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{{#Wiki_filter:Enclosure Palo Verde Nuclear Generating Station Units 1, 2, & 3 2016 Annual Radioactive Effluent Release Report
{{#Wiki_filter:Technical Specification 5.6.3 Technical Requirements Manual 3.7.102.4 Qaps                                                                                Palo Verde Nuclear Generating Station PO Box 52034 102-07491 TNW/MDD/TMJ                                                              Phoenix, Arizona 85072-2034 April 21, 2017                                                                    Maii Station 7636 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001


TABLE OF CONTENTS SECTION PAGE INTRODUCTION ..................................................................................................................
==Dear Sirs:==
......................... 5 BIBLIOGR APHY ..................................................................................................................
.......................... 6 APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS........................... 7 APPENDIX B METE OROLOGY ........................................................................................................
.......... 61 APPENDIX C DOSE CALCULATIONS ..................................................................................................
..... 84 APPENDIX D NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING ................................ 93 LIST OF TABLES TABLE PAGE  1 Evaporation P ond Data .........................................................................................................
............................ 17 2 Batch Releas e Data ............................................................................................................
.............................. 17 3 Units 1, 2 & 3 Gaseous Effluents Average Lower Limit Of Detection .............................................................
.. 18  4 Unit 1 Gaseous Effluents - Su mmation of All Releases ..........................................................................
.......... 19 5 Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ...................... 20 6 Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates .............................................. 21 7 Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines ............................... 22 8 Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates ....................................................... 23  9 Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines .............................................. 24 10 Unit 1 Gaseous Effluents - Contin uous and Batch - Particulates ................................................................
..... 25  11 Unit 1 Radiation Doses at and Beyond the Site Boundary ........................................................................
....... 26 


LIST OF TABLES TABLE PAGE  12 Unit 2 Gaseous Effluents - Su mmation of All Releases ..........................................................................
==Subject:==
......... 27 13 Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ..................... 28 14 Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates ............................................. 29 15 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines
Palo Verde Nuclear Generating Station (PVNGS)
............................... 30 16 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates ...................................................... 31 17 Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines ............................................. 32 18 Unit 2 Gaseous Effluents - Contin uous and Batch - Particulates ................................................................
Units 1, 2, 3 and Independent Spent Fuel Storage Installation Docket Nos. STN 50-528/529/530 and 72-44 Annual Radioactive Effluent Release Report 2016 In accordance with Technical Specification 5.6.3, the annual radioactive effluent release report for 2016 is enclosed.
..... 33 19 Unit 2 Radiation Doses at and Beyond the Site Boundary ........................................................................
PVNGS Technical Requirement Manual section 3.7.102.4 requires an annual report to be prepared and submitted if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 micro curies of removable radiation. There were no events in 2016 that met this reporting threshold.
....... 34 20 Unit 3 Gaseous Effluents - Su mmation of All Releases ..........................................................................
No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Michael DiLorenzo, Licensing Section Leader, at (623) 393-3495.
......... 35 21 Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ..................... 36 22 Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates ............................................. 37 23 Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines
Sincerely, Weber, Thomas DN: cn=Weber, Thomas N(Z00499)
............................... 38 24 Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates ...................................................... 39 25 Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines ............................................. 40 26 Unit 3 Gaseous Effluents - Contin uous and Batch - Particulates ................................................................
N(Z00499)        Reason: l am approving this document Date: 2017.04.21 14:47:11 -07'00' Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/TMJ/sma
..... 41 27 Unit 3 Radiation Doses at and Beyond the Site Boundary ........................................................................
....... 42 


