        ODCM Rev. 20
The Annual Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
: a. Container volume,
: b. Total curie quantity (specify whether determined by measurement or estimate),
: c. Principal radionuclides (specify whether determined by measurement or estimate),
: d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
: e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
: f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).
The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
Changes to the ODCM shall be submitted in the form of a complete, legible copy as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Changes made to the Process Control Program shall be submitted with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the Process Control Program was made.
84                                    ODCM Rev. 20
72 Requirement: Annual Radiological Environmental Operating Report
* Routine Annual Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted by May 15 of each year in accordance with Technical Specification 5.6.2.
The Annual Radiological Environmental Operating Reports 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, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 6.2.
The Annual Radiological Environmental Operating Reports 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 specified in Table 6-4 and Figure 6-1 and Figure 6-2 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 reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Section 6.3; discussion of all deviations from the sampling schedule of Table 6-1; and discussion of all analyses in which the LLD required by Table 6-3 was not achievable.
* A single submittal may be made for a multiple unit station.
**  One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
85                                      ODCM Rev. 20
APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses.
The determination of a controlling location for implementation of IOCFR50 for radioiodines and particulates is known to be a function of:
(1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Equation 5-2 results in the respective equations at the controlling location. The isotopic release rates are based upon the source terms calculated using the PVNGS Environmental Report, Operating License Stage, Table 3.5-12, without carbon.
All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated. These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure. An infant is assumed to be present at all milk pathway locations. A child is assumed to be present at all vegetable garden locations. The ground plane exposure pathway is only considered to be present where an infant is not present. Naturally, inhalation is present everywhere an individual is present.
For the determination of the controlling locations, the highest X/Q and D/Q values, based on the 9 year meteorological data base, for the vegetable garden, cow milk, and goat milk pathways, are selected for each unit. The receptor organ doses have been calculated at each of these locations. Based upon these calculations, it is determined that the controlling receptor pathway is a function of unit location. For Unit 1, the controlling receptor is a garden-child pathway; for releases from Unit 2 and Unit 3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table 4-16, 4-17, or 4-18, which, in turn, is based upon the 1984 Land Use Census. Locations of the nearest residences, gardens and milk animals, as determined in the 1984 Land Use Census, are given in Table 4-16, 4-17, and 4-18.
86                                      ODCM Rev. 20
APPENDIX B BASES FOR REQUIREMENTS B-2.1 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 the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, 64 of Appendix A to 10 CFR PART 50.
There are two separate radioactive gaseous effluent monitoring systems: the low range effluent monitors for normal plant radioactive gaseous effluents and the high range effluent monitors for post-accident plant radioactive gaseous effluents. The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions. The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the low range monitors.
B-3.1 GASEOUS EFFLUENT - DOSE RATE This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY, in excess of the design objectives of Appendix I to 10 CFR part 50. This requirement is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section H.A and l.C design objectives of Appendix I to 10 CFR part 50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a 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 mremslyear to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year. This requirement does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).
This requirement applies to the release of radioactive materials in gaseous effluents from all reactor 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 (LLD). 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 (revised annually).
87                                      ODCM Rev. 20
B-3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - CONCENTRATION This requirement is provided to ensure that the annual total effective dose equivalent to individual members of the public from the licensed operation does not exceed the requirements of 10 CFR Part 20, due to the accumulated activity in the evaporation ponds from the secondary system discharges.
Restricting the concentrations of the secondary liquid wastes discharged to the onsite evaporation ponds will restrict the quantity of radioactive material that can accumulate in the ponds. This, in turn, provides assurance that in the event of an uncontrolled release of the pond's contents to an UNRESTRICTED AREA, the resulting total effective dose equivalent to individual members of the public at the nearest exclusion area boundary will not exceed the requirements of 10 CFR Part 20.
This requirement applies to the secondary system liquid waste discharges of radioactive materials from all reactor units to the onsite evaporation ponds.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD). 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 (revised annually).
B-4.1 GASEOUS EFFLUENT - DOSE, Noble Gases This requirement is provided to implement Sections ll.B, Il.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section Il.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and 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 the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous 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 10 CFR Part 50, 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 and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.
88                                      ODCM Rev. 20
B-4.2 GASEOUS EFFLUENT - DOSE - Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days This requirement is provided to implement the requirements of Sections II.C, III.A, IV.A of Appendix I, 10 CFR Part 50. This requirement is the guide set forth in Section ll.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 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 IIl.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases for 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 specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these 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 requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.
B-4.3 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix 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 H.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.
The minimum analysis frequency of 4/M (i.e., at least 4 times per month at intervals no greater than 9 days and a minimum of 48 times a year) is used for certain radioactive gaseous waste sampling in Table 3-1. This will eliminate taking double samples when quarterly and weekly samples are required at the same time.
89                                      ODCM Rev. 20


Land Use Census A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m 2 (500 ft 2) producing broad leaf vegetation.
B-4A  SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - DOSE This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section M.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IVA of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by 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 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section lII.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, 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.
Applicability:
This requirement applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
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 Section 4.2.1, identify the new location(s) in the next Annual Radioactive Effluent Release Report, pursuant to Section 7.1.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 Section 6.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may then be deleted from the monitoring program.6.2.1 Surveillance Requirements
B-5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE This requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.1301(d). The requirement specifies the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Even if a site was to contain up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units (including outside storage tanks, etc.)
: a. The land use census shall be conducted during the growing season annually 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.
are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a 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, submittal of the Special Report within 30 days 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 Part 190.11 and 10 CFR Part 20.2203(a)(4), 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 other requirements for dose limitation of 10 CFR Part 20, as addressed in Section 3.2 and 3.1 of the ODCM. 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.
The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.6.2.2 Implementation of the Requirements The above Requirement is implemented by Nuclear Administrative and Technical Manual procedures.
ODCM Rev. 20 90
* 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 6-1 shall be followed, including analysis of control samples.71 ODCM Rev. 20 63 Requirement:
Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 6-1, as applicable.
Applicability:
At all times.Action: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.63.1 Surveillance Requirements
: a. A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the methodology and parameters in this manual shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.63.2 Implementation of the Requirements PVNGS laboratories or contract laboratories which perform analyses for the Radiological Environmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program. The participation includes all of the determinations (sample medium-radionuclide combinations) that are included in the monitoring program.If deviation from specified limits is identified an investigation is made to determine the reason for the deviation and corrective actions are taken as necessary.
The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report.72 ODCM Rev. 20 I TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE SAMPLE NOTE DESIGNATION SITE TYPE (d) (a) LOCATION DESCRIPTION (c)1 TLD SUP E30 Goodyear 2 TLD SUP ENE24 Scott-Libby School 3 TLD SUP E21 Liberty School 4 TLD SUP E16 Buckeye 4 Air SUP E16 Same as TLD S TLD (b) SP ESE1 1 Palo Verde School 6 TLD (b) Control SSE31 APS Gila Bend substation 6A Air (b) Control SSE13 Old US 80 7 TLD (b) SP SE7 Old US 80 and Arlington School Rd.7A Air SUP ESE3 Arlington School 8 TLD (b) OR SSE4 Southern Pacific Pipeline Rd.9 TLD (b) OR S5 Southern Pacific Pipeline Rd.10 TLD (b) OR SE5 355th Ave. and Elliot Rd.11 TLD (b) OR ESE5 339th Ave. and Dobbins Rd.12 TLD (b) OR E5 339th Ave. and Buckeye-Salome Rd.13 TLD (b) IR N1 N site boundary 14 TLD (b) IR NNE2 NNE site boundary 14A Air (b) NNE2 371st Ave. and Buckeye-Salome Rd.15 TLD (b) IR NE2 NE site boundary, WRF access road 15 Air (b) NE2 Same as TLD 16 TLD (b) IR ENE2 ENE site boundary 17 TLD (b) JR E2 E site boundary 17A Air SUP E3 351st Ave.18 TLD (b) IR ESE2 ESE site boundary 19 TLD (b) IR SE2 SE site boundary 20 TLD (b) IR SSE2 SSE site boundary 73 ODCM Rev. 20 TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE SAMPLE NOTE DESIGNATION SITE TYPE (d) (a) LOCATION DESCRIPTION (c)21 TLD (b) IR S3 S site boundary 21 Air SUP S3 Same as TLD 22 TLD (b) IR SSW3 SSW site boundary 23 TLD (b) OR W5 N of Elliot Rd 24 TLD (b) OR SW4 N of Elliot Rd.25 TLD (b) OR WSW5 N of Elliot Rd.26 TLD (b) OR SSW4 Duke Property 27 TLD (b) IR SWi SW site boundary 28 TLD (b) IR WSW1 WSW site boundary 29 TLD (b) IR WI W site boundary 29 Air (b) WI Same as TLD 30 TLD (b) IR WNWI WNW site boundary 31 TLD (b) IR NWI NW site boundary 32 TLD (b) IR NNW1 NNW site boundary 33 TLD (b) OR NW4 S of Buckeye Rd.34 TLD (b) OR NNW5 395th Ave. and Van Buren St.35 TLD (b) SP NNW8 Tonopah 35 Air SUP NNW8 Same as TLD 36 TLD (b) OR N5 Wintersburg Rd. and Van Buren St.37 TLD (b) OR NNE5 363rd Ave. and Van Buren St.38 TLD (b) OR NE5 355th Ave. and Buckeye Rd.39 TLD (b) OR ENE5 343rd Ave. N of Broadway Rd.40 TLD (b) SP N2 Wintersburg 40 Air (b) N2 Same as TLD 41 TLD SUP ESE3 Arlington School 42 TLD (b) SP N8 Ruth Fisher School 44 TLD (b) Control ENE35 El Mirage 74 ODCM Rev. 20 TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE SAMPLE NOTE DESIGNATION SITE TYPE (d) (a) LOCATION DESCRIPTION (c)SUP Transit 45 TLD Control ONSITE Central lab, lead pig 46 TLD (b) SP ENE30 Litchfield Park School 46 Water (b) WD NW9 Local farm 47 TLD SUP E35 Littleton School 47 Vegetation (b) ESE4 Local residence 48 TLD SUP E24 Jackrabbit Trail 48 Water (b) WD SWi Local residence 49 TLD SUP ENEI 1 Palo Verde Rd.49 Water (b) WD N2 Local residence 50 TLD (b) OR WNW5 S of Buckeye-Salome Rd.51 Milk (b) NE4 Local residence (goats)52 Vegetation (b) NNE2 Local residence 53 Milk (b) Control NE36 Local residence (goats)54 Milk (b) NNE4 Local residence (goats)WD 55 Water SUP SW3 Local residence Ground Water 57 (b) WG onsite Well 27ddc Ground Water 58 (b) WG onsite Well 34abb Surface Water 59 (b) WS onsite Evaporation Pond #1 Surface Water 60 (b) WS onsite Reservoir 62 Vegetation (b) Control ENE26 Commercial produce company Surface Water 63 (b) WS onsite Evaporation Pond #2 I 75 ODCM Rev. 20 NOTES: (a) Distance and direction are relative to the Unit 2 containment, rounded to the nearest mile.(b) These samples fulfill the requirements of the ODCM, Table 6-1.(c) Refer to Figure 6-1 and Figure 6-2 for relative locations of sample sites.(d) IR -inner ring OR -outer ring SP -school or population center WS -waterborne surface WG -waterborne ground WD -waterborne drinking SUP -designated supplemental sampling location 76 ODCM Rev. 20 Graphic Scale In Miles d 0 1 2 3 4 5 , v .[NNE-1 ~ f T C I -1E e7 NW ~x ~-~ ~ Ib7-WNW Palo Verde Nuclear Generating Station Figure 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-10 MILES 77 ODCM Rev. 20
-r F T 9IL W I L-__-----
_Poe vwft.. .......1:v.:H::s:yampa
*' u~9ts ' -W U IId NE P-m A 'Graphic Scale In Milest 1 0 1 2 3 4 NAL -T .E Hom~~ Rd-_ _c FkiS 14M. Ad._Iw B2""Pd.I I_ J-21"* Ad, 1 C.I ,I , Li...I I.\, , ,..... E r mSurpris I I ThwdSi .~I',"I 4 W N I.\l ' I I;OzI Ade PI..*
* Glendale LIM ii -PHOENIX 10-I I--- I -I --I -00 0 0 PO 0!-4 tdF n { I %>X >4- dl0L~ C04l I1,-j ,I % 1 Rd% % 1 35 Miles illes 30 Miles 1e4 3Miles l tem V810 I V*fft I I I I ESI/ 20 Miles KEY TO MAP I i I I Railroad ..Palo Verde Nuclear AirstripAlrport
-Generating Station iiBoundary t Schools Located T ThDrmolumina( t RD)Sample Se* Near Sample Sites m T V vagetleon* Municipal Buildings A Air Sample M PMh Palo Verde Nuclear Generating Station Figure 6-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-35 MILES Figure 6-3 DELETED 79 ODCM Rev. 20 OffsIte Dose Calculation Manual Palo Verde Nuclear Generating Station Offslte Dose Calculation Manual Palo Verde Nuclear Generating Station itersburg Road Buckeye-Salome Road B Met Tower-6 Unit 1 Unit 2 Unit 3 North C Legend 4, Centerline of Containment Prperoy Purchased Exclusion Boundary-Site Boundary Elliot Road (Ward Road)Ppety Purchased Outside Exdhion Area Figure 6-4 SITE EXCLUSION AREA BOUNDARY Scale (miles)0 80 ODCM Rev. 20 Olisite Dose Calculation Manual Palo Verde Nuclear Genemtlng Station Offsite Dose Calculation Manual Palo Vterde Nuclear Generating Station Fuel Building Exhaust Main Steam Support Structure Condenser Vacuum Combined Exhaust Fuel Rulili Containment Turbine Building Operations Support Building.. i., , I ,-i, ....., -i --, , z -,-, i I ..': :i '.1 .2 I -:--00 0-Z7 Spray Pond ^Auxiliary Building It Radwaste Building Control Building Diesel Gen Building Elevation of Exhaust PoInt Above Grade Plant Ven tCondenser Vacuum 145 Fuel Building*
109,.9u Palo Verde Nuclear Generating Station Figure 6-5 GASEOUS EFFLUENTS RELEASE POINTS Offsihe Dose Calculation Manual Palo Verde Nuclear Generating Station Graphic Scale In MilseF 0 1 2 1 4 9i KEY TO MAP Paved Road Palo Verde Nuclear-Unpaved Road Generating Station 4WD Road Boundary HOI-IGI--
Gas Pipeline School 0 ol--o- Oil Pipeline-T-Tl -Power Une
* Siren I-I-I Railroad M Milepost 4f Airstrip 82 ODCM Rev. 20  


===7.0 RADIOLOGICAL===
B-6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
The Radiological Environmental Monitoring Program required by this requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. 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. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. 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 (LLD). The LLDs required by Table 6-3 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 posteriri (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 (revised annually).
B-6.2  LAND USE CENSUS This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/n12.
B-6.3  INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
91                                    ODCM Rev. 20


REPORTS 7.1 Requirement:
APPENDIX C DEFINITIONS Note:
Annual Radioactive Effluent Release Report *Routine Annual Radioactive Effluent Release Reports covering the operation of the units during the previous calendar year shall be submitted in accordance with Technical Specification 5.6.3.The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.The Annual 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**.
The following definitions were derived from the Palo Verde Nuclear Generating Station Technical Specifications. These selected definitions support those portions of the Technical Specifications which were transferred to the ODCM and have been incorporated into the Requirements sections of the ODCM.
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 6-4) 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. 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 the ODCM.The Annual 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.
Definitions:
Acceptable methods for calculating the dose contributions are given Section 5.0 and Regulatory Guide 1.109 Rev. 1, October 1977.The Annual Radioactive Effluent Release Report shall also include information required by the Technical Requirements Manual, Section 5.0.600.1.
The defined terms of this section appear in capitalized type and are applicable throughout the Requirements sections of this ODCM.
* A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.** In lieu of submission with the Annual 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.83 ODCM Rev. 20 The Annual Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period: a. Container volume, b. Total curie quantity (specify whether determined by measurement or estimate), c. Principal radionuclides (specify whether determined by measurement or estimate), d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).
ACTION ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.
The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.Changes to the ODCM shall be submitted in the form of a complete, legible copy as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Changes made to the Process Control Program shall be submitted with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the Process Control Program was made.84 ODCM Rev. 20 72 Requirement:
Annual Radiological Environmental Operating Report *Routine Annual Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted by May 15 of each year in accordance with Technical Specification 5.6.2.The Annual Radiological Environmental Operating Reports 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, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of land use censuses required by Section 6.2.The Annual Radiological Environmental Operating Reports 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 specified in Table 6-4 and Figure 6-1 and Figure 6-2 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 reports shall also include the following:
a summary description of the radiological environmental monitoring program; at least two legible maps** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Section 6.3; discussion of all deviations from the sampling schedule of Table 6-1; and discussion of all analyses in which the LLD required by Table 6-3 was not achievable.
* A single submittal may be made for a multiple unit station.** One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.85 ODCM Rev. 20 APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses.The determination of a controlling location for implementation of IOCFR50 for radioiodines and particulates is known to be a function of: (1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Equation 5-2 results in the respective equations at the controlling location.
The isotopic release rates are based upon the source terms calculated using the PVNGS Environmental Report, Operating License Stage, Table 3.5-12, without carbon.All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated.
These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure.
An infant is assumed to be present at all milk pathway locations.
A child is assumed to be present at all vegetable garden locations.
The ground plane exposure pathway is only considered to be present where an infant is not present. Naturally, inhalation is present everywhere an individual is present.For the determination of the controlling locations, the highest X/Q and D/Q values, based on the 9 year meteorological data base, for the vegetable garden, cow milk, and goat milk pathways, are selected for each unit. The receptor organ doses have been calculated at each of these locations.
Based upon these calculations, it is determined that the controlling receptor pathway is a function of unit location.
For Unit 1, the controlling receptor is a garden-child pathway; for releases from Unit 2 and Unit 3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table 4-16, 4-17, or 4-18, which, in turn, is based upon the 1984 Land Use Census. Locations of the nearest residences, gardens and milk animals, as determined in the 1984 Land Use Census, are given in Table 4-16, 4-17, and 4-18.86 ODCM Rev. 20 APPENDIX B BASES FOR REQUIREMENTS B-2.1 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 the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, 64 of Appendix A to 10 CFR PART 50.There are two separate radioactive gaseous effluent monitoring systems: the low range effluent monitors for normal plant radioactive gaseous effluents and the high range effluent monitors for post-accident plant radioactive gaseous effluents.
The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions.
The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the low range monitors.B-3.1 GASEOUS EFFLUENT -DOSE RATE This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY, in excess of the design objectives of Appendix I to 10 CFR part 50. This requirement is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled.
It provides operational flexibility for releasing gaseous effluents to satisfy the Section H.A and l.C design objectives of Appendix I to 10 CFR part 50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a 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 mremslyear to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.
This requirement does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).
This requirement applies to the release of radioactive materials in gaseous effluents from all reactor 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 (LLD). 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 (revised annually).
87 ODCM Rev. 20 B-3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS -CONCENTRATION This requirement is provided to ensure that the annual total effective dose equivalent to individual members of the public from the licensed operation does not exceed the requirements of 10 CFR Part 20, due to the accumulated activity in the evaporation ponds from the secondary system discharges.
Restricting the concentrations of the secondary liquid wastes discharged to the onsite evaporation ponds will restrict the quantity of radioactive material that can accumulate in the ponds. This, in turn, provides assurance that in the event of an uncontrolled release of the pond's contents to an UNRESTRICTED AREA, the resulting total effective dose equivalent to individual members of the public at the nearest exclusion area boundary will not exceed the requirements of 10 CFR Part 20.This requirement applies to the secondary system liquid waste discharges of radioactive materials from all reactor units to the onsite evaporation ponds.The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD). 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 (revised annually).
B-4.1 GASEOUS EFFLUENT -DOSE, Noble Gases This requirement is provided to implement Sections ll.B, Il.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section Il.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and 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 the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous 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 10 CFR Part 50, 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 and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.88 ODCM Rev. 20 B-4.2 GASEOUS EFFLUENT -DOSE -Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days This requirement is provided to implement the requirements of Sections II.C, III.A, IV.A of Appendix I, 10 CFR Part 50. This requirement is the guide set forth in Section ll.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 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 IIl.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1. 111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases for 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 specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY.
The pathways that were examined in the development of these 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 requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.B-4.3 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix 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 H.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.The minimum analysis frequency of 4/M (i.e., at least 4 times per month at intervals no greater than 9 days and a minimum of 48 times a year) is used for certain radioactive gaseous waste sampling in Table 3-1. This will eliminate taking double samples when quarterly and weekly samples are required at the same time.89 ODCM Rev. 20 B-4A SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS -DOSE This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section M.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IVA of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by 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 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section lII.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.This requirement applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.B-5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE This requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.1301(d).
The requirement specifies the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Even if a site was to contain up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units (including outside storage tanks, etc.)are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a 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, submittal of the Special Report within 30 days 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 Part 190.11 and 10 CFR Part 20.2203(a)(4), 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 other requirements for dose limitation of 10 CFR Part 20, as addressed in Section 3.2 and 3.1 of the ODCM. 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 20.1301.90 ODCM Rev. 20 B-6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)The Radiological Environmental Monitoring Program required by this requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.
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.
Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
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 (LLD). The LLDs required by Table 6-3 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 posteriri (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 (revised annually).
B-6.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program 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/n1 2.B-6.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.91 ODCM Rev. 20 APPENDIX C DEFINITIONS Note: The following definitions were derived from the Palo Verde Nuclear Generating Station Technical Specifications.
These selected definitions support those portions of the Technical Specifications which were transferred to the ODCM and have been incorporated into the Requirements sections of the ODCM.Definitions:
The defined terms of this section appear in capitalized type and are applicable throughout the Requirements sections of this ODCM.ACTION ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.
CHANNEL CALIBRATION See the Technical Specification definition.
CHANNEL CALIBRATION See the Technical Specification definition.
CHANNELCHECK See the Technical Specification definition.
CHANNELCHECK See the Technical Specification definition.
CHANNEL FUNCTIONAL TEST See the Technical Specification definition.
CHANNEL FUNCTIONAL TEST See the Technical Specification definition.
DOSE EQU1IVALENT I-131 See the Technical Specification definition.
DOSE EQU1IVALENT I-131 See the Technical Specification definition.
EREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table C-1.GASEOUS RADWASTE SYSTEM A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
EREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table C-1.
MEMBER(S)
GASEOUS RADWASTE SYSTEM A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
OF THE PUBLIC MEMBER(S)
MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant.
OF THE PUBLIC shall include all persons who are not occupationally associated with the plant.This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.92 ODCM Rev. 20 APPENDIX C DEFINITIONS (Continued)
92                                     ODCM Rev. 20
 
APPENDIX C DEFINITIONS (Continued)
OPERABLE-OPERABuLThY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).
OPERABLE-OPERABuLThY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).
MODE See the Technical Specification definition.
MODE See the Technical Specification definition.
PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.PREPURGING 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 condition, in such a manner that replacement air or gas is required to purify the confinement.
PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
PREPURGING 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 condition, in such a manner that replacement air or gas is required to purify the confinement.
AT1EI THERMAL POWER See the Technical Specification definition.
AT1EI THERMAL POWER See the Technical Specification definition.
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
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.
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.93 ODCM Rev. 20 APPENDIX C DEFINITIONS (Continued)
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTE.D AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT 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.
93                                     ODCM Rev. 20
Such a system is not considered to have any effect on noble gas effluents.
 
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
APPENDIX C DEFINITIONS (Continued)
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.94 ODCM Rev. 20 TABLE C-1 FREQUENCY NOTATION NOTATION S D w 4/M M Q SA ANNUALLY R p S/U N.A.FREQUENCY At least once per 12 hours.At least once per 24 hours.At least once per 7 days.At least 4 times per month at intervals no greater than 9 days and a minimum of 48 times per year.At least once per 31 days.At least once per 92 days.At least once per 184 days.At least once per 365 days At least once per 18 months.Completed prior to each release.Prior to reactor startup.Not Applicable.
UNRESTRICTE.D AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
95 ODCM Rev. 20 APPENDIX D REFERENCES 1 Title 10, Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation." 2 Title 10, Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities." 3 Title 40, Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations." 4 Federal Register, Vol. 58, No. 245, Thursday, December 23, 1993, Notices, pages 68170-68179.
VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT 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. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
5 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 1974.6 Regulatory Guide 1.109, "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," Revision 1, October 1977.7 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 1977.8 Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.9 NUREG-0133, Preparation of Radiological Effluent Technical Specifications For Nuclear Power Plants, Oct. 1978.10 NUREG 0841, "Final Environmental Statement Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3", Section 5.9.1.4, February, 1982.11 NUREG-1301, "Offsite Dose Calculation Manual Guidance:
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.
Standard Radiological Effluent Controls for Pressurized Water Reactor", Arpil 1991.12 Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station, December 1981.13 PVNGS Updated Final Safety Analysis Report 14 Calculation 13-NC-ZY-252, "Annual Average Dose from Normal Operation Liquid Discharge from the Evaporation Pond", Rev 0.15 Calculation 13-NC-ZY-253, "Annual Average Dose from Normal Operation Airborne Direct and Sky Shine from the Evaporation Pond", Rev 0.16 Calculation 13-NC-ZY-254, "Radiation Dose Due to an Evaporation Pond Dike Failure During a Seismic Event", Rev. 0.96 ODCM Rev. 20}}
94                                     ODCM Rev. 20
 
TABLE C-1 FREQUENCY NOTATION NOTATION                       FREQUENCY S   At least once per 12 hours.
D    At least once per 24 hours.
w    At least once per 7 days.
At least 4 times per month at intervals no greater than 4/M  9 days and a minimum of 48 times per year.
M    At least once per 31 days.
Q  At least once per 92 days.
SA  At least once per 184 days.
ANNUALLY At least once per 365 days R  At least once per 18 months.
p  Completed prior to each release.
S/U  Prior to reactor startup.
N.A. Not Applicable.
95                                     ODCM Rev. 20
 
APPENDIX D REFERENCES 1   Title 10, Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation."
2   Title 10, Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities."
3   Title 40, Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations."
4   Federal Register, Vol. 58, No. 245, Thursday, December 23, 1993, Notices, pages 68170-68179.
5   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.
6   Regulatory Guide 1.109, "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,"
Revision 1, October 1977.
7   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.
8   Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
9   NUREG-0133, Preparation of Radiological Effluent Technical Specifications For Nuclear Power Plants, Oct. 1978.
10 NUREG 0841, "Final Environmental Statement Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3", Section 5.9.1.4, February, 1982.
11 NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactor", Arpil 1991.
12 Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station, December 1981.
13 PVNGS Updated Final Safety Analysis Report 14 Calculation 13-NC-ZY-252, "Annual Average Dose from Normal Operation Liquid Discharge from the Evaporation Pond", Rev 0.
15 Calculation 13-NC-ZY-253, "Annual Average Dose from Normal Operation Airborne Direct and Sky Shine from the Evaporation Pond", Rev 0.
16 Calculation 13-NC-ZY-254, "Radiation Dose Due to an Evaporation Pond Dike Failure During a Seismic Event", Rev. 0.
96                                     ODCM Rev. 20}}

Latest revision as of 06:50, 14 March 2020

Appendix D, Offsite Dose Calculation Manual Revision 20
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APPENDIX D OFFSITE DOSE CALCULATION MANUAL Revision 20 95 PVNGS ARERR 2005

OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 REVISION 20 Originator Louis Drinovsky -- Date: _ _

Tech. Reviewer Kevin Kutner Date:

Director, Radiation Protection John Gaffney Date:

PRB John Hesser Date:

Effective Date: August 31, 2005

TABLE OF CONTENTS TITLE PAGE

1.0 INTRODUCTION

1 1.1 Liquid Effluent Pathways I 1.2 Gaseous Effluent Pathways 2 1.3 Nuisance Pathways 2 1.4 Meteorology 4 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS 5

2.1 Requirements

Gaseous Monitors 5 2.1.1 Surveillance Requirements 5 2.1.2 Implementation of the Requirements 12 2.1.2.1 Equivalent Dose Factor Determination 13 2.1.2.2 Site Release Rate Limit (QsrrF) 14 2.1.2.3 Unit Release Rate Limits (QUNIT) 15 2.1.2.4 Setpoint Determination 15 2.1.2.5 Monitor Calibration 16 3.0 GASEOUS AND LIQUID EFFLUENT DOSE RATES 17

3.1 Requirements

Gaseous Effluents 17 3.1.1 Surveillance Requirements 17 3.1.2 Implementation of the Requirements 18

3.2 Requirements

Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System - Concentration 26 3.2.1 Surveillance Requirements 26 3.2.2 Implementation of the Requirements 26 4.0 GASEOUS & LIQUID EFFLUENTS - DOSE 31

4.1 Requirements

Noble Gases 31 4.1.1 Surveillance Requirements 31 4.1.2 Implementation of the Requirement: Noble Gas 32

4.2 Requirement

Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 33 4.2.1 Surveillance Requirements 33 4.2.2 Implementation of the Requirement 34

4.3 Requirements

Gaseous Radwaste Treatment 36 4.3.1 Surveillance Requirements 36 4.3.2 Implementation of the Requirement 37 4A Requirements: Liquid Effluents 57 4.4.1 Surveillance Requirements 57 4.4.2 Implementation of the Requirements 57 i ODCM Rev. 20

TABLE OF CONTENTS TITLE PAGE 5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 58

5.1 Requirement

Total Dose 58 5.1.1 Surveillance Requirements 58 5.1.2 Implementation of the Requirement 58 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 62

6.1 Requirement

REMP 62 6.1.1 Surveillance Requirements 63 6.1.2 Implementation of the Requirements 63

6.2 Requirement

Land Use Census 71 6.2.1 Surveillance Requirements 71 6.2.2 Implementation of the Requirements 71

6.3 Requirement

Interlaboratory Comparison Program 72 6.3.1 Surveillance Requirements 72 6.3.2 Implementation of the Requirements 72 7.0 RADIOLOGICAL REPORTS 83

7.1 Requirement

Annual Radioactive Effluent Release Report 83

7.2 Requirement

Annual Radiological Environmental Operating Report 85 APPENDIX A DETERMINATION OF CONTROLLING LOCATION 86 APPENDIX B BASES FOR REQUIREMENTS 87 2.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 87 3.1 GASEOUS EFFLUENT - DOSE RATE 87 3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - CONCENTRATION 88 4.1 GASEOUS EFFLUENT - DOSE, Noble Gases 88 4.2 GASEOUS EFFLUENT - DOSE - Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days89 4.3 GASEOUS RADWASTE TREATMENT 89 4.4 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - DOSE 90 5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 90 6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 91 6.2 LAND USE CENSUS 91 6.3 INTERLABORATORY COMPARISON PROGRAM 91 APPENDIX C DEFINITIONS 92 APPENDIX D REFERENCES 96 ii ODCM Rev. 20

LIST OF TABLES TABLE TITLE PAGE 1-1 NUISANCE PATHWAYS 3 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 6 2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 10 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 20 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY 23 3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 24 3-4 Pi VALUES FOR THE INHALATION PATHWAY 25 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 27 3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 30 3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 30 4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY 39 4-2 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - ADULT RECEPTOR 40 4-3 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - TEEN RECEPTOR 41 4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR 42 4-5 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - ADULT RECEPTOR 43 4-6 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - TEEN RECEPTOR 44 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILD RECEPTOR 45 4-8 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - ADULT RECEPTOR 46 4-9 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEEN RECEPTOR 47 4-10 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - CHILD RECEPTOR 48

.. . ODCM Rev. 20

LIST OF TABLES TABLE TITLE PAGE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR 49 4-12 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - ADULT RECEPTOR 50 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -TEEN RECEPTOR 51 4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILD RECEPTOR 52 4-15 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTOR 53 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 1 54 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 55 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 56 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 64 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 68 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS 69 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS 73 C-1 FREQUENCY NOTATION 95 iv ODCM Rev. 20

LIST OF FIGURES FIGURE TITLE PAGE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-10 MILES 77 6-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-35 MILES 78 6-3 DELETED 79 6-4 SITE EXCLUSION AREA BOUNDARY 80 6-5 GASEOUS EFFLUENTS RELEASE POINTS 81 6-6 LOW POPULATION ZONE 0-5 MILES 82 v ODCM Rev. 20

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) implements the program elements which are required by the Administrative Controls section of the Technical Specifications. The ODCM contains the operational requirements, the surveillance requirements, and actions required if the operational requirements are not met for the Radioactive Effluent Controls Program and the Radiological Environmental Monitoring Program to assure compliance with 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. The Technical Specifications, Section 3.0, also apply to the ODCM. Substitute the word "Requirements" for "Limiting Condition for Operation." It should be noted that the hot and cold shutdown and operability requirements in Technical Specification 3.0.3 and 3.0.4 do not apply to any of the requirements contained in this ODCM. The ODCM also contains descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by the Technical Specifications.