LIST OF TABLES TABLE PAGE 28 Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines - Total By Quarter ................ 43 29 Units 1, 2, and 3 Gaseous E ffluents - Continuous - Particulates - Total By Quarter ........................................ 44 30 Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total By Quarter
==Enclosure:==
.......................... 45 31 Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total By Quarter ................................................. 46 32 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines - Total By Quarter 47 33 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Quarter ....................... 48 34 Units 1, 2 and 3 Gaseous Effluents- Continuous - Fission Gases and Iodine - Total By Unit .......................... 49 35 Units 1, 2 and 3 Gaseous E ffluents- Continuous - Particulates - Total By Unit ................................................ 50 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total By Unit ................................... 51 37 Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates - Total By Unit ......................................................
Palo Verde Nuclear Generating Station Units 1, 2 and 3 2016 Annual Radioactive Effluent Release Report cc:  K. M. Kennedy              NRC Region IV Regional Administrator S. P. Lingam              NRC NRR Project Manager for PVNGS M. M. Watford              NRC NRR Project Manager C. A. Peabody              NRC Senior Resident Inspector for PVNGS A. V. Godwin              Arizona Radiation Regulatory Agency (ARRA)
... 52 38 Units 1, 2 and 3 Gaseous E ffluents- Continuous and Batch - Fission Gases and Iodine - Total By Unit ......... 53 39 Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Unit .............................. 54 40 Estimation of Total Percent Error .............................................................................................
T. Morales                Arizona Radiation Regulatory Agency (ARRA)
......................... 55 41 Effluent Monitoring Instrumentation Out of Service Greater than 30 Days ...................................................... 56 42 Solid Waste Summary ...........................................................................................................
A member of the STARS Alliance LLC Callaway
........................... 57 43 Doses To Special Locations For 2016 ...........................................................................................
* Diablo Canyon
................... 87 44 Integrated Population Dose for 2016 ...........................................................................................
* Palo Verde
..................... 88 45 Summary of Individual Doses for 2016 ..........................................................................................
* Wolf Creek
.................. 92 


INTRODUCTION This report summarizes effluent and waste disposal source term data, meteorological data, and doses from radioactive effluents for the Palo Verde Nuclear Generating Station (PVNGS) for the period of January through December 2016. The data presented meets the reporting requirements of Regulatory Guide 1.21 (Revision 1, June 1974) of the U.S. Nuclear Regulatory Commission and the PVNGS Technical Specifications. 
Enclosure Palo Verde Nuclear Generating Station Units 1, 2, & 3 2016 Annual Radioactive Effluent Release Report


BIBLIOGRAPHY U.S. Nuclear Regulatory Commission, 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, 1974.
PALO VERDE NUCLEAR GENERATING STATION UNITS 1,2 AND 3 2016 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT USNRC Docket No. STN 50-528/529/530 RCTSA11566 e 4 McDowell,      Digitally signed by McDowell, Joshua (Z08270)
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23 (Safety Guide 23), "Onsite Meteorological Programs," 1972.
DN: cn=McDowel(. Joshua (Z08270)
U.S. Nuclear Regulatory Commission, NUREG/CR-2919, "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," 1982.
Joshua          Reason; I am the author of this document Prepared by:  (Z08270)        Date; 2017.04.14 17:42:41
U.S. Nuclear Regulatory Commission, NUREG-0579, "Users Guide to GASPAR C ode," June 1980. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, 1977.
                                -OT-OO*
U.S. Nuclear Regulatory Commission, NUREG-0172, "Age-specific Radiation Dose Commitment Factors for a One-Year Chronic Intake," 1977.
Routolo,      M(Z99739)
U.S. Nuclear Regulatory Commission, NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," 1978.
Oigtially signed by RouUilo, Robert Reviewed by: Robert          ON: cneRoototo, Robert M(Ze9739)
Reason: t have reviewed trtls document M(Z99739)
Date: 2017.04,15 05:55:37 -07W Approved by:                Digitally signed by Moeller, Carl (Z09119)
DN: cn=Moeller, Carl Carl          (Z09119)
Date: 2017.04.15 (Z09119)      07:46:51 -07'00'
 
TABLE OF CONTENTS SECTION                                                                                                                                          PAGE INTRODUCTION ........................................................................................................................................... 5 BIBLIOGRAPHY ............................................................................................................................................ 6 APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS........................... 7 APPENDIX B METEOROLOGY .................................................................................................................. 61 APPENDIX C DOSE CALCULATIONS ....................................................................................................... 84 APPENDIX D NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING ................................ 93 LIST OF TABLES TABLE                                                                                                                                                    PAGE 1    Evaporation Pond Data ..................................................................................................................................... 17 2    Batch Release Data .......................................................................................................................................... 17 3    Units 1, 2 & 3 Gaseous Effluents Average Lower Limit Of Detection ............................................................... 18 4    Unit 1 Gaseous Effluents - Summation of All Releases .................................................................................... 19 5    Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ...................... 20 6    Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates.............................................. 21 7    Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines ............................... 22 8    Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates ....................................................... 23 9    Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines .............................................. 24 10  Unit 1 Gaseous Effluents - Continuous and Batch - Particulates ..................................................................... 25 11  Unit 1 Radiation Doses at and Beyond the Site Boundary ............................................................................... 26 PVNGS 2016 ARERR                                                                                                                                              Page 2
 