The ODCM provides the parameters and methodology to be used in calculating offsite doses resulting from radioactive effluents, in the calculation of gaseous effluent monitor Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. Included are methods for determining air, whole body, and organ dose at the controlling location due to plant effluents to assure compliance with the regulatory requirements detailed in the ODCM. Methods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the ODCM. The ODCM utilizes information from NRC Regulatory Guide 1.109, "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," October 1977, and NRC NUREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978. NUREG 0133 utilizes some of the key information in Regulatory Guide 1.109 to provide methods which were used in the preparation of the radiological effluent Technical Specifications and which have now been transferred to the ODCM in accordance with NRC Generic Letter 89-01, "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," January 31, 1989, and NUREG 1301, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01, Supplement No. 1, April 1991. Further guidance for the implementation of the new 10 CFR Part 20, effective January 1, 1994, was obtained from the Federal Register, Vol. 58, December 23, 1993. It is recognized that this is only draft guidance, however, it is the only guidance for referencing the new 10 CFR 20 in the ODCM.

1.1 Liquid Effluent Pathways Dose calculation methodology for radioactive liquid effluents is not included in this manual due to the desert location of the plant, the hydrology of the area, and the fact that there are no liquid releases to areas at or beyond the SITE BOUNDARY during normal operation. All liquid discharges to the onsite evaporation ponds are controlled by Section 3.2. The impact of postulated accidental seepages on the groundwater system, and in particular on the existing wells located in the 5-mile zone around the site area has been calculated and analyzed in Section 2.4.13.3 of the PVNGS FSAR.

If plant operating conditions become such that the likelihood of a liquid effluent pathway is created, then dose calculation methodology for this pathway will be added to this manual.

I ODCM Rev. 20

12 Gaseous Effluent Pathways All gaseous effluents are treated as ground level releases and are considered to be "long-term" as discussed in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." This includes the containment purge and Waste Gas Decay Tank releases as well as the normal ventilation system and condenser vacuum exhaust releases. All releases are either greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in duration or are made at random, not depending upon atmospheric conditions or time of day. The releases are lumped together and calculated as an entity. Historical annual average X/Q values are used throughout this manual for all gaseous effluent setpoint and dose calculations. Airborne releases are further subdivided into two subclasses:

1.2.1 Iodine-131, Iodine-133, Tritium and Radionuclides In Particulate Form with Half-lives Greater than Eight Days In this model, a controlling location is identified for assessing the maximum exposure to a MEMBER OF THE PUBLIC for the various pathways and to critical organs. Infant exposure occurs through inhalation and any actual milk pathway. Child, teenager and adult exposure derives from inhalation, consumed vegetation pathways, and any actual milk and meat pathways. Dose to each of the seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung and GI-LLI) are computed from individual nuclide contributions in each sector. The largest of the organ doses in any sector is compared to 10 CFR 50, Appendix I design objectives. The release rates of these nuclides will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.

1.2.2 Noble Gases The air dose from both the beta and gamma radiation component of the noble gases will be assessed and compared to the 10 CFR 50, Appendix I design objectives. The noble gas release rate will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.

Section 2.0 of this manual discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to assure compliance with the 10 CFR Part 20 limits as implemented in Section 3.0. Section 4.0 discusses the methods to assure releases are As Low As Reasonably Achievable (ALARA) in accordance with Appendix I to 10 CFR Part 50.

Methods are described in Section 5.0 for determining the annual cumulative dose to a MEMBER OF THE PUBLIC from gaseous effluents and direct radiation to assure compliance with 40 CFR Part 190.

The requirements for the Annual Radiological Effluent Release Report and the Radiological Environmental Monitoring Program, including the Annual Land Use Census and the Interlaboratory Comparison Program, and the Annual Environmental Report are described in Sections 6.0 and 7.0 of this manual.

13 Nuisance Pathways This section addresses the potential release pathways which should not contribute more than 10% of the doses evaluated in this manual. Table 1-1 lists examples of potential release pathways. The ODCM methodology for calculation of doses will be applied to an applicable release pathway if a likely potential arises for contributing more than 10% of the doses evaluated in this manual.

2 ODCM Rev. 20

TABLE 1-1 NUISANCE PATHWAYS (EXAMPLES)

Evaporation Pond Cooling Towers Laundry/Decon Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents Dry Active Waste Processing and Storage (DAWPS) Building Respirator Cleaning Facility Secondary Side Decontamination Equipment Low Level Radioactive Material Storage Facility 3 ODCM Rev. 20

1A Meteorology Historical annual average atmospheric dispersion (X/Q) and deposition (D/Q) data, based on nine years of meteorological data, and given in Table 3-2 for each of the three nuclear generating units are used to demonstrate compliance with the ODCM Requirements. These Requirements include:

Section 2.0 Gaseous Effluent Monitor Setpoints; Section 3.0 Gaseous and Liquid Effluent - Dose Rate Section 4.0 Gaseous and Liquid Effluent - Dose Section 5.0 Total Dose and Dose to Public Onsite Sections 2.0 and 3.0 specify utilizing the highest X/Q or D/Q meteorological dispersion parameter at the Site Boundary for any of the three units as applicable. Using the highest dispersion parameter for any of the units provides a conservative assumption to assure compliance with the higher 10 CFR Part 20 limits.

Section 4.0 specifies utilizing the highest X/Q at the Site Boundary for the particular unit, from Table 3-2 for noble gases. The highest XIQ and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathway's location (site boundary using Table 3-2 or other controlling locations using Table 4-16, 4-17, or 4-18).

Section 5.0 specifies utilizing the highest X/Q for the particular unit's releases at the controlling location from Table 4-16,4-17, or 4-18, for noble gases. The highest X/Q and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases at the controlling pathway's location using Table 4-16, 4-17, or 4-18.

Section 7.0 requires that 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.

4 ODCM Rev. 20

2.0 GASEOUS EFFLUENT MONITOR SETPOINTS

2.1 Requirements

Gaseous Monitors The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.0 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 2.1.2.

Applicability: As shown in Table 2-1.

Action:

a. With the low range radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Requirement, 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 2-1. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

2.1.1 Surveillance Requirements

a. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2.

5s ODCM Rev. 20

TABLE 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. GASEOUS RADWASTE SYSTEM
a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release #RU- 12 35
b. Flow Rate Monitor 36
2. NOT USED
3. DELETED
4. PLANT VENT SYSTEM A. Low Range Monitors ON
a. Noble Gas Activity Monitor #RU-143
  • 37
b. Iodine Sampler
  • 40
c. Particulate Sampler 40
d. Flow Rate Monitor
  • 36
e. Sampler Flow Rate Measuring Device
  • 36 B. High Range Monitors
a. Noble Gas Activity Monitor #RU-144
  • 42
b. Iodine Sampler
  • 42 C c. Particulate Sampler
  • 42
d. Sampler Flow Rate Measuring Device
  • 42 0

TABLE 2-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

5. FUEL BUILDING VENTILATION SYSTEM A. Low Range Monitors
a. Noble Gas Activity Monitor #RU- 145 1 37,41
b. Iodine Sampler 1 ## 40
c. Particulate Sample 1 #4 40
d. Flow Rate Monitor 1 ## 36
e. Sampler Flow Rate Measuring Device 1 ## 36 B. High Range Monitors
a. Noble Gas Activity Monitor #RU-146 1 ## 42
b. Iodine Sampler 1 4* 42
c. Particulate Sample 1 ## 42
d. Sampler Flow Rate Measuring Device 1 #I 42 0

to 0

Table 2-1 (Continued)

TABLE NOTATION

  • At all times.
    • During GASEOUS RADWASTE SYSTEM operation
      • Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).
  1. During waste gas release.
    1. In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.

ACTION 35 - 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. At least two independent samples of the tanks contents are analyzed, and
b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - 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 />.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the actions of (a) or (b) or (c) are performed:

a. Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s).
b. Place moveable air monitors in-line.
c. Either take grab samples at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, OR obtain gas channel monitor readings locally at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if the channel is functional locally but inoperable due to loss of communication with the minicomputer. The surveillance requirements of Section 2.1.1 must be performed at the required frequencies for the channel to be functional locally.

ACTION 38 - NOT USED ACTION 39 - NOT USED ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 3-1 within one hour after the channel has been declared inoperable.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, comply with Technical Requirements Manual TLCO 3.3.108.

8 ODCM Rev. 20

Table 2-1 (Continued)

TABLE NOTATION ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement restore the channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or:

a. Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) when it is needed.
b. Prepare and submit a Special Report to the Commission within 30 days following the event outlining the action(s) taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

9 ODCM Rev. 20

TABLE 2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED

1. GASEOUS RADWASTE SYSTEM
a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release RU-12 p P(7) R(3) Q(I),(2),P####
b. Flow Rate Monitor P N.A. R Q,P###
2. DELETED
3. DELETED
4. PLANT VENT SYSTEM (RU-143 and RU-144) 0 *
a. Noble Gas Activity Monitor D(5) M(7) R(3) Q(2)
b. Iodine Sampler N.A. N.A. N.A. N.A.
c. Particulate Sampler N.A. N.A. N.A. N.A.
d. Flow Rate Monitor D(6) N.A. R Q
e. Sampler Flow Rate Measuring Device D(6) N.A. R Q
5. FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)
a. Noble Gas Activity Monitor D(5) M(7) R(3) Q(2)
b. Iodine Sampler N.A. N.A. N.A. N.A.

0 c. Particulate Sample N.A. N.A. N.A. N.A.

d. Flow Rate Monitor D(6) N.A. R Q 0
e. Sampler Flow Rate Measuring Device D(6) N.A. R Q

Table 2-2 (Continued)

TABLE NOTATION

  • At all times.
    • During GASEOUS RADWASTE SYSTEM operation
      • Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).
  1. During waste gas release.
    1. In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.
      1. Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

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

1. Instrument indicates measured levels above the alarm setpoint.
2. Circuit failure.
3. Instrument indicates a downscale failure.
4. Instrument controls not set in operate mode.

(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 may be used in lieu of the reference standards associated with the initial calibration.

(4) NOT USED (5) The channel check for channels in standby status shall consist of verification that the channel is on-line and reachable.

(6) Daily channel check not required for flow monitors in standby status.

(7) LED may be utilized as the check source in lieu of a source of increased activity.

I1I ODCM Rev. 20

2.1.2 Implementation of the Requirements The general methodology for establishing low range gaseous effluent monitor setpoints is based upon a site release rate limit in iLCO/sec derived from site specific meteorological dispersion conditions, radioisotopic distribution, and whole body and skin dose factors. The high alarm of the low range monitors will alarm/trip when the release rate from an individual vent will result in exceeding the limits in Section 3.1. 80% of Section 3.1 limits is considered to be the site release rate limit. The site release rate limit will be allocated among the licensed units' release points. The unit release rate limit will then be utilized for the determination of gaseous effluent monitor setpoints. A fraction of the unit release rate limit is then allotted to each release point and its monitor alert setpoint (gCi/cc) is derived using actual or fan design flow rates.

Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be reviewed based on actual release data.

For the purpose of implementation of Section 2.1, the alarm setpoint levels for low range effluent noble gas monitors are established to ensure that personnel are alerted when the noble gas releases are at a rate such that if the releases would continue for the year they would approach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose in Section 3.1.

The equations in Section 3.1 of this manual provide the methodology for calculating the gaseous effluent dose rate.

The evaluation of doses due to releases of radioactive material can be simplified by the use of equivalent dose factors as defined in Section 2.1.2. 1.

The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is being used for the dose equivalent value.

12 ODCM Rev. 20

2.1.2.1 Equivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows:

Keq = Ej[(Ki)(fi)] (2-1)

Where:

Keq = the equivalent whole body dose factor weighted by historical radionuclide distribution in releases in mremlyr per g+/-Ci/m 3 .

Ki = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per g Ci/m3 from Table 3-3.

fi = the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.

The equivalent skin dose factor is calculated as follows:

(L + l.lM)eq = Ei[(Li + 1-.Mi)(fi)] (2-2)

Where:

(L+1.lM)eq = the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases in mrem/yr per gCi/m 3.

Li = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per gCi/m3 from Table 3-3.

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per g+/-Ci/m 3 from Table 3-3.

fi = the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.

1.1 = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

13 ODCM Rev. 20

2.1.2.2 Site Release Rate Limit (QsrrF)

The release rates corresponding to 80% of the whole body (QWB) and skin (QSK) dose rate limits are calculated using the equivalent dose factors defined in Section 2.1.2.1.

The site release rate limit (QSffE) is the lower Of QWB or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded.

The QSrrE is established as follows:

QSITEWB (DWB)(08) (2-3)

(Keq)(X/Q)SITE Where:

QSrrE,WB = the site release rate, in jiCi/sec, that would deliver a dose rate 80% of the whole body dose rate limit, DWB.

DWB = whole body dose rate limit of 500 mrem/yr.

3 Keq = equivalent whole body dose factor, in mrem/yr per pCi/M weighted by the historical radionuclide distribution.

(X/Q)SrrE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/M3 , at the Site Boundary for any of the 3 units, from Table 3-2.

0.8 = administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.

QSIT SK = (DSK)(O. 8 ) (24)

QsIE~s =(L + 1-IM)eq(X/Q)SITE(2)

Where:

QSrrE,SK = the site release rate limit, in pCi/sec, that would deliver a dose rate 80% of the skin dose rate limit, DSK.

DSK = skin dose rate limit of 3000 mrem/yr.

3 (L+ l.lM),q = equivalent skin dose factor, in mrem/yr per glCi/m , weighted by the radionuclide distribution.

(/Q)SrrE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/n 3 , at the Site Boundary for any of the three units, from Table 3-2.

0.8 = administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.

After determination of the QSrE whole body and skin dose rates (equations 2-3 and 2-4, respectively), the most conservative result will be used as QsITE, the site release rate limit.

14 ODCM Rev. 20

2.1.23 Unit Release Rate Limits (QuNrr)

Typically QSrrE will be divided equally among operating units. If operational history dictates a larger fraction of the QsrrE be assigned to a specific unit then a weighted average of each unit's contribution to the QSrrE will be utilized to determine the QUNrr.

QUNIT = (uNrr) (QSiTE) (2-5)

Where:

QUNIT = unit release rate limit, in pCi/sec.

fUNIT = the fraction (* 1) of noble gas historically released from a specific operating unit to the total of all noble gas released from the site.

QsrrE = the site release rate limit, in gCi/sec determined in Section 2.1.2.2.

2.1.2.4 Setpoint Determination To comply with the requirements in Section 2.1, the alarm/trip setpoints can now be established using the unit release rate limit (QUNrT) to ensure that the noble gas releases do not exceed the dose rate limits.

To allow for multiple sources of releases from different or common release points, the effluent monitor setpoint includes an administrative factor which allocates a percentage of the unit release rate limit to each of the release sources. Monitor setpoints will also be adjusted in accordance with Nuclear Administrative and Technical Manual procedures to account for monitor-specific characteristics.

Monitors RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-143 and RU-145 is calculated as follows:

Monitor (QUNIT)(a)

Setpoint (472)(Flow Rate) (2-6)

Where:

Monitor Setpoint = the setpoint for the effluent monitor, in pCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.

QUNIT = unit release rate limit, in pCi/sec, as determined in Section 2.1.2.3.

Flow Rate = the flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration.

472 = conversion factor, cubic centimeter/second per cubic feet/minute.

a = fraction of QUNPr allocated for a specific release point. The sum of these administrative values shall be less than or equal to one.

15 ODCM Rev. 20

Monitor RU- 2 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:

Monitor < [(QUNIT)(a)(O. 9 ) - (H)(PF)(472)] (2-7) setpoint (Flow Rate)(472)

Where:

Monitor Setpoint = the setpoint for the monitor, in tCi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.

QUNIT = unit release rate limit, in tCilsec, as determined in Section 2.1.2.3.

Flow Rate = flow rate, in cfm at STP at which the tank will be released.

PF = the current process flow of the plant vent in CFM.

H = the current plant vent monitor concentration in pCi/cc.

a = fraction of QUNri allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.

0.9 = an administrative value to account for potential increases in activity from other contributors to the same release point.

472 = conversion factor, cubic centimeter/second per cubic feettminute.

If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms, and yet assure an alarm should an inadvertent release occur.

2.1.2.5 Monitor Calibration The Radiation Level Conversion Factor (RLF) for each monitor is entered into the Radiation Monitoring System Database and may change whenever the monitor is calibrated. Calibration is performed in accordance with Nuclear Administrative and Technical Manual procedures.

16 ODCM Rev. 20

3.0 GASEOUS AND LIQUID EFFLUENT DOSE RATES

3.1 Requirements

Gaseous Effluents The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 6-4 and Figure 6-5) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
b. For 1-131 and 1-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

Applicability: At all times.

Action:

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

3.1.1 Surveillance Requirements

a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2.
b. The dose rate due to I-131, I-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1.

17 ODCM Rev. 20

3.1.2 Implementation of the Requirements Noble Gases Noble gas activity monitor setpoints are established at release rates which permit corrective action to be taken before exceeding the 10 CFR 20 annual dose limits as described in Section 2.0. The requirements for sampling and analysis of continuous and batch effluent releases are given in Table 3-1. The methods for sampling and analysis of continuous and batch effluent releases are given in the Nuclear Administrative and Technical Manual procedures. The dose rate in unrestricted areas shall be determined using the following equations.