LIST OF TABLES TABLE                                                                                                                                PAGE 12  Unit 2 Gaseous Effluents - Summation of All Releases ................................................................................... 27 13  Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ..................... 28 14  Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates ............................................. 29 15  Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines............................... 30 16  Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates ...................................................... 31 17  Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines ............................................. 32 18  Unit 2 Gaseous Effluents - Continuous and Batch - Particulates ..................................................................... 33 19  Unit 2 Radiation Doses at and Beyond the Site Boundary ............................................................................... 34 20  Unit 3 Gaseous Effluents - Summation of All Releases ................................................................................... 35 21  Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ..................... 36 22  Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates ............................................. 37 23  Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines............................... 38 24  Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates ...................................................... 39 25  Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines ............................................. 40 26  Unit 3 Gaseous Effluents - Continuous and Batch - Particulates ..................................................................... 41 27  Unit 3 Radiation Doses at and Beyond the Site Boundary ............................................................................... 42 PVNGS 2016 ARERR                                                                                                                          Page 3
 
LIST OF TABLES TABLE                                                                                                                                                  PAGE 28  Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines - Total By Quarter ................ 43 29  Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates - Total By Quarter ........................................ 44 30  Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total By Quarter.......................... 45 31  Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total By Quarter ................................................. 46 32  Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines - Total By Quarter 47 33  Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Quarter ....................... 48 34  Units 1, 2 and 3 Gaseous Effluents- Continuous - Fission Gases and Iodine - Total By Unit .......................... 49 35  Units 1, 2 and 3 Gaseous Effluents- Continuous - Particulates - Total By Unit ................................................ 50 36  Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total By Unit ................................... 51 37  Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates - Total By Unit ......................................................... 52 38  Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine - Total By Unit ......... 53 39  Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Unit .............................. 54 40  Estimation of Total Percent Error ...................................................................................................................... 55 41  Effluent Monitoring Instrumentation Out of Service Greater than 30 Days ...................................................... 56 42  Solid Waste Summary ...................................................................................................................................... 57 43  Doses To Special Locations For 2016 .............................................................................................................. 87 44  Integrated Population Dose for 2016 ................................................................................................................ 88 45  Summary of Individual Doses for 2016 ............................................................................................................ 92 PVNGS 2016 ARERR                                                                                                                                            Page 4
 
INTRODUCTION This report summarizes effluent and waste disposal source term data, meteorological data, and doses from radioactive effluents for the Palo Verde Nuclear Generating Station (PVNGS) for the period of January through December 2016. The data presented meets the reporting requirements of Regulatory Guide 1.21 (Revision 1, June 1974) of the U.S. Nuclear Regulatory Commission and the PVNGS Technical Specifications.
PVNGS 2016 ARERR                                                                        Page 5
 
BIBLIOGRAPHY U.S. Nuclear Regulatory Commission, 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, 1974.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23 (Safety Guide 23), Onsite Meteorological Programs, 1972.
U.S. Nuclear Regulatory Commission, NUREG/CR-2919, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, 1982.
U.S. Nuclear Regulatory Commission, NUREG-0579, Users Guide to GASPAR Code, June 1980.
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, Revision 1, 1977.
U.S. Nuclear Regulatory Commission, NUREG-0172, Age-specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, 1977.
U.S. Nuclear Regulatory Commission, NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, 1978.
Technical Specifications, Palo Verde Nuclear Generating Station, Units 1, 2 and 3, Docket No. 50-528/529/530.
Technical Specifications, Palo Verde Nuclear Generating Station, Units 1, 2 and 3, Docket No. 50-528/529/530.
Bechtel Power Corp., "Cooling Tower Blowdown System Solar Evaporation Pond," Sept. 1980.
Bechtel Power Corp., Cooling Tower Blowdown System Solar Evaporation Pond, Sept. 1980.
Generation Engineering, "Geotechnical Exploration for Evaporation Pond #2," Oct. 1986 Letter No. 212-00789-WFQ/RHM, "1989 PVNGS Evaporation Pan Data," Jan. 1989. Offsite Dose Calculation Manual Palo Verde Nuclear Generating Station Units 1, 2 and 3, Rev. 27.
Generation Engineering, Geotechnical Exploration for Evaporation Pond #2, Oct. 1986 Letter No. 212-00789-WFQ/RHM, 1989 PVNGS Evaporation Pan Data, Jan. 1989.
Offsite Dose Calculation Manual Palo Verde Nuclear Generating Station Units 1, 2 and 3, Rev. 27.
NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.
NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.
Calculation 13-NC-CH-0200, Rev 7,FSAR - Primary Coolant Activities (PCA)
Calculation 13-NC-CH-0200, Rev 7,FSAR - Primary Coolant Activities (PCA)
PVNGS 2016 ARERR                                                                          Page 6


APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS
APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS PVNGS 2016 ARERR                                    Page 7


Supplemental Information 1.0 REGULATORY LIMITS 1.1 Liquid Releases 1.1.1 PVNGS ODCM Requirement 3.2 The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:
Supplemental Information 1.0   REGULATORY LIMITS 1.1     Liquid Releases 1.1.1     PVNGS ODCM Requirement 3.2 The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:
5.0E-07 µCi/ml for principal gamma-emitters (except Ce-144) 3.0E-06 µCi/ml for Ce-144 1.0E-06 µCi/ml for I-131.
5.0E-07 Ci/ml for principal gamma-emitters (except Ce-144) 3.0E-06 Ci/ml for Ce-144 1.0E-06 Ci/ml for I-131.
1.0E-03 µCi/ml for H-3 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to:
1.0E-03 Ci/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 µCi/ml for Cs-134 2.0E-06 µCi/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 1.1.2 PVNGS ODCM Requirement 4.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor, to areas at and beyond the SITE BOUNDARY shall be limited:
2.0E-06 Ci/ml for Cs-134 2.0E-06 Ci/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 1.1.2     PVNGS ODCM Requirement 4.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor, to areas at and beyond the SITE BOUNDARY shall be limited:
: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
: b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
: b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
1.2 Gaseous Releases 1.2.1 PVNGS ODCM Requirement 3.1 The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
PVNGS 2016 ARERR                                                                            Page 8
 
1.2     Gaseous Releases 1.2.1   PVNGS ODCM Requirement 3.1 The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:
: a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and
: a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and
: b. For I-131 and I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.
: b. For I-131 and I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.
1.2.2 PVNGS ODCM Requirement 4.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
1.2.2   PVNGS ODCM Requirement 4.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
: a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
: a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
1.2.3 PVNGS ODCM Requirement 4.2 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 shall be limited to the following:
: b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
: a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b. During any calendar year: Less than or equal to 15 mrem to any organ.
1.2.3   PVNGS ODCM Requirement 4.2 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 shall be limited to the following:
1.2.4 PVNGS ODCM Requirement 4.3 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, 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 when averaged over 31 days, would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
: a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
1.3 Total Dose 1.3.1 PVNGS ODCM Requirement 5.1 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 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
: b. During any calendar year: Less than or equal to 15 mrem to any organ.
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS Air: Release Concentrations are limited to dose rate limits described in section 1.2.1 of this report.
1.2.4   PVNGS ODCM Requirement 4.3 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, 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 when averaged over 31 days, would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
3.0 AVERAGE ENERGY The average energy (E) of the radionuclide mixture in releases of fission and activation gases is not applicable to PVNGS.
PVNGS 2016 ARERR                                                                              Page 9
4.0 MEASUREMENTS   AND   APPROXIMATIONS   OF   TOTAL   RADIOACTIVITY   IN GASEOUS EFFLUENTS For continuous releases, sampling is in accordance with PVNGS ODCM Table 3-1.
 