For whole body dose rate:

DWB = Y [(K,)(X/Q)SITE(Ql)] (3-1)

For skin dose rate:

DSK = Zj[(Lj + l.lMi)(X/Q)s1TE(Qi)] (3-2)

Where:

Ki = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per iVCi/m 3 from Table 3-3.

Qi = the release rate of radionuclide i, in CO/sec.

(X/Q)SrrE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3, for any of the three units, from Table 3-2.

DWB = the annual whole body dose rate (mrem/yr.).

Li = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per tCi/m3 from Table 3-3.

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per VCi/m 3 from Table 3-3.

DSK = the annual skin dose rate (mrem/yr).

1.1 = unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

18 ODCM Rev. 20

1-131. 1-133. tritium and radionuclides in particulate form with half-lives greater than 8 days The methods for sampling and analysis of continuous and batch releases for I-131, I-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, are given in the applicable Nuclear Administrative and Technical Manual procedures. Additional monthly and quarterly analyses shall be performed in accordance with Table 3-1. The total organ dose rate in unrestricted areas shall be determined by the following equation:

Do = Ei[(PI)(X/Q)SITE(Qi) (3-3)

Where:

Pi = the dose factor, in mrem/yr per ,pCi/m3, for radionuclide i, for the inhalation pathway, from Table 3-4.

(X/Q)SrrE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3 , at the Site Boundary, for any of the three units, Qi = the release rate of radionuclide i, in .tCi/sec Do = the total organ dose rate (mrem/yr).

19 ODCM Rev. 20

TABLE 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT SAMPLING ANALYSIS TYPE OF OF DETECTION GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (LLD) (IpCVdm)'

A. Waste Gas Storage P P Principal Gamma 1.0E-04 Each Tank Grab Each Tank Emitters9 Sample B. Containment Purge P P Principal Gamma 1.OE-04 Each Purgebc Each Purgebsc Emitters Grab Sample H-3 H-3 1.OE-06 C. 1. DELETED Mb,e Mb Principal Gamma 1.OE-04

2. Plant Vent Grab Sample Emittersg
3. Fuel Bldg. Exhaust H-3 1OE-06 Continuousf 4/Md I-131 1.OE-12 Charcoal Sample I-133 L.OE-10 continuousf 4/Md Principal Gamma .OE- II Particulate Emittersg Sample (I-13 1, Others)

Continuousf M Gross Alpha 1.OE- I1 Composite Particulate Sample Continuousf Q Sr-89, Sr-90 1.OE-l 1 Composite Particulate Sample D. All Radwaste Teypes as Continuousf Noble Gas Noble Gases Gross Beta 1.OE-06 listed in A., B., and C., Monitor or Gamma above.

20 ODCM Rev. 20

Table 3-1 (Continued)

TABLE NOTATION a The LLD is 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):

LD = 4.66 sb LL =E

  • V
  • 2.22E6
  • Y
  • exp(-XAt)

Where:

LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume). Current literature defines the LLD as the detection capability for the instrumentation only and the MDC minimum detectable concentration, as the detection capability for a given instrument, procedure and type of sample.

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

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

2.22E6 is the number of transformations per minute per microcurie, Y is the fractional radiocheniical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between the midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples. 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.

21 ODCM Rev. 20

Table 3-1 (Continued)

TABLE NOTATION b Analyses shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1-hour period if 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased more than a factor of 3; and 2) the noble gas activity monitor on the plant vent shows that effluent activity has increased by more than a factor of 3. If the associated noble gas vent monitor is inoperable, samples must be obtained as soon as possible. Analyses shall be performed within a four-hour period. This requirement does not apply to the Fuel Building Exhaust.

c Sampling and analyses shall also be performed at least once per 31 days when purging time exceeds 30 days continuous.

d Samples shall be changed at least 4 times a month 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 sampler). 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.

e Tritium grab samples shall be taken at least monthly from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f 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 Requirements 3.1, 4.1 and 4.2 of the ODCM.

g 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 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported in the Annual Radioactive Effluent Release Report.

22 ODCM Rev. 20

TABLE 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY UNIT 1 UNIT 2 UNIT 3 DISTANCE XIQ D/Q DISTANCE X/Q D/Q DISTANCE XIQ D/Q DIRECTION (METERS) (SEC/m3 ) (mw2 ) (METERS) (SEC/m3) (mr2) (METERS) (SEC/m3) (m 2)

N 1037 4.93E-06 9.24E-09 1318 3.85E-06 6.17E-09 1661 3.54E-06 4.86E-09 NNE 1057 4.14E-06 1.19E-08 1342 3.18E-06 7.93E-09 1693 2.86E-06 6.23E-09 NE 2206 2.84E-06 6.84E-09 2545 2.42E-06 5.34E-09 2756 2.21E-06 4.65E-09 ENE 1967 2.51E-06 4.43E-09 2206 2.22E-06 3.64E-09 2337 2.08E-06 3.30E-09 E 1927 2.56E-06 3.24E-09 2163 2.27E-06 2.66E-09 2290 2.14E-06 2.41E-09 ESE 1967 2.61E-06 2.46E-09 2067 2.32E-06 2.11E-09 2023 2.37E-06 2.10E-09 SE 2049 3.56E-06 2.36E-09 2101 3.47E-06 2.26E-09 2256 3.24E-06 2.00E-09 SSE 2730 3.80E-06 1.58E-09 3026 3.43E-06 1.32E-09 2786 3.72E-06 1.52E-09 S 3006 5.07E-06 1.78E-09 2699 5.16E-06 1.97E-09 2346 5.90E-06 2.51E-09 SSW 2258 6.52E-06 3.20E-09 1836 7.90E-06 4.56E-09 1607 8.91E-06 5.73E-09 SW 1487 7.47E-06 5.65E-09 1208 7.72E-06 6.88E-09 1057 8.68E-06 8.61E-09 WSW 1251 4.52E-06 5.93E-09 1014 5.55E-06 8.44E-09 889 5.34E-06 8.83E-09 W 1225 4.73E-06 9.49E-09 993 5.86E-06 1.34E-08 871 6.72E-06 1.67E-08 WNW 1244 3.76E-06 6.76E-09 1010 4.67E-06 9.60E-09 885 5.37E-06 1.19E-08 NW 1254 3.43E-06 5.87E-09 1191 3.62E-06 6.40E-09 1045 4.17E-06 7.98E-09 NNW 1069 3.70E-06 7.26E-09 1342 2.85E-06 4.87E-09 1561 2.93E-06 4.58E-09 0

Reference:

Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.

0

TABLE 3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Whole Body Skin Gamma Air Dose Factor Dose Factor Dose Factor Beta Air Dose Ki Li Mi Factor Ni mrernm 3 mrem-m3 mrad-m3 mrad-m3 Radionuclide yr-jiCi yr-pCi yr-pCi yr-I+/-Ci Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E3+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.1 lE+03 Xe-133m 2.5 1E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.1 lE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.5 1E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109, Table B-I.

24 ODCM Rev. 20

TABLE 3-4 Pi VALUES FOR THE INHALATION PATHWAY (mremlyr/pCCVm3 )

NUCLIDE Age Group Organ Pi H-3 TEEN LIVER 1.27E+03 CR-51 TEEN LUNG 2.10E+04 MN-54 TEEN LUNG 1.98E+06 FE-59 TEEN LUNG 1.53E+06 CO-58 TEEN LUNG 1.34E+06 CO-60 TEEN LUNG 8.72E+06 ZN-65 TEEN LUNG 1.24E+06 SR-89 TEEN LUNG 2.42E+06 SR-90 TEEN BONE 1.08E+08 ZR-95 TEEN LUNG 2.69E+06 SB-124 TEEN LUNG 3.85E+06 1-131 CHILD THYROID 1.62E+07 I-133 CHILD THYROID 3.85E+06 CS-134 TEEN LIVER 1.13E+06 CS-137 CHILD BONE 9.07E+05 BA- 140 TEEN LUNG 2.03E+06 CE-141 TEEN LUNG 6.14E+05 CE-144 TEEN LUNG 1.34E+07 25 ODCM Rev. 20

3.2 Requirements

Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System - Concentration The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:

5.OE-07 pCi/ml for the principal gamma emitters (except Ce-144) 3.OE-06 piCi/ml for Ce-144 1.OE-06 piCi/ml for I-131 L.OE-03 piCi/ml for H-3 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to:

2.0E-06 ipCi/ml for Cs-134 2.0E-06 pCi/ml for Cs-137 The concentrations specified in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, for all other isotopes Applicability: At all times.

Action:

When any secondary system liquid waste discharge pathway concentration determined in accordance with the surveillance requirements given below exceeds the above Requirements, divert that discharge pathway to the liquid radwaste system without delay or terminate the discharge.

3.2.1 Surveillance Requirements

a. Secondary system liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 3-5.

3.2.2 Implementation of the Requirements This requirement is implemented by Nuclear Administrative and Technical Manual procedures.

26 ODCM Rev. 20

TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling & Type Of (LLD)*

Pathway Destination Analysis Frequency Notes Activity Analysis (11Ciml)

1. Chemical Waste Neutralizer retention basin P Each Batch Principal Gamma Emittersc 5.OE-07 Tank (CWNT)b liquid radwaste N. A. 1-131 1.OE-06 H-3 1.01E-05
2. Steam Generator Blowdown circ. water P Each Batch 1 Principal Gamma Emittersc 5.0E-07 Low TDS Sumpb CWNT N. A. 1-131 1.0E-06 H-3 1.0E-05
3. Condensate
a. Condensate Polishing Low circ. water P Each Batch 3 Principal Gamma Emittersc 5.OE-07 TDS Sumpb CWNT N. A. 1-131 1.0E-06 H-3 1.0E-05 N%)
b. Initial Backwash (low TDS sump) to P Each Discharge Principal Gamma Emittersc 5.0E-07 circ. water 1-131 1.0E-06 (low TDS sump) to N. A. H-3 I.0E-05 CWNT
c. Pre-service rinse effluent retention basin P Each Discharge 2 Principal Gamma Emintersc 5.0E-07 through SC-N-V069 -131 1.OE-06 condenser through N. A. H-3 1.0E-05 SC-N-UV232
d. Overboard condensate circ water through P Each Discharge Principal Gamma Emittersc 5.OE-07 CD-N-V194 1-131 1.0E-06 retention basin P Each Discharge 2 H-3 1.0E-05 through SC-N-V079
4. Turbine Building Sump' retention basin D Grab Sample 3 Principal Gamma Emittersc 5.OE-07 0

CWNT N. A. 1-131 1.OE-06 H-3 1.0E-05

0 0

TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling & Type Of (LLD)"

Pathway Destination Analysis Frequency Notes Activity Analysis (RCi/ml)

5. North & South Condenser Area retention basin D Grab Sample 3 Principal Gamma Emittersc 5.OE-07 Sumpsd CWNT N. A. I-131 1.OE-06 H-3 1.OE-05
6. Steam Generator Blowdown to retention basin P Each Discharge 2 Principal Gamma Emitters' 5.OE-07 Retention Basin through SC-N-V064 1-131 1.OE-06 H-3 1.OE-05
7. Retention Basin to Evaporation evaporation pond P Each Batch Principal Gamma Emitters' 5.OE-07 Pond 1-131 1.OE-06 H-3 1.OE-05 00 1 Sampling and analysis are required only when concentration for chemical waste neutralizer tank or steam generator activity exceeds the requirement 2 RU-200 shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3-6. The Alarm/Trip setpoints for RU-200 are set to ensure that the concentrations in the retention basins do not exceed the Requirement 3 Sampling and analysis are required only when concentration for chemical waste neutralizer tank or condensate activity exceeds the requirement 0

0

Table 3-5 (Continued)

TABLE NOTATION a The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system which may include radiochemical separation:

4.66 Sb LLD = E

  • V
  • 2.22E6
  • Y
  • exp(-XAt)

Where:

LLD is the "a priori" lower limit of detection as defined above as microcuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate as counts per minute, E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield when applicable, X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.

TIypical 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 posterori (after the fact) limit for a particular measurement.

b 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 to assure representative sampling.

c 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. Ce-144 shall also be measured, but with an LLD of 3.OE-06. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

d 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 29 ODCM Rev. 20

TABLE 3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Channel Mode in which Channel Source Channel Functional Surveillance is Instrument Check Check Calibration Test Required RU-200 P N. A. R Q See Table 3-7 TABLE 3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Mode In which Surveillance Secondary System Liquid Release Pathway is Required Action if RU-200 Is inoperable Obtain grab sample 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 analyze in accordance Pre-service rinse to retention basins At All Times with section 3.2 Obtain grab sample 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 analyses in accordance Condensate overboard to retention basins 1-4 with section 3.2 Modes 1-4: Suspend the release Steam Generator Blowdown/Drain to retention At All Times Modes 5,6 & defueled: Obtain grab basins sample 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 analyze in accordance with sec-tion 3.2 30 ODCM Rev. 20

4.0 GASEOUS & LIQUID EFFLUENTS - DOSE

4.1 Requirements

Noble Gases The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITM BOUNDARY (see Figure 6-4 and Figure 6-5) 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:

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

4.1.1 Surveillance Requirements

a. Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology contained in Section 4.1.2 at least once per 31 days.

31 ODCM Rev. 20

4.1.2 Implementation of the Requirement: Noble Gas The air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from each unit during any specified time period shall be determined by the following equations:

For gamma radiation:

D yu = (3.17E-08) Fj[(M 1) (Q).UN(Q,)] (4-1)

For beta radiation:

D A. = (3.17E-08) Hi [(N1) (XIQ)Ur<Qi)] (4-2)

Where:

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per iVCitm 3 from Table 3-3.

Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per pCi/M3 from Table 3-3.

3 (X/Q)uNI = the highest calculated annual average dispersion parameter, in sec/m , at the site boundary for the particular Unit, from Table 3-2. Optionally, the highest value may be used for any Unit calculation.

=7.47E-06 from Unit I

=7.90E-06 from Unit 2

=8.91E-06 from Unit 3 D yu = the total gamma air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.

D Pu = the total beta air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.

Qi = the integrated release, from the particular unit, in IiCi, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period.

3.17E-08 = the inverse of seconds in a year (yr/sec).

The cumulative gamma air dose and beta air dose for a quarterly or annual evaluation shall be based on the calculated dose contribution from each specified time period occurring during the reporting time period.

32 ODCM Rev. 20

4.2 Requirement

Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-

5) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 7.5 inrems to any organ and,
b. During any calendar year: Less than or equal to 15 mrems to any organ.

Applicability: At all times.

Action:

With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit 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.

4.2.1 Surveillance Requirements

a. Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters contained in Section 4.2.2 at least once per 31 days.

33 ODCM Rev. 20

4.2.2 Implementation of the Requirement The organ dose to an individual from I-131, I-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:

Dou = (3.17E-08) Zi [k (Rik Wk) (Qi)] (4-3)

Where:

Do. = the total accumulated organ dose from gaseous effluents for a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.

Qi = the quantity of radionuclide i, in gCi, released in gaseous effluents from a particular unit.

Rik = the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mremlyr per pCi/m3 and for the food and ground plane pathways in m2 _ mrem/yr per piCi/sec, except H-3, which has units of mrem/yr per iVCi/m 3 ) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.

3.17E-08 = the inverse of seconds per year (yr/sec).

Wk = the highest annual average dispersion or deposition parameter for the particular Unit, used for estimating the dose at the site boundary or to a MEMBER OF THE PUBLIC at the controlling location for the particular Unit. Optionally, the highest value may be used for any Unit calculation.

= (X/Q)UNrIP in sec/M3 for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table 3-2.

=7.47E-06 from Unit I

=7.90E-06 from Unit 2

=8.91E-06 from Unit 3

= (X/Q)UNrr, in sec/m3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17 or 4-18.

=2.92E-06 from Unit 1

=2.19E-06 from Unit 2

=2.31E-06 from Unit 3

= (D/Q)UNrr, in m-2 , for the food and ground plane pathways, for organ dose at the site boundary, from Table 3-2.

=1.19E-08 from Unit 1

=1.34E-08 from Unit 2

=1.67E-08 from Unit 3 34 ODCM Rev. 20

= (D/Q)uNrD in m-2 , for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18.

=3.25E-09 from Unit I

=3.88E-10 from Unit 2

=4.21E-10 from Unit 3 Residences, vegetable gardens and milk animals located within 5 miles of the site will be identified during the annual land use census. The controlling pathway and location will be identified and will be used for all MEMBER OF THE PUBLIC dose evaluations.