1.3     Total Dose 1.3.1     PVNGS ODCM Requirement 5.1 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 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
2.0   MAXIMUM PERMISSIBLE CONCENTRATIONS Air: Release Concentrations are limited to dose rate limits described in section 1.2.1 of this report.
3.0   AVERAGE ENERGY The average energy (E) of the radionuclide mixture in releases of fission and activation gases is not applicable to PVNGS.
4.0   MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY                               IN GASEOUS EFFLUENTS For continuous releases, sampling is in accordance with PVNGS ODCM Table 3-1.
Particulate and iodine radionuclides are sampled continuously at the Plant Vent and Fuel Building exhaust points. The particulate filters and charcoal cartridges are exchanged for analysis at least four times per month. Noble gas and tritium are sampled at least once per 31 days. The hourly average Radiation Monitoring System (RMS) effluent monitor readings are used, when available, to account for increases and decreases in noble gas concentrations between noble gas grab samples. The tritium concentration is assumed constant between sampling periods.
Particulate and iodine radionuclides are sampled continuously at the Plant Vent and Fuel Building exhaust points. The particulate filters and charcoal cartridges are exchanged for analysis at least four times per month. Noble gas and tritium are sampled at least once per 31 days. The hourly average Radiation Monitoring System (RMS) effluent monitor readings are used, when available, to account for increases and decreases in noble gas concentrations between noble gas grab samples. The tritium concentration is assumed constant between sampling periods.
For batch releases, sampling is also in accordance with PVNGS ODCM Table 3-1. For containment purges, the noble gas concentration may be adjusted to account for decreases or increases in concentration during the purge using RMS readings. The volume of air released during the purge is determined using the exhaust fan rated flow rate. For Waste Gas Decay Tank releases, the volume released is corrected to standard pressure.
For batch releases, sampling is also in accordance with PVNGS ODCM Table 3-1. For containment purges, the noble gas concentration may be adjusted to account for decreases or increases in concentration during the purge using RMS readings. The volume of air released during the purge is determined using the exhaust fan rated flow rate. For Waste Gas Decay Tank releases, the volume released is corrected to standard pressure.
Effective January 1, 2004, Containment Purge release permits are updated by removing the permit pre-release particulate and iodine activity. This eliminates double accounting for the Containment Purge particulate and iodine activity at the Plant Vent but allows the particulate and iodine activity to be included in the Containment Purge pre-release dose projection.
Effective January 1, 2004, Containment Purge release permits are updated by removing the permit pre-release particulate and iodine activity. This eliminates double accounting for the Containment Purge particulate and iodine activity at the Plant Vent but allows the particulate and iodine activity to be included in the Containment Purge pre-release dose projection.
The Lower Limit of Detection (LLD) of a measurement system is defined in Table 3 - 1 of the PVNGS ODCM. An average LLD for each radionuclide is provided in Table 3.
The Lower Limit of Detection (LLD) of a measurement system is defined in Table 3 - 1 of the PVNGS ODCM. An average LLD for each radionuclide is provided in Table 3.
5.0 BATCH RELEASES 5.1 Gaseous Batch release durations are presented in Table 2.
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5.2 Liquid None. 6.0 ABNORMAL RELEASES None 7.0 OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL PROGRAM (PCP) REVISIONS 7.1 The Offsite Dose Calculation Manual (ODCM) was revised in 2016. A complete copy of the ODCM is attached as Appendix E of this report. Revision 27 of the ODCM went effective on 3/25/2016.
 