The R; values were calculated in accordance with the methodologies in NUREG-0133. The following site specific information was used to calculate R,:

Yalue The length of the grazing season for milk animals (Q.

Ref. ER-OL, Section 2.1.3.4.3 0.75 The length of the grazing season for meat animals (f8).

Ref. ER-OL, Section 2.1.3.4.4 0.25 The fraction of daily feed derived from pasture while on pasture for milk animals (fp).

Ref. ER-OL, Section 2.1.3.4.3 0.35 The fraction of daily feed derived from pasture while on pasture for meat animals (fp).

Ref. ER-OL, Section 2.1.3.4.3 0.05 The fraction of year vegetables are grown, (fl) approximation.

Ref. ER-OL, Section 2.1.3.4, Table 2.1-8. 0.667 The annual absolute humidity (g/m3 ), H, Ref. UFSAR, Table 2.3-16 6 35 ODCM Rev. 20

43 Requirements: Gaseous Radwaste Treatment The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figure 6-4 and Figure 6-5) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-5) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

Applicability: At all times:

Action:

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

a. Identification of the inoperable equipment or subsystems and the reason for inoperability,
b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
c. Summary description of action(s) taken to prevent a recurrence.

43.1 Surveillance Requirements

a. Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 4.3.2.

36 ODCM Rev. 20

432 Implementation of the Requirement Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.

Dose Projection - Noble Gases The air dose, in mrads is determined using the methodology described in Section 4.1.2 of this manual. This information is used to determine an air dose projection for the next 31 days using the following equations:

For gamma radiation:

31 day y = Dy+/- CDy (4-4)

For beta radiation:

31 day = Do +/- CDP (4-5)

Where:

Dy = the total gamma air dose in mrads at the site boundary due to noble gases released in gaseous effluents for the previous 31 days.

D = the total beta air dose in mrads at the site boundary due to noble gases released in gaseous effluents for the previous 31 days.

CDy = any current or projected change in gamma air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 day y.

CDP = any current or projected change in beta air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 day P.

When performing the 31 day dose projection using the Gaseous Radioactive Effluent Tracking System (GRETS), Dy and DP3 will include the dose from any release permits that fall within the selected 31 day time period. As a result, the actual dose projection will often be based on the accumulated dose for a time period greater than 31 days.

37 ODCM Rev. 20

Dose Projection 131. 1-133. tritium. and all radionuclides in particulate form with half-lives greater than eight days The organ dose, in mrem, is determined using the methodology described in Section 4.2.2 of this manual. This information is used to determine an organ dose projection for the next 31 days using the following equation:

31day, = Do+/-CDo (4-6)

Where:

Do = the total organ dose due to I-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in mrem, released in gaseous effluents for the previous 31 days.

CDO = any current or projected change in organ dose, in mrem, which could have a significant impact on 31 day,.

When performing the 31 day dose projection using the Gaseous Radioactive Effluent Tracking System (GRETS), Do will include the dose from any release permits that fall within the selected 31 day time period. As a result, the actual dose projection will often be based on the accumulated dose for a time period greater than 31 days.

38 ODCM Rev. 20

TABLE 4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY NUCLIDE T. BODY SKIN H-3 O.OOE+00 O.OOE+00 CR-51 4.66E+06 5.5 1E+06 MN-54 1.39E+09 1.63E+09 FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 CO-60 2.15E+10 2.53E+10 ZN-65 7.47E+08 8.59E+08 SR-89 2.16E+04 2.51E+04 SR-90 O.OOE+00 O.OOE+00 ZR-95 2.45E+08 2.84E+08 SB-124 5.98E+08 6.90E+08 1-131 1.72E+07 2.09E+07 I-133 2.45E+06 2.98E+06 CS-134 6.86E+09 8.OOE+09 CS-137 1.03E+10 1.20E+10 BA-140 2.05E+07 2.35E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.95E+07 8.04E+07 39 ODCM Rev. 20

TABLE 4-2 RI DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.87E+03 2.87E+03 2.87E+03 2.87E+03 2.87E+03 2.87E+03 CR-51 O.OOE+00 O.OOE+00 4.OOE+04 2.39E+04 8.82E+03 5.31E+04 1.01E+07 MN-54 O.OOE+00 2.97E+08 5.66E+07 O.OOE+00 8.83E+07 0.00E+00 9.09E+08 FE-59 1.14E+08 2.68E+08 1.03E+08 0.00E+00 O.OOE+00 7.49E+07 8.93E+08 CO-58 0.00E+00 2.84E+07 6.38E+07 0.00E+00 O.OOE+00 O.OOE+00 5.76E+08 CO-60 O.OOE+00 1.59E+08 3.5 1E+08 0.00E+00 O.OOE+00 O.OOE+00 2.99E+09 ZN-65 3.OOE+08 9.56E+08 4.32E+08 0.00E+00 6.39E+08 0.00E+00 6.02E+08 SR-89 9.08E+09 O.OOE+00 2.61E+08 0.00E+00 0.00E+00 0.00E+00 1.46E+09 SR-90 5.76E+11 O.OOE+00 1.41E+11 O.OOE+00 0.00E+00 O.OOE+00 1.67E+10 ZR-95 1.08E+06 3.47E+05 2.35E+05 0.00E+00 5.45E+05 O.OOE+00 1.10E+09 SB-124 9.53E+07 1.80E+06 3.78E+07 2.31E1+05 O.OOE+00 7.42E+07 2.71E+09 1-131 5.49E+07 7.85E+07 4.50E+07 2.57E+10 1.35E+08 O.OOE+00 2.07E+07 I-133 1.39E+06 2.42E+06 7.38E+05 3.56E1+08 4.22E+06 0.001E+00 2.17E+06 CS-134 4.44E+09 1.06E+10 8.64E+09 O.OOE+00 3.42E+09 1.13E+09 1.85E+08 CS-137 6.06E+09 8.29E+09 5.43E+09 O.OOE+00 2.81E+09 9.36E1+08 1.60E+08 BA-140 9.43E+07 1.19E+05 6.18E+06 O.OOE+00 4.03E+04 6.78E+04 1.94E+08 CE-141 1.73E+05 1.17E+05 1.33E+04 0.00E+00 5.44E+04 O.OOE+00 4.48E+08 CE-144 3.12E+07 1.30E+07 1.67E+06 O.OOE+00 7.73E+06 O.OOE+00 1.05E+10 40 ODCM Rev. 20

TABLE 4-3 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 3.36E+03 3.36E+03 3.36E+03 3.36E+03 3.36E+03 3.36E+03 CR-51 O.OOE+00 O.OOE+00 5.60E+04 3.11E+04 1.23E+04 7.99E+04 9.41E+06 MN-54 O.OOE+00 4.41E+08 8.74E+07 O.OOE+00 1.31E+08 O.OOE+00 9.04E+08 FE-59 1.69E+08 3.94E+08 1.52E+08 O.OOE+00 0.OOE+00 1.24E+08 9.3 1E+08 CO-58 O.OOE+00 4.16E+07 9.59E+07 O.OOE+00 O.OOE+00 O.OOE+00 5.74E+08 CO-60 O.OOE+00 2.42E+08 5.45E+08 O.OOE+00 0.OOE+00 O.OOE+00 3.15E+09 ZN-65 4.1 lE+08 1.43E+09 6.65E+08 O.OOE+00 9.12E+08 O.OOE+00 6.04E+08 SR-89 1.43E+10 O.OOE+00 4.10E+08 0.00E+00 0.OOE+00 0.OOE+00 1.70E+09 SR-90 7.30E+l 1 O.OOE+00 1.80E+ Il O.OOE+00 0.OOE+00 O.OOE+00 2.05E+10 ZR-95 1.64E+06 5.17E+05 3.56E+05 O.OOE+00 7.60E+05 O.OOE+00 1.19E+09 SB-124 1.47E+08 2.70E+06 5.73E+07 3.33E+05 0.00E+00 1.28E+08 2.96E+09 I-131 5.29E+07 7.41E+07 3.98E+07 2.16E+10 1.28E+08 0.OOE+00 1.47E+07 1-133 1.29E+06 2.19E+06 6.68E1+05 3.06E+08 3.84E+06 O.OOE+00 1.66E+06 CS-134 6.90E+09 1.62E+10 7.53E+09 O.OOE+00 5.16E+09 1.97E+09 2.02E+08 CS-137 9.86E+09 1.3 1E+10 4.57E+09 O.OOE+00 4.46E+09 1.73E+09 1.87E+08 BA-140 1.07E+08 1.3 1E+05 6.88E+06 0.00E+00 4.44E+04 8.80E+04 1.65E+08 CE-141 2.61E+05 1.74E+05 2.OOE+04 0.00E+00 8.19E+04 O.OOE+00 4.98E+08 CE-144 5.1 1lE+07 2.12E+07 2.75E+06 O.OOE+00 1.26E+07 O.OOE+00 1.29E+10 41 ODCM Rev. 20

TABLE 4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER TBODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 5.23E+03 5.23E+03 5.23E+03 5.23E+03 5.23E+03 5.23E+03 CR-51 O.OOE+00 O.OOE+00 1.08E+05 6.02E+04 1.64E+04 1.IOE+05 5.75E+06 MN-54 O.OOE+00 6.49E+08 1.73E+08 O.OOE+00 1.82E+08 O.OOE+00 5.45E+08 FE-59 3.79E+08 6.13E+08 3.05E+08 O.OOE+00 O.OOE+00 1.78E+08 6.38E+08 CO-58 O.OOE+00 6.21E+07 1.90E+08 O.OOE+00 O.OOE+00 O.OOE+00 3.62E+08 CO-60 O.OOE+00 3.70E+08 1.09E+09 O.OOE+00 O.OOE+00 O.OOE+00 2.05E+09 ZN-65 7.93E+08 2.1 lE+09 1.3 1E+09 O.OOE+00 1.33E+09 O.OOE+00 3.71E+08 SR-89 3.44E+10 O.OOE+00 9.83E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.33E+09 SR-90 1.22E+12 O.OOE+00 3.09E+l 1 O.OOE+00 O.OOE+00 O.OOE+00 1.64E+10 ZR-95 3.72E+06 8.17E+05 7.27E+05 O.OOE+00 1.17E+06 O.OOE+00 8.52E+08 SB-124 3.38E+08 4.39E+06 1.19E+08 7.47E+05 O.OOE+00 1.88E+08 2.12E+09 I-131 9.95E+07 1.OOE+08 5.68E+07 3.31E+10 1.64E+08 O.OOE+00 8.90E+06 1-133 2.36E+06 2.91E+06 1.10E+06 5.41E+08 4.85E+06 O.OOE+00 1. 17E+06 CS-134 1.57E+10 2.57E+10 5.43E+09 O.OOE+00 7.98E+09 2.86E+09 1.39E+08 CS-137 2.34E+10 2.24E+10 3.3 lE+09 O.OOE+00 7.31E+09 2.63E+09 1.40E+08 BA-140 2.20E+08 1.93E+05 1.28E+07 O.OOE+00 6.27E+04 1.15E+05 1.1IE+08 CE-141 6.15E+05 3.07E+05 4.55E+04 O.OOE+00 1.34E+05 O.OOE+00 3.83E+08 CE-144 1.24E+08 3.89E+07 6.62E+06 O.OOE+00 2.15E+07 O.OOE+00 1.01E+10 42 ODCM Rev. 20

TABLE 4-5 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 4.33E+02 4.33E+02 4.33E+02 4.33E+02 4.33E+02 4.33E+02 CR-51 O.OOE+00 O.OOE+00 3.44E+02 2.06E+02 7.58E+01 4.57E+02 8.65E+04 MN-54 O.OOE+00 2.71E+06 5.18E+05 O.OOE+00 8.08E+05 0.00E+00 8.31IE+06 FE-59 2.60E+07 6.1 1E+07 2.34E+07 0.00E+00 O.OOE+00 1.71E+07 2.04E+08 CO-58 O.OOE+00 2.84E+06 6.36E+06 0.00E+00 O.OOE+00 O.OOE+00 5.75E-i07 CO-60 O.OOE+00 2.61E+07 5.76E+07 O.OOE+00 O.OOE+00 O.OOE+00 4.90E+08 ZN-65 9.97E+07 3.17E+08 1.43E+08 O.OOE+00 2.12E+08 O.OOE+00 2.OOE+08 SR-89 3.41E+07 O.OOE+00 9.79E+05 O.OOE+00 0.00E+00 O.OOE+00 5.47E+06 SR-90 4.43E+09 O.OOE+00 1.09E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.28E+08 ZR-95 2.68E+05 8.58E+04 5.81E+04 O.OOE+00 1.35E+05 O.OOE+00 2.72E+08 SB-124 2.67E+06 5.05E+04 1.06E+06 6.48E+03 O.OOE+00 2.08E+06 7.59E+07 I-131 1.36E+05 1.94E+05 1.1 II E+05 6.37E+07 3.33E+05 O.OOE+00 5.1 3E+04 I-133 4.56E-03 7.94E-03 2.42E-03 1.17E+00 1.39E-02 O.OOE+00 7.14E-03 CS-134 2.17E+08 5.17E+08 4.23E+08 O.OOE+00 1.67E+08 5.56E+07 9.05E+06 CS-137 3.1 lE+08 4.25E+08 2.78E+08 O.OOE+00 1.44E+08 4.79E+07 8.22E+06 BA-140 4.35E+05 5.46E+02 2.85E+04 O.OOE+00 1.86E+02 3.13E+02 8.95E+05 CE-141 8.87E+02 6.OOE+02 6.80E+01 O.OOE+00 2.79E+02 O.OOE+00 2.29E-i06 CE-144 4.23E+05 1.771E+05 2.27E+04 O.OOE+00 1.05E+05 O.OOE+00 1.43E+08 43 ODCM Rev. 20

TABLE 4-6 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.58E+02 2.58E+02 2.58E+02 2.58E+02 2.58E+02 2.58E+02 CR-51 O.OOE+00 O.OOE+00 2.75E+02 1.53E+02 6.03E+01 3.93E+02 4.62E+04 MN-54 O.OOE+00 2.07E+06 4.1 1E+05 O.OOE+00 6.18E+05 O.OOE+00 4.25E+06 FE-59 2.08E+07 4.85E+07 1.87E+07 O.OOE+00 O.OOE+00 1.53E+07 1.15E1+08 CO-58 O.OOE+00 2.19E+06 5.04E+06 O.OOE+00 O.OOE+00 O.OOE+00 3.02E+07 CO-60 0.00E+00 2.03E+07 4.56E+07 0.00E+00 O.OOE+00 O.OOE+00 2.64E+08 ZN-65 7.01E+07 2.43E+08 1.14E1+08 O.OOE+00 1.56E+08 O.OOE+00 1.03E+08 SR-89 2.88E+07 O.OOE+00 8.24E+05 O.OOE+00 O.OOE+00 O.OOE+00 3.43E+06 SR-90 2.87E+09 O.OOE+00 7.08E+08 O.OOE+00 O.OOE+00 O.OOE+00 8.05E+07 ZR-95 2.14E+05 6.76E+04 4.65E+04 O.OOE+00 9.93E+04 O.OOE+00 1.56E+08 SB-124 2.18E+06 4.02E+04 8.52E+05 4.95E+03 O.OOE+00 1.91E+06 4.40E+07 1-131 1.13E+05 1.58E+05 8.49E+04 4.61E+07 2.72E+05 O.OOE+00 3.13E+04 I-133 3.82E-03 6.48E-03 1.98E-03 9.04E-01 1.14E-02 O.OOE+00 4.90E-03 CS-134 1.73E+08 4.07E+08 1.89E+08 O.OOE+00 1.29E+08 4.94E+07 5.06E+06 CS-137 2.58E+08 3.43E+08 1.20E+08 O.OOE+00 1.17E+08 4.54E+07 4.88E+06 BA-140 3.59E+05 4.40E+02 2.3 1E+04 O.OOE+00 1.49E+02 2.96E+02 5.54E+05 CE-141 7.45E+02 4.97E+02 5.71E+01 O.OOE+00 2.34E+02 O.OOE+00 1.42E+06 CE-144 3.56E+05 1.47E+05 1.91E+04 O.OOE+00 8.80E+04 O.OOE+00 8.96E+07 44 ODCM Rev. 20

TABLE 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER TXBODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 3.12E+02 3.12E+02 3.12E+02 3.12E+02 3.12E+02 3.12E+02 CR-51 O.OOE+00 O.OOE+00 4.29E+02 2.38E+02 6.51E+01 4.35E+02 2.28E+04 MN-54 O.OOE+00 2.37E+06 6.31E1+05 O.OOE+00 6.64E+05 O.OOE+00 1.99E+06 FE-59 3.68E+07 5.96E+07 2.97E+07 0.00E+00 O.OOE+00 1.73E+07 6.20E+07 CO-58 O.OOE+00 2.55E+06 7.82E+06 O.OOE+00 O.OOE+00 O.OOE+00 1.49E+07 C0-60 O.OOE+00 2.40E+07 7.09E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.33E+08 ZN-65 1.05E+08 2.80E+08 1.74E+08 O.OOE+00 1.77E+08 O.OOE+00 4.92E+07 SR-89 5.45E+07 O.OOE+00 1.56E+06 O.OOE+00 O.OOE+00 O.OOE+00 2.1 lE+06 SR-90 3.70E+09 O.OOE+00 9.39E+08 O.OOE+00 O.OOE+00 O.OOE+00 4.99E+07 ZR-95 3.81E+05 8.36E+04 7.45E+04 O.OOE+00 1.20E+05 O.OOE+00 8.73E+07 SB-124 3.95E+06 5.12E+04 1.38E+06 8.72E+03 O.OOE+00 2.19E+06 2.47E+07 I-131 2.09E+05 2.11E+05 1.20E+05 6.96E+07 3.46E+05 O.OOE+00 1.87E+04 1-133 7.09E-03 8.77E-03 3.32E-03 1.63E+00 1.46E-02 O.OOE+00 3.53E-03 CS-134 3.05E+08 5.OOE+08 1.06E+08 O.OOE+00 1.55E+08 5.56E+07 2.70E+06 CS-137 4.75E+08 4.55E+08 6.71E+07 O.OOE+00 1.48E+08 5.33E+07 2.85E+06 BA-140 6.63E+05 5.81E+02 3.87E+04 O.OOE+00 1.89E+02 3.46E+02 3.36E+05 CE-141 1.40E+03 6.99E+02 1.04E+02 O.OOE+00 3.07E+02 O.OOE+00 8.72E+05 CE-144 6.72E+05 2.11E+05 3.58E+04 O.OOE+00 1.17E+05 O.OOE+00 5.49E+07 45 ODCM Rev. 20

TABLE 4-8 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.02E+03 1.02E+03 1.02E+03 1.02E+03 1.02E+03 1.02E+03 CR-51 O.OOE+00 O.OOE+00 8.28E+03 4.95E+03 1.82E+03 1.10E+04 2.08E+06 MN-54 O.OOE+00 3.99E+06 7.61E+05 O.OOE+00 1.19E+06 O.OOE+00 1.22E+07 FE-59 9.69E+06 2.28E+07 8.73E+06 O.OOE+00 O.OOE+00 6.36E+06 7.59E+07 CO-58 O.OOE+00 1.74E+06 3.90E+06 O.OOE+00 O.OOE+00 O.OOE+00 3.53E+07 C0-60 O.OOE+00 8.41E+06 1.85E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.58E+08 ZN-65 6.34E+08 2.02E+09 9.12E+08 O.OOE+00 1.35E+09 O.OOE+00 1.27E+09 SR-89 4.90E+08 O.OOE+00 1.41E+07 O.OOE+00 O.OOE+00 O.OOE+00 7.86E+07 SR-90 2.43E+10 O.OOE+00 5.96E+09 O.OOE+00 O.OOE+00 O.OOE+00 7.02E+08 ZR-95 3.39E+02 1.09E+02 7.37E+01 O.OOE+00 1.71E+02 O.OOE+00 3.45E+05 SB-124 9.1 lE+06 1.72E+05 3.61E+06 2.21E+04 O.OOE+00 7.09E+06 2.59E+08 1-131 7.77E+07 1. IIE+08 6.37E+07 3.64E+10 1.91E+08 O.OOE+00 2.93E+07 I-133 1.02E+06 1.77E+06 5.39E+05 2.60E+08 3.08E+06 O.OOE+00 1.59E+06 CS-134 2.83E+09 6.73E+09 5.50E+09 O.OOE+00 2.18E+09 7.23E+08 1.1 8E+08 CS-137 3.83E+09 5.24E+09 3.43E+09 O.OOE+00 1.78E+09 5.91E+08 1.01E+08 BA-140 7.11 IE+06 8.93E+03 4.66E+05 O.OOE+00 3.04E+03 5.1 1E+03 1.46E+07 CE-141 8.73E+03 5.90E+03 6.70E+02 O.OOE+00 2.74E+03 O.OOE+00 2.26E+07 CE-144 1.01E+06 4.21E+05 5.41E+04 O.OOE+00 2.50E+05 O.OOE+00 3.41E+08 46 ODCM Rev. 20

TABLE 4-9 RI DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID IUDNEY LUNG GI-LLI H-3 O.OOE+00 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 CR-51 O.OOE+00 O.OOE+00 1.45E+04 8.03E+03 3.17E+03 2.06E+04 2.43E+06 MN-54 O.OOE+00 6.64E+06 1.32E+06 O.OOE+00 1.98E+06 0.OOE+00 1.36E+07 FE-59 1.69E+07 3.95E+07 1.52E+07 O.OOE+00 0.OOE+00 1.24E+07 9.33E+07 C0-58 O.OOE+00 2.93E+06 6.76E+06 O.OOE+00 0.OOE+00 O.OOE+00 4.04E+07 CO-60 O.OOE+00 1.42E+07 3.21E+07 O.OOE+00 0.OOE+00 0.00E+00 1.86E+08 ZN-65 9.74E+08 3.38E+09 1.58E+09 O.OOE+00 2.17E+09 0.OOE+00 1.43E+09 SR-89 9.03E+08 O.OOE+00 2.59E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.08E+08 SR-90 3.43E+10 O.OOE+00 8.48E+09 O.OOE+00 0.OOE+00 0.OOE+00 9.64E+08 ZR-95 5.94E+02 1.87E+02 1.29E+02 O.OOE+00 2.75E+02 O.OOE+00 4.32E+05 SB-124 1.62E+07 2.99E+05 6.34E+06 3.69E+04 0.OOE+00 1.42E+07 3.27E+08 I-131 1.41E+08 1.98E+08 1.06E+08 5.76E+10 3.40E+08 0.OOE+00 3.9 1E+07 I-133 1.86E+06 3.15E+06 9.60E+05 4.39E+08 5.52E+06 0.00E+00 2.38E+06 CS-134 4.91E+09 1.166E+10 5.36E+09 O.OOE+00 3.67E+09 1.40E+09 1.44E+08 CS-137 6.95E+09 9.24E+09 3.22E+09 0.OOE+00 3.15E+09 1.22E+09 1.32E+08 BA-140 1.28E+07 1.57E+04 8.27E+05 O.OOE+00 5.33E+03 1.06E+04 1.98E+07 CE-141 1.60E+04 1.07E+04 1.23E1+03 O.OOE+00 5.03E+03 0.OOE+00 3.06E+07 CE-144 1.86E+06 7.68E+05 9.97E+04 0.OOE+00 4.59E+05 O.OOE+00 4.67E+08 47 ODCM Rev. 20

TABLE 4-10 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 CR-51 O.OOE+00 O.OOE+00 2.95E+04 1.64E+04 4.47E+03 2.99E+04 1.56E+06 MN-54 O.OOE+00 9.94E+06 2.65E+06 O.OOE+00 2.79E+06 O.OOE+00 8.34E+06 FE-59 3.92E+07 6.35E+07 3.16E+07 O.OOE+00 O.OOE+00 1.84E+07 6.61E+07 CO-58 O.OOE+00 4.48E+06 1.37E+07 O.OOE+00 0.00E+00 O.OOE+00 2.61E+07 CO-60 O.OOE+00 2.21E+07 6.52E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.23E+08 ZN-65 1.91E+09 5.09E+09 3.17E+09 O.OOE+00 3.2 1E+09 O.OOE+00 8.95E+08 SR-89 2.23E+09 O.OOE+00 6.38E+07 O.OOE+00 O.OOE+00 O.OOE+00 8.65E+07 SR-90 5.80E+10 O.OOE+00 I.47E+10 O.OOE+00 O.OOE+00 O.OOE+00 7.8 1E+08 ZR-95 1.38E+03 3.03E+02 2.70E+02 O.OOE+00 4.34E+02 O.OOE+00 3.16E+05 SB-124 3.84E+07 4.99E+05 1.35E+07 8.49E+04 O.OOE+00 2.13E+07 2.41E+08 1-131 3.42E+08 3.44E+08 1.96E+08 1. 14E+I I 5.65E+08 O.OOE+00 3.06E+07 I-133 4.51E+06 5.57E+06 2.1 1E+06 1.04E+09 9.29E+06 O.OOE+00 2.25E+06 CS-134 1.13E+10 1.86E+10 3.92E+09 O.OOE+00 5.76E+09 2.07E+09 1.00E+08 CS-137 1.67E+10 1.60E+10 2.36E+09 O.OOE+00 5.22E+09 1.88E+09 1.00E+08 BA-140 3. 1OE+07 2.71E+04 1.81E+06 O.OOE+00 8.83E+03 1.62E+04 1.57E+07 CE-141 3.94E+04 1.97E+04 2.92E+03 O.OOE+00 8.62E+03 O.OOE+00 2.45E+07 CE-144 4.57E+06 1.43E+06 2.44E+05 O.OOE+00 7.94E+05 O.OOE+00 3.74E+08 48 ODCM Rev. 20

TABLE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR NUCLIDE BONE LIVER TBODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 3.18E+03 3.18E+03 3.18E+03 3.18E+03 3.18E+03 3.18E+03 CR-51 O.OOE+00 O.OOE+00 4.67E+04 3.05E+04 6.66E+03 5.93E+04 1.36E+06 MN-54 O.OOE+00 1.85E+07 4.19E+06 O.OOE+00 4.10E+06 O.OOE+00 6.79E+06 FE-59 7.32E+07 1.28E+08 5.04E+07 O.OOE+00 O.OOE+00 3.78E+07 6.1 1E+07 CO-58 O.OOE+00 8.96E+06 2.23E+07 O.OOE+00 O.OOE+00 O.OOE+00 2.23E+07 CO-60 O.OOE+00 4.52E+07 1.07E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.07E+08 ZN-65 2.57E+09 8.81E+09 4.06E+09 O.OOE+00 4.27E+09 O.OOE+00 7.44E+09 SR-89 4.25E+09 O.OOE+00 1.22E+08 O.OOE+00 O.OOE+00 O.OOE+00 8.74E+07 SR-90 6.31E+10 O.OOE+00 1.61E+10 O.OOE+00 O.OOE+00 O.OOE+00 7.88E+08 ZR-95 2.45E+03 5.97E+02 4.23E+02 O.OOE+00 6.43E+02 O.OOE+00 2.97E+05 SB-124 7.41E+07 1.09E+06 2.30E+07 1.97E+05 O.OOE+00 4.64E+07 2.29E+08 1-131 7.14E+08 8.42E+08 3.70E+08 2.77E+I I 9.83E+08 O.OOE+00 3.OOE+07 I-133 9.52E+06 1.39E+07 4.06E+06 2.52E+09 1.63E+07 O.OOE+00 2.35E+06 CS-134 1.82E+10 3.40E+10 3.44E+09 O.OOE+00 8.76E+09 3.59E+09 9.24E+07 CS-137 2.67E+10 3.13E+10 2.22E+09 O.OOE+00 8.39E+09 3.40E+09 9.78E+07 BA-140 6.37E+07 6.37E+04 3.28E+06 O.OOE+00 1.5 lE+04 3.91E+04 1.57E+07 CE-141 7.81E+04 4.77E+04 5.61E+03 O.OOE+00 1.47E+04 O.OOE+00 2.46E+07 CE-144 6.55E+06 2.68E+06 3.67E+05 O.OOE+00 1.08E+06 O.OOE+00 3.76E+08 49 ODCM Rev. 20

TABLE 4-12 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 CR-51 O.OOE+00 O.OOE+00 1.OOE+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 O.OOE+00 3.96E+04 6.30E+03 O.OOE+00 9.84E+03 1.40E+06 7.74E+04 FE-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+00 O.OOE+00 1.02E+06 1.88E+05 CO-58 O.OOE+00 1.58E+03 2.07E+03 O.OOE+00 O.OOE+00 9.28E+05 1.06E+05 CO-60 O.OOE+00 1.15E+04 1.48E+04 O.OOE+00 O.OOE+00 5.97E+06 2.85E+05 ZN-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+00 6.90E+04 8.64E+05 5.34E+04 SR-89 3.04E+05 O.OOE+00 8.72E+03 O.OOE+00 O.OOE+00 1.40E+06 3.50E+05 SR-90 9.92E+07 O.OOE+00 6.10E+06 O.OOE+00 O.OOE+00 9.60E+06 7.22E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+00 5.42E+04 1.77E+06 1.50E+05 SB-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 O.OOE+00 2.48E+06 4.06E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+00 6.28E+03 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+00 8.88E+03 CS-134 3.73E+05 8A8E+05 7.28E+05 O.OOE+00 2.87E+05 9.76E+04 1.04E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 O.OOE+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+00 8.48E+05 7.78E+06 8.16E+05 50 ODCM Rev. 20

TABLE 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER TMBODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 CR-51 O.OOE+00 O.OOE+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.OOE+03 MN-54 O.OOE+00 5.1 IE+04 8.40E+03 O.OOE+00 1.27E+04 1.98E+06 6.68E+04 FE-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+00 O.OOE+00 1.53E+06 1.78E+05 CO-58 O.OOE+00 2.07E+03 2.78E+03 O.OOE+00 O.OOE+00 1.34E+06 9.52E+04 CO-60 O.OOE+00 1.51E+04 1.98E+04 O.OOE+00 O.OOE+00 8.72E+06 2.59E+05 ZN-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+00 8.64E+04 1.24E+06 4.66E+04 SR-89 4.34E+05 O.OOE+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 1.08E+08 O.OOE+00 6.68E+06 O.OOE+00 O.OOE+00 1.65E+07 7.65E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+00 6.74E+04 2.69E+06 1.49E+05 SB-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 O.OOE+00 3.85E+06 3.98E+05 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+00 6.49E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+00 3.75E+05 1.46E+05 9.76E+03 CS-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+01 3.52E+03 O.OOE+00 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+00 1.21E+06 1.34E+07 8.64E+05 51 ODCM Rev. 20

TABLE 4-14 RI DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILD RECEPTOR NUCLIDE BONE LIVER TXBODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E1+01 1.70E+04 1.08E+03 MN-54 O.OOE+00 4.29E+04 9.51E+03 O.OOE+00 1.00E-+04 1.58E+06 2.29E+04 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E-+00 1.27E+06 7.07E+04 CO-58 0.OOE+00 1.77E+03 3.16E+03 0.OOE+00 0.00E+00 1.llE+06 3.44E+04 CO-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E1+04 9.95E+05 1.63E+04 SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 O.OOE+00 2.16E+06 1.67E+05 SR-90 1.011E+08 0.00E+00 6.44E+06 0.00E+00 O.OOE+00 1.48E+07 3.43E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.1 lE+04 SB-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 O.OOE+00 3.24E+06 1.64E+05 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS-134 6.51E+05 1.01E+06 2.25E+05 O.OOE+00 3.30E+05 1.21E+05 3.85E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 O.OOE+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7AOE+04 6.48E+01 4.33E+03 0.OOE+00 2.11EE+-01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+00 1.17E+06 1.20E+07 3.89E+05 52 ODCM Rev. 20

TABLE 4-15 RI DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 CR-51 O.OOE+00 O.OOE+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 O.OOE+00 2.53E+04 4.98E+03 O.OOE+00 4.98E+03 1.00E+06 7.06E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+00 O.OOE+00 1.02E+06 2.48E+04 CO-58 0.00E+00 1.22E+03 1.82E+03 O.OOE+00 O.OOE+00 7.77E+05 1.1IlIE+04 CO-60 O.OOE+00 8.02E+03 1.18E+04 O.OOE+00 O.OOE+00 4.51E+06 3.19E+04 ZN-65 1.93E+04 6.26E+04 3.1 IE+04 O.OOE+00 3.25E+04 6.47E+05 5.14E+04 SR-89 3.98E+05 O.OOE+00 1.14E+04 O.OOE+00 O.OOE+00 2.03E+06 6.40E+04 SR-90 4.09E+07 O.OOE+00 2.59E+06 O.OOE+00 O.OOE+00 1.12E+07 1.3 1E+05 ZR-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+00 3.1 1E+04 1.75E+06 2.17E+04 SB-124 3.79E+04 5.56E+02 1.20E+04 1.01E+02 O.OOE+00 2.65E+06 5.91E+04 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 O.OOE+00 1.06E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+00 5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 O.OOE+00 5.38E+05 9.84E+06 1.48E+05 53 ODCM Rev. 20

TABLE 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT I X/Q RESIDENCE(b) D/Q X/Q GARDEN(b) D/(2 X/Q MILK(b) D/Q2 DIRECTION (Sec/m 3 ) Dist. Miles (m- 2) (Sec/m3 ) Dist Miles (m ) (Sec/r 3 ) Dist. Miles (mr)

N 2.92E-06 1.4 3.25E-09 2.92E-06 1.4 3.25E-09 7.03E-07 (a) 3.48E-10 NNE 1.81E-06 1.8 2.88E-09 4.70E-07 (a) 4.04E-10 4.70E-07 (a) 4.04E-10 NE 1.95E-06 1.9 3.85E-09 1.76E-06 2.1 3.29E-09 5.77E-07 (a) 6.51E-10 ENE 1.03E-06 2.7 1.08E-09 1.03E-06 2.7 1.08E-09 3.86E-07 (a) 2.86E-10 E 9.39E-07 2.8 6.68E-10 3.71E-07 (a) 1.87E-10 3.71E-07 (a) 1.87E-10 ESE 6.37E-07 3.7 2.84E-10 4.12E-07 4.6 1.60E-10 4.12E-07 4.6 1.60E-10 goat SE 8.83E-07 4.1 2.61E-10 8.83E-07 4.1 2.61E-10 5.84E-07 (a) 1.52E-10 SSE 1.27E-06 4.7 2.611E-10 1.09E-06 (a) 2.15E-10 1.09E-06 (a) 2.15E-10 S 2.58E-06 4.6 4.85E-10 2.09E-06 5.2 3.59E-10 2.13E-06 5.1 3.71E-10 cow SSW 3.26E-06 3.5 8.26E-10 2.28E-06 (a) 4.53E-10 2.28E-06 (a) 4.53E-10 SW 2.80E-06 2.9 9.10E-10 1.58E-06 (a) 3.56E- 10 1.58E-06 (a) 3.56E-10 WSW 1.95E-06 2.6 1.09E-09 8.55E-07 (a) 3.18E-10 8.55E-07 (a) 3.18E-10 W 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 WNW 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 NW 8.24E-07 3.8 5.25E-10 7.55E-07 4.1 4.61E-10 6.02E-07 (a) 3.27E-10 NNW 1.46E-06 2.0 1.47E-09 5.20E-07 (a) 3.04E-10 5.20E-07 (a) 3.04E-10 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.

(b) Controlling locations are discussed in Appendix A.

References:

1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.

CD

TABLE 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 X/Q RESIDENCE(b) D/Q XIQ GARDEN(h) D/Q XIQ MILK(b) D/7 DIRECTION (Sec/r 3 ) Dist. Miles (mr2 ) (Sec/m3 ) Dist Miles (m- 2) (Sec/m 3) Dist. Miles (m7 )

N 2.73E-06 1.5 2.92E-09 2.39E-06 1.7 2.35E-09 7.03E-07 (a) 3.48E-10 NNE 2.20E-06 1.5 3.87E-09 2.20E-06 1.5 3.87E-09 4.70E-07 (a) 4.04E-10 NE 1.85E-06 2.0 3.55E-09 1.57E-06 2.3 2.78E-09 5.77E-07 (a) 6.51E-10 ENE 1.03E-06 2.7 1.08E-09 1.03E-06 2.7 1.08E-09 3.86E-07 (a) 2.86E-10 E 8.80E-07 3.0 6.06E-10 3.71E-07 (a) 1.87E-10 3.71E-07 (a) 1.87E-10 ESE 6.25E-07 3.7 2.76E-10 3.96E-07 4.7 1.51E-10 3.96E-07 4.7 1.5 IE-10 goat SE 9.06E-07 4.0 2.72E-10 9.06E-07 4.0 2.72E-10 5.84E-07 (a) 1.52E-10 Ut SSE 1.34E-06 4.5 2.811E-10 1.09E-06 (a) 2.15E-10 1.09E-06 (a) 2.15E-10 S 2.63E-06 4.5 5.01E-10 2.19E-06 5.0 3.88E-10 2.19E-06 5.0 3.88E-10 cow SSW 3.48E-06 3.2 9.19E-10 2.28E-06 (a) 4.53E-10 2.28E-06 (a) 4.53E-10 SW 2.93E-06 2.7 9.75E-10 1.58E-06 (a) 3.56E-10 1.58E-06 (a) 3.566E-10 WSW 2.01E-06 2.5 1.16E-09 8.55E-07 (a) 3.18E-10 8.55E-07 (a) 3.18E-10 W 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 WNW 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 NW 7.84E-07 4.0 4.88E-10 7.84E-07 4.0 4.88E-10 6.02E-07 (a) 3.27E-10 NNW 1.46E-06 2.0 1.47E-09 5.20E-07 5.0 3.04E-10 5.20E-07 (a) 3.04E-10 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.

0 (b) Controlling locations are discussed in Appendix A.

0

References:

1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.

TABLE 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 X/Q RESIDENCE(b) D/Q X/Q GARDEN(b) D/Q X/Q MILK(b) D/Q DIRECTION (Sec/r 3 ) Dist. Miles (mr2 ) (Sec/m3 ) Dist. Miles (m ) (Sec/m3 ) Dist. Miles (rn 2 )

N 2.58E-06 1.8 2.47E-09 2.42E-06 1.9 2.22E-09 7.03E-07 (a) 3.48E-10 NNE 1.85E-06 1.7 2.97E-09 1.85E-06 1.7 2.97E-09 4.70E-07 (a) 4.04E-10 NE 1.66E-06 2.2 3.OOE-09 I1.48E-06 2.4 2.54E-09 5.77E-07 (a) 6.51E-10 ENE 8.75E-07 2.9 8.86E-10 8.75E-07 2.9 8.86E-10 3.86E-07 (a) 2.86E-10 E 8.90E-07 3.0 6.17E-10 4.06E-07 4.6 2.15E-10 4.25E-07 4.5 2.31E-10 goat ESE 6.37E-07 3.7 2.84E-10 5.80E-07 4.0 2.46E-10 3.73E-07 (a) 1.37E-10 SE 5.84E-07 (a) 1.52E-10 5.84E-07 (a) 1.52E-10 5.84E-07 (a) 1.52E-10 LA ON SSE 1.36E-06 4.4 2.88E-10 I1.09E-06 (a) 2.15E-10 1.09E-06 (a) 2.151E-10 S 2.65E-06 4.2 5.25E-10 2.25E-06 4.9 4.06E-10 2.3 1E-06 4.8 4.21E-10 cow SSW 3.64E-06 3.1 9.82E-10 2.28E-06 (a) 4.53E-10 2.28E-06 (a) 4.53E-10 SW 3.19E-06 2.5 1.1IE-09 1.58E-06 (a) 3.56E-10 1.58E-06 (a) 3.56E-10 WSW 2.12E-06 2.4 1.26E-09 8.55E-07 (a) 3.18E-10 8.55E-07 (a) 3.18E-10 W 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 7.54E-10 (a) 4.44E-10 WNW 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 NW 6.83E-07 4.3 4.05E-10 6.82E-07 4.3 4.05E-10 6.02E-07 (a) 3.27E-10 NNW 1.34E-06 2.2 1.26E-09 5. 16E-07 5.0 3.01E-10 5.20E-07 (a) 3.04E-10 0 (a) 5-mile value used since there is no pathway located within the sector up to five miles.

(b) Controlling locations are discussed in Appendix A.

0

References:

1984 Land Use Census (letter ANPM-21221-JRMALEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.

4.4 Requirements

Liquid Efuents The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See Figure 6-4 and Figure 6-5) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total 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 total body and to less than or equal to 10 mrems to any organ.

Applicability: At all times.

Action:

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

4.4.1 Surveillance Requirements 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 the ODCM at least once per 31 days.

4.4.2 Implementation of the Requirements This Requirement does not require implementation guidance. There are no offsite liquid effluent releases.

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5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE

5.1 Requirement

Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to direct 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:

With the calculated doses from the release of radioactive materials in liquid and gaseous effluents exceeding twice the limits of Section 4.4a, 4.4b, 4.1a, 4.1b, 4.2a or 4.2b calculations shall be made including direct radiation contributions from the reactor units (including outside storage tanks, etc.) to determine whether the above limits of Section 5.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203(a)(4), 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 concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report within 30 days is considered a timely request, and a variance is granted until staff action on the request is complete.

5.1.1 Surveillance Requirements

a. Cumulative dose contributions from the gaseous effluents shall be determined in accordance with the surveillance requirements of Section 4.4.1, 4.1.1 and 4.2.1 and in accordance with the methodology and parameters contained in Section 5.1.2.
b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Section 5.1.2. This requirement is applicable only under conditions set forth in Section 5.1, Action.

5.1.2 Implementation of the Requirement Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered.

The total dose to any MEMBER OF THE PUBLIC will be determined based on a sum of the doses from all three units' releases and doses from direct radiation from PVNGS.

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This dose evaluation is performed annually and submitted with the Annual Radioactive Effluent Release Report to assure compliance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. NUREG-0543, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), February 1980, provides a discussion on compliance with 40 CFR Part 190 in relation to the Radiological Environmental Technical Specifications for sites of up to four nuclear power reactors. The NUREG concludes that as long as a nuclear plant site operates at a level below the 10 CFR Part 50, Appendix I reporting requirements, and there is no significant source of direct radiation from the site, no extra analysis is required to demonstrate compliance with 40 CFR Part 190. As a result, this dose evaluation will also be performed whenever calculated doses associated with effluent releases exceed twice the limits of Section 4.4a, 4.4b, 4.1a, 4.lb, 4.2a or 4.2b.

Dose Contribution from Liquid and Gaseous Effluents The annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noble gases released in gaseous effluents is determined by using the following equation:

DWB = (3.17E-08) Zi [(Ki) (X/Q)UNIT (Q1)] (5-1)

Where:

K- = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per jiCi/m 3 from Table 3-3.

Qi = the integrated release of radionuclide i, in pCi for the previous calendar year.

(X/Q)UNrr = the highest calculated annual average dispersion parameter, in sec/m3 , for a particular unit, at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.

=2.92E-06 from Unit 1

=2.19E-06 from Unit 2

=2.31E-06 from Unit 3 DWB = the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.

3.17E-08 = the inverse of seconds in a year (yr/sec).

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The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-1 31, iodine- 133, tritium and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents is determined by using the following equation:

Do = (3.17E-08) Zi [Ek(RikWk) (Qi)] (5-2)

Where:

Do = the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location.

Qi = the integrated release of radionuclide i, in pCi, for the previous calendar year.

Rik = the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per pCi/M3 and for the food and ground plane pathways in m2 -mrem/yr per gCi/sec) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.

WK = the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the total annual organ dose to a MEMBER OF THE PUBLIC at the controlling location for the particular unit.

= (X/Q)UNrrm in sec/M3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.

=2.92E-06 from Unit I

=2.19E-06 from Unit 2

=2.31E-06 from Unit 3

= (D/Q)uNrr, in m-2, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.

=3.25E-09 from Unit I

=3.88E-10 from Unit 2

=4.21E-10 from Unit 3 3.17E-08 = the inverse of seconds in a year (yr/sec).

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Dose Due to Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be evaluated by first determining the direct radiation dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling location by the inverse square law of distance.

Dose from Radioactive Liquid and Gaseous Effluents to MEMBERS OF THE PUBLIC due to their activities within the SITE BOUNDARY.

These activities have been determined to be limited to the vicinity of the Energy Information Center (EIC) located inside the SITE BOUNDARY. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location.

However this calculation has been historically performed assuming an occupancy factor of one (implying continuous occupancy over the entire year).

A X/Q, determined for the Energy Information Center, will be used for this assessment.

Equations 5-1 and 5-2 in Section 5.1.2 should be used for this assessment.

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6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

6.1 Requirement

REMP The radiological environmental monitoring program shall be conducted as specified in Table 6-1, based on locations determined using data from the pre-operational monitoring period; and/or the operational monitoring period indicating a need to make changes in the program.

Applicability: At all times.

Action:

a. With the radiological environmental monitoring program not being conducted as specified in Table 6-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, as required by Section 7.2, a description of the reasons for not conducting the program as required and the plans 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 6-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to A MEMBER OF THE PUBLIC is less than the calendar year limits of Section 4.4, 4.1 and 4.2. When more than one of the radionuclides in Table 6-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + 2 1.0 reporting level (l) reporting level (2) . ..

When radionuclides other than those in Table 6-2 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 is equal to or greater than the calendar year limits of Section 4.4, 4.1 and 4.2. 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.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 6-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
  • The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

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6.1.1 Surveillance Requirements

a. The radiological environmental monitoring samples shall be collected pursuant to Table 6-1 from the specific locations given in Table 6-4 and Figure 6-1 and Figure 6-2 and shall be analyzed pursuant to the requirements of Table 6-1, and the detection capabilities required by Table 6-3.

6.1.2 Implementation of the Requirements The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected based on the effluent measurements and modeling of the environmental exposure pathways.

Thus the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from station operation.

This requirement is implemented by Nuclear Administrative and Technical Manual procedures.

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TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations' Collection Frequency' of Analyslsd A1rborn Samples from 5 locations: 4 Continuous sampling Gross beta weeklyc, samples at or near the SITE collected weekly, or I-131 weekly; gamma Radioiodine and BOUNDARIES (#14A, 15,29,40) more frequently if isotopic analysis of particulates including 3 different sectors of the required by dust composite (by highest calculated annual average loading. location) quarterly.

ground level D/Q.*

I sample (#40) from areas of special interest, which is from the vicinity of a community having the highest calculated annual average D/Q.

I sample (#6A) from a control I location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.'

Direct radiationb Forty (40) routine monitoring Quarterly Gamma dose stations (#5-40, #42, #44, #46, #50) quarterly.

either with 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 (16 locations);

An outer ring of stations, one in each meteorological sector in the 6-8 km (4-5 mi) range from the site (16 locations); and The balance of the stations (8 locations) 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.

  • D/Q refers to average annual relative ground deposition rate.

64 ODCM Rev. 20

TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequencya of Analysisd Waterborne Surface Water storage reservoir (#60) Monthly composite of Gamma isotopic Evaporation pond #1 (#59) weekly grab sample. analysis monthly; Evaporation pond #2 (#63) tritium quarterly.

Ground 2 onsite wells' (#57, #58) Quarterly grab sample Tritium and gamma isotopic analysis quarterly.

Drinking (well) 3 wells from surrounding Composite sample of I-131 analysis on each residences (#46, #48, #49) that weekly grab samples composite when the would be affected by its discharge. over 2-week period dose calculated for when 1-131 analysis is the consumption of performed, monthly the water is greater composite of weekly than I mrem per grab samples otherwise year.9 Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.

Ingestko Samples from milking animals in Semimonthly for Gamma isotopic and 3 locations within 5 km distant animals on pasture; I-131 analysis I Milk having the highest dose potential. otherwise, monthly. semimonthly when If there are none, 1 sample from animals are on pasture milking animals in each of three or monthly at other areas between 5 and 8 km (3-5 mi) times.

I distant (#51, #54) where doses are calculated to be greater than 1 mrem per year.9 One sample from milking animals at a control location 15 to 30 km (9-18 mi) distant (#53) and in the least prevalent wind direction.

65 ODCM Rev. 20

TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequencya of Analyslsd Food Producitsj 2 samples (#47, #52) of 3 types of Monthly during Gamma isotopic broad leaf vegetation (as available) growing season. analysis.

from locations identified per the criteria of Section 6.2b. of this manual.

I control sample (#62) of 3 types Monthly during Gamma isotopic of broad leaf vegetation (as growing season. analysis.

available) grown 15 to 30 km (9-18 mi) distant in the least prevalent wind direction.e

  • When broad leaf vegetation samples are not available, reports from 4 existing supplemental airborne radioiodine sample locations will be substituted.

66 ODCM Rev. 20

TABLE 6-1 (Continued)

TABLE NOTATION a The number, media, frequency, and location of sampling may vary from site to site. It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question. Actual locations (distance and direction) from the site shall be provided in Table 6-4 and Figure 6-1 or Figure 6-2 in the ODCM. Refer to Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants."

b Regulatory Guide 4.13 provides guidance for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor, and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

c Particulate sample filters shall be analyzed for gross beta 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 or water is greater than 10 times the yearly mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.

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

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

f Groundwater samples should 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.

g The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

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TABLE 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/I) or Gas (pCi/ni) Will) (pCi/kg, wet)

H-3 20,000

  • Mn-54 1,000 Fe-59 400 Co-58 1,000 Co-60 300 Zn-65 300 Zr-Nb-95 400 I-131 2** 0.9 3 100 Cs-134 30 10 60 1,000 Cs-137 50 20 70 2,000 Ba-La-140 200 300
  • For drinking water samples. This is a 40 CFR 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 reporting level of 20 pCi/I may be used.

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TABLE 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS a Lower Limit of Detection (LLD)b Airborne Particulate Fresh Milk Food Products Analysis Water (pCiI) or Gas (pCVM3 ) (pCiL) (pCi/kg, wet)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 Fe-59 30 Co-58, -60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 15 60 Cs-137 18 0.06 18 80 Ba-140 60 60 La-140 15 15 NOTE: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

  • 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.

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Table 6-3 (Continued)

TABLE NOTATION a Guidance for detection capabilities for thermoluminescent dosimeters used for environmental measurements is given in Regulatory Guide 4.13.

b Table 6-3 indicates acceptable detection capabilities for radioactive materials in environmental samples.

These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, 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 4.66s,,

LLDE

  • V
  • 2.22
  • Y
  • exp(-XAt)

Where:

LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume),

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

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

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples (e.g.,

potassium-40 in milk samples). 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. 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 LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

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6.2 Requirement

Land Use Census A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

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 Section 4.2.1, identify the new location(s) in the next Annual Radioactive Effluent Release Report, pursuant to Section 7.1.
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 Section 6.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may then be deleted from the monitoring program.

6.2.1 Surveillance Requirements

a. The land use census shall be conducted during the growing season annually 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 Section 7.2.

6.2.2 Implementation of the Requirements The above Requirement is implemented by Nuclear Administrative and Technical Manual procedures.

  • 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 6-1 shall be followed, including analysis of control samples.

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63 Requirement: Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 6-1, as applicable.

Applicability: At all times.

Action:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.

63.1 Surveillance Requirements

a. A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the methodology and parameters in this manual shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.

63.2 Implementation of the Requirements PVNGS laboratories or contract laboratories which perform analyses for the Radiological Environmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program. The participation includes all of the determinations (sample medium-radionuclide combinations) that are included in the monitoring program.

If deviation from specified limits is identified an investigation is made to determine the reason for the deviation and corrective actions are taken as necessary. The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report.

72 ODCM Rev. 20

TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE SAMPLE NOTE DESIGNATION SITE TYPE (d) (a) LOCATION DESCRIPTION (c) 1 TLD SUP E30 Goodyear 2 TLD SUP ENE24 Scott-Libby School 3 TLD SUP E21 Liberty School 4 TLD SUP E16 Buckeye 4 Air SUP E16 Same as TLD S TLD (b) SP ESE1 1 Palo Verde School 6 TLD (b) Control SSE31 APS Gila Bend substation 6A Air (b) Control SSE13 Old US 80 7 TLD (b) SP SE7 Old US 80 and Arlington School Rd.

I 7A Air SUP ESE3 Arlington School 8 TLD (b) OR SSE4 Southern Pacific Pipeline Rd.

9 TLD (b) OR S5 Southern Pacific Pipeline Rd.

10 TLD (b) OR SE5 355th Ave. and Elliot Rd.

11 TLD (b) OR ESE5 339th Ave. and Dobbins Rd.

12 TLD (b) OR E5 339th Ave. and Buckeye-Salome Rd.

13 TLD (b) IR N1 N site boundary 14 TLD (b) IR NNE2 NNE site boundary 14A Air (b) NNE2 371st Ave. and Buckeye-Salome Rd.

15 TLD (b) IR NE2 NE site boundary, WRF access road 15 Air (b) NE2 Same as TLD 16 TLD (b) IR ENE2 ENE site boundary 17 TLD (b) JR E2 E site boundary 17A Air SUP E3 351st Ave.

18 TLD (b) IR ESE2 ESE site boundary 19 TLD (b) IR SE2 SE site boundary 20 TLD (b) IR SSE2 SSE site boundary 73 ODCM Rev. 20

TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE SAMPLE NOTE DESIGNATION SITE TYPE (d) (a) LOCATION DESCRIPTION (c) 21 TLD (b) IR S3 S site boundary 21 Air SUP S3 Same as TLD 22 TLD (b) IR SSW3 SSW site boundary 23 TLD (b) OR W5 N of Elliot Rd 24 TLD (b) OR SW4 N of Elliot Rd.

25 TLD (b) OR WSW5 N of Elliot Rd.

26 TLD (b) OR SSW4 Duke Property 27 TLD (b) IR SWi SW site boundary 28 TLD (b) IR WSW1 WSW site boundary 29 TLD (b) IR WI W site boundary 29 Air (b) WI Same as TLD 30 TLD (b) IR WNWI WNW site boundary 31 TLD (b) IR NWI NW site boundary 32 TLD (b) IR NNW1 NNW site boundary 33 TLD (b) OR NW4 S of Buckeye Rd.

34 TLD (b) OR NNW5 395th Ave. and Van Buren St.

35 TLD (b) SP NNW8 Tonopah 35 Air SUP NNW8 Same as TLD 36 TLD (b) OR N5 Wintersburg Rd. and Van Buren St.

37 TLD (b) OR NNE5 363rd Ave. and Van Buren St.

38 TLD (b) OR NE5 355th Ave. and Buckeye Rd.

39 TLD (b) OR ENE5 343rd Ave. N of Broadway Rd.

40 TLD (b) SP N2 Wintersburg 40 Air (b) N2 Same as TLD 41 TLD SUP ESE3 Arlington School 42 TLD (b) SP N8 Ruth Fisher School 44 TLD (b) Control ENE35 El Mirage 74 ODCM Rev. 20

TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE SAMPLE NOTE DESIGNATION SITE TYPE (d) (a) LOCATION DESCRIPTION (c)

SUP Transit 45 TLD Control ONSITE Central lab, lead pig 46 TLD (b) SP ENE30 Litchfield Park School 46 Water (b) WD NW9 Local farm 47 TLD SUP E35 Littleton School 47 Vegetation (b) ESE4 Local residence 48 TLD SUP E24 Jackrabbit Trail 48 Water (b) WD SWi Local residence 49 TLD SUP ENEI 1 Palo Verde Rd.

49 Water (b) WD N2 Local residence 50 TLD (b) OR WNW5 S of Buckeye-Salome Rd.

51 Milk (b) NE4 Local residence (goats) 52 Vegetation (b) NNE2 Local residence 53 Milk (b) Control NE36 Local residence (goats)

I 54 Milk (b) NNE4 Local residence (goats)

WD 55 Water SUP SW3 Local residence Ground Water 57 (b) WG onsite Well 27ddc Ground Water 58 (b) WG onsite Well 34abb Surface Water 59 (b) WS onsite Evaporation Pond #1 Surface Water 60 (b) WS onsite Reservoir 62 Vegetation (b) Control ENE26 Commercial produce company Surface Water 63 (b) WS onsite Evaporation Pond #2 75 ODCM Rev. 20

NOTES: (a) Distance and direction are relative to the Unit 2 containment, rounded to the nearest mile.

(b) These samples fulfill the requirements of the ODCM, Table 6-1.

(c) Refer to Figure 6-1 and Figure 6-2 for relative locations of sample sites.

(d) IR - inner ring OR - outer ring SP - school or population center WS - waterborne surface WG - waterborne ground WD - waterborne drinking SUP -designated supplemental sampling location 76 ODCM Rev. 20

Graphic Scale In Miles d 0 1 2 3 4 5

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-~ ~ Ib7-WNW 1f ~ C - T Palo Verde Nuclear Generating Station Figure 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES 0-10 MILES 77 ODCM Rev. 20

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0 AirstripAlrport - Generating Station PROGRAM SAMPLE SITES 0-35 MILES iiBoundary t Schools Located T ThDrmolumina(RD)Samplet Se PO

  • Near Sample Sites m T V vagetleon
  • Municipal Buildings A Air Sample M PMh 0

Figure 6-3 DELETED 79 ODCM Rev. 20

Calculation Manual OffsIte Dose Calculation Palo Verde Nuclear Generating Station Offslte Manual Palo Verde Nuclear Generating Station Buckeye-Salome Road itersburg Road B

-6 Unit 1 Unit 2 Met Tower Unit 3 C

North Legend Centerline of Containment Prperoy 4, Purchased Exclusion Boundary

- Site Boundary Ppety Purchased Elliot Road Outside Exdhion Area Figure 6-4 Scale (miles)

(Ward Road) SITE EXCLUSION AREA BOUNDARY 0 80 ODCM Rev. 20

Palo Verde Nuclear Genemtlng Station Olisite Dose Offsite Calculation Manual Dose Calculation Manual Palo Vterde Nuclear Generating Station Fuel Building Main Steam Operations Exhaust Support Condenser Vacuum Turbine Support Fuel Rulili Containment Structure Combined Exhaust Building Building

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Offsihe Dose Calculation Manual Palo Verde Nuclear Generating Station Graphic Scale In MilseF 0 1 2 1 4 9i KEY TO MAP Paved Road Palo Verde Nuclear

- Unpaved Road Generating Station 4WD Road Boundary HOI-IGI-- Gas Pipeline School ol--o- 0 Oil Pipeline

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4f Airstrip 82 ODCM Rev. 20

7.0 RADIOLOGICAL REPORTS

7.1 Requirement

Annual Radioactive Effluent Release Report

The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual 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 6-4) 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. 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 the ODCM.

The Annual 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 contributions are given Section 5.0 and Regulatory Guide 1.109 Rev. 1, October 1977.

The Annual Radioactive Effluent Release Report shall also include information required by the Technical Requirements Manual, Section 5.0.600.1.

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

83 ODCM Rev. 20

The Annual Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. Container volume,
b. Total curie quantity (specify whether determined by measurement or estimate),
c. Principal radionuclides (specify whether determined by measurement or estimate),
d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

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

Changes to the ODCM shall be submitted in the form of a complete, legible copy as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Changes made to the Process Control Program shall be submitted with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the Process Control Program was made.

84 ODCM Rev. 20

72 Requirement: Annual Radiological Environmental Operating Report

The Annual Radiological Environmental Operating Reports 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, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 6.2.

The Annual Radiological Environmental Operating Reports 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 specified in Table 6-4 and Figure 6-1 and Figure 6-2 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 reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Section 6.3; discussion of all deviations from the sampling schedule of Table 6-1; and discussion of all analyses in which the LLD required by Table 6-3 was not achievable.

  • A single submittal may be made for a multiple unit station.
    • One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

85 ODCM Rev. 20

APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses.

The determination of a controlling location for implementation of IOCFR50 for radioiodines and particulates is known to be a function of:

(1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Equation 5-2 results in the respective equations at the controlling location. The isotopic release rates are based upon the source terms calculated using the PVNGS Environmental Report, Operating License Stage, Table 3.5-12, without carbon.

All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated. These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure. An infant is assumed to be present at all milk pathway locations. A child is assumed to be present at all vegetable garden locations. The ground plane exposure pathway is only considered to be present where an infant is not present. Naturally, inhalation is present everywhere an individual is present.

For the determination of the controlling locations, the highest X/Q and D/Q values, based on the 9 year meteorological data base, for the vegetable garden, cow milk, and goat milk pathways, are selected for each unit. The receptor organ doses have been calculated at each of these locations. Based upon these calculations, it is determined that the controlling receptor pathway is a function of unit location. For Unit 1, the controlling receptor is a garden-child pathway; for releases from Unit 2 and Unit 3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table 4-16, 4-17, or 4-18, which, in turn, is based upon the 1984 Land Use Census. Locations of the nearest residences, gardens and milk animals, as determined in the 1984 Land Use Census, are given in Table 4-16, 4-17, and 4-18.

86 ODCM Rev. 20

APPENDIX B BASES FOR REQUIREMENTS B-2.1 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 the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, 64 of Appendix A to 10 CFR PART 50.

There are two separate radioactive gaseous effluent monitoring systems: the low range effluent monitors for normal plant radioactive gaseous effluents and the high range effluent monitors for post-accident plant radioactive gaseous effluents. The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions. The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the low range monitors.

B-3.1 GASEOUS EFFLUENT - DOSE RATE This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY, in excess of the design objectives of Appendix I to 10 CFR part 50. This requirement is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section H.A and l.C design objectives of Appendix I to 10 CFR part 50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a 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 mremslyear to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year. This requirement does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

This requirement applies to the release of radioactive materials in gaseous effluents from all reactor 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 (LLD). 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 (revised annually).

87 ODCM Rev. 20

B-3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - CONCENTRATION This requirement is provided to ensure that the annual total effective dose equivalent to individual members of the public from the licensed operation does not exceed the requirements of 10 CFR Part 20, due to the accumulated activity in the evaporation ponds from the secondary system discharges.

Restricting the concentrations of the secondary liquid wastes discharged to the onsite evaporation ponds will restrict the quantity of radioactive material that can accumulate in the ponds. This, in turn, provides assurance that in the event of an uncontrolled release of the pond's contents to an UNRESTRICTED AREA, the resulting total effective dose equivalent to individual members of the public at the nearest exclusion area boundary will not exceed the requirements of 10 CFR Part 20.

This requirement applies to the secondary system liquid waste discharges of radioactive materials from all reactor units to the onsite evaporation ponds.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD). 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 (revised annually).

B-4.1 GASEOUS EFFLUENT - DOSE, Noble Gases This requirement is provided to implement Sections ll.B, Il.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section Il.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and 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 the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous 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 10 CFR Part 50, 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 and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.

88 ODCM Rev. 20

B-4.2 GASEOUS EFFLUENT - DOSE - Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days This requirement is provided to implement the requirements of Sections II.C, III.A, IV.A of Appendix I, 10 CFR Part 50. This requirement is the guide set forth in Section ll.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 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 IIl.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases for 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 specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these 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 requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.

B-4.3 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix 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 H.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.

The minimum analysis frequency of 4/M (i.e., at least 4 times per month at intervals no greater than 9 days and a minimum of 48 times a year) is used for certain radioactive gaseous waste sampling in Table 3-1. This will eliminate taking double samples when quarterly and weekly samples are required at the same time.

89 ODCM Rev. 20

B-4A SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - DOSE This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section M.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IVA of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by 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 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section lII.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This requirement applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

B-5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE This requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.1301(d). The requirement specifies the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Even if a site was to contain up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units (including outside storage tanks, etc.)

are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a 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, submittal of the Special Report within 30 days 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 Part 190.11 and 10 CFR Part 20.2203(a)(4), 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 other requirements for dose limitation of 10 CFR Part 20, as addressed in Section 3.2 and 3.1 of the ODCM. 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.

ODCM Rev. 20 90

B-6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

The Radiological Environmental Monitoring Program required by this requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station 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. 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 (LLD). The LLDs required by Table 6-3 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 posteriri (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 (revised annually).

B-6.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/n12.

B-6.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

91 ODCM Rev. 20

APPENDIX C DEFINITIONS Note:

The following definitions were derived from the Palo Verde Nuclear Generating Station Technical Specifications. These selected definitions support those portions of the Technical Specifications which were transferred to the ODCM and have been incorporated into the Requirements sections of the ODCM.

Definitions:

The defined terms of this section appear in capitalized type and are applicable throughout the Requirements sections of this ODCM.

ACTION ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION See the Technical Specification definition.

CHANNELCHECK See the Technical Specification definition.

CHANNEL FUNCTIONAL TEST See the Technical Specification definition.

DOSE EQU1IVALENT I-131 See the Technical Specification definition.

EREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table C-1.

GASEOUS RADWASTE SYSTEM A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

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APPENDIX C DEFINITIONS (Continued)

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

MODE See the Technical Specification definition.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

PREPURGING 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 condition, in such a manner that replacement air or gas is required to purify the confinement.

AT1EI THERMAL POWER See the Technical Specification definition.

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

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.

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APPENDIX C DEFINITIONS (Continued)

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

VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT 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. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

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.

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TABLE C-1 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

w At least once per 7 days.

At least 4 times per month at intervals no greater than 4/M 9 days and a minimum of 48 times per year.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

ANNUALLY At least once per 365 days R At least once per 18 months.

p Completed prior to each release.

S/U Prior to reactor startup.

N.A. Not Applicable.

95 ODCM Rev. 20

APPENDIX D REFERENCES 1 Title 10, Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation."

2 Title 10, Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities."

3 Title 40, Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations."

4 Federal Register, Vol. 58, No. 245, Thursday, December 23, 1993, Notices, pages 68170-68179.

5 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.

6 Regulatory Guide 1.109, "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,"

Revision 1, October 1977.

7 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.

8 Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.

9 NUREG-0133, Preparation of Radiological Effluent Technical Specifications For Nuclear Power Plants, Oct. 1978.

10 NUREG 0841, "Final Environmental Statement Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3", Section 5.9.1.4, February, 1982.

11 NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactor", Arpil 1991.

12 Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station, December 1981.

13 PVNGS Updated Final Safety Analysis Report 14 Calculation 13-NC-ZY-252, "Annual Average Dose from Normal Operation Liquid Discharge from the Evaporation Pond", Rev 0.

15 Calculation 13-NC-ZY-253, "Annual Average Dose from Normal Operation Airborne Direct and Sky Shine from the Evaporation Pond", Rev 0.

16 Calculation 13-NC-ZY-254, "Radiation Dose Due to an Evaporation Pond Dike Failure During a Seismic Event", Rev. 0.

96 ODCM Rev. 20

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