7.1 There were no revisions to the Process Control Program (PCP) in 2016.
5.0   BATCH RELEASES 5.1   Gaseous Batch release durations are presented in Table 2.
8.0 EFFLUENTS AND SOLID WASTES 8.1 Gaseous Effluents Gaseous effluent information is presented in Table 1 through Table 41. Incl uded in these tables are summaries of the effluents and estimated total error.
5.2   Liquid None.
8.2 Liquid Effluents There were no liquid effluent releases beyond the Site Boundary from PVNGS.
6.0   ABNORMAL RELEASES None 7.0   OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL PROGRAM (PCP) REVISIONS 7.1   The Offsite Dose Calculation Manual (ODCM) was revised in 2016. A complete copy of the ODCM is attached as Appendix E of this report. Revision 27 of the ODCM went effective on 3/25/2016.
8.3 Solid Waste Solid waste shipments are summarized in Table 42.
7.1   There were no revisions to the Process Control Program (PCP) in 2016.
9.0 MISCELLANEOUS INFORMATION 9.1 EVAPORATION PONDS Releases made to the Evaporation Ponds are limited to the concentrations specified in PVNGS ODCM Requirement 3.2. The Evaporation Ponds were monitored in accordance with PVNGS ODCM Requirement 6.1.
8.0   EFFLUENTS AND SOLID WASTES 8.1   Gaseous Effluents Gaseous effluent information is presented in Table 1 through Table 41. Included in these tables are summaries of the effluents and estimated total error.
The average historical evaporation is approximately 12 inches, per pond, for each of the first and fourth quarters, and 33 inches, per pond, for each of the second and third quarters. Evaporation Pond One is approximately 250 acres. This equates to 3.08E+11 cc evaporated from Pond One for each of the first and fourth quarters and 8.48E+11 cc evaporated from Pond One for each of the second and third quarters. Evaporation Pond Two is approximately 235 acres. The am ount evaporated from Pond Two is 2.90E+11 cc for each of the first and fourth quarters and 7.97E+11 cc for each of the second and third quarters.
8.2   Liquid Effluents There were no liquid effluent releases beyond the Site Boundary from PVNGS.
8.3   Solid Waste Solid waste shipments are summarized in Table 42.
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9.0   MISCELLANEOUS INFORMATION 9.1 EVAPORATION PONDS Releases made to the Evaporation Ponds are limited to the concentrations specified in PVNGS ODCM Requirement 3.2. The Evaporation Ponds were monitored in accordance with PVNGS ODCM Requirement 6.1.
The average historical evaporation is approximately 12 inches, per pond, for each of the first and fourth quarters, and 33 inches, per pond, for each of the second and third quarters. Evaporation Pond One is approximately 250 acres. This equates to 3.08E+11 cc evaporated from Pond One for each of the first and fourth quarters and 8.48E+11 cc evaporated from Pond One for each of the second and third quarters. Evaporation Pond Two is approximately 235 acres. The amount evaporated from Pond Two is 2.90E+11 cc for each of the first and fourth quarters and 7.97E+11 cc for each of the second and third quarters.
Evaporation Pond Three is constructed of two smaller ponds of 90 acres each (3A and 3B). The amount evaporated from each section of Pond Three is 1.11E+11 cc for each of the first and fourth quarters and 3.05E+11 cc for each of the second and third quarters.
Evaporation Pond Three is constructed of two smaller ponds of 90 acres each (3A and 3B). The amount evaporated from each section of Pond Three is 1.11E+11 cc for each of the first and fourth quarters and 3.05E+11 cc for each of the second and third quarters.
Using a site boundary X/Q of 5.0E-05 sec/m 3 for the evaporation ponds and equation 4-3 from the ODCM, the dose from the evaporation ponds to a hypothetical individual at the site boundary, for all pathways, is summarized in Table 1. 9.2 RADIATION MONITORING SYSTEM SETPOINT VERIFICATION Current effluent monitor noble gas channel alert alarm setpoints are based on an assumed one percent failed fuel source term. The current method used for the setpoint values are more reliable than basing the setpoints upon the constantly varying values of the actual noble gas source term presented in Table 38.
Using a site boundary X/Q of 5.0E-05 sec/m 3 for the evaporation ponds and equation 4-3 from the ODCM, the dose from the evaporation ponds to a hypothetical individual at the site boundary, for all pathways, is summarized in Table 1.
9.3 RCS RADIOIODINE (TRM T5.0.600)
9.2   RADIATION MONITORING SYSTEM SETPOINT VERIFICATION Current effluent monitor noble gas channel alert alarm setpoints are based on an assumed one percent failed fuel source term. The current method used for the setpoint values are more reliable than basing the setpoints upon the constantly varying values of the actual noble gas source term presented in Table 38.
9.3   RCS RADIOIODINE (TRM T5.0.600)
There were no cases where primary coolant specific activity exceeded the Technical Specification 3.4.17 limits during the reporting period.
There were no cases where primary coolant specific activity exceeded the Technical Specification 3.4.17 limits during the reporting period.
9.4 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
9.4   INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
There are no radioactive effluents from the NAC-UMS System. Direct dose at the Site Boundary is reported in the Annual Radiological Environmental Operating Report.
There are no radioactive effluents from the NAC-UMS System. Direct dose at the Site Boundary is reported in the Annual Radiological Environmental Operating Report.
9.5 MAJOR CHANGES TO THE RADIOACTIVE WASTE SYSTEMS (liquid, gaseous, and solid).
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None. 9.6 SAMPLES RESULTS FROM GROUNDWATER WELLS THAT ARE NOT DESCRIBED IN THE ODCM AS PART OF THE REMP (NEI 07-07, Industry Groundwater Protection Initiative, August 2007), are included in Appendix D. This initiative provides added assurance that groundwater will not be adversely affected by PVNGS operations.
 
There were no NEI 07-07 reportable leaks or spills.
9.5   MAJOR CHANGES TO           THE RADIOACTIVE WASTE SYSTEMS (liquid, gaseous, and solid).
There were no positive sample results. 9.7 REPORT ADDENDUM There were two addendums to this report. The first is a correction to the 2013 ARERR and the second is a correction to the 2013 ARERR.
None.
10.0 DISCUSSION 10.1 Unit One Unit One operated with a refueling outage (1R19) from April 9, 2016 to May 14, 2016. Maintenance outages: 1M20A September 7, 2016 to September 13, 2016 Estimated number of fuel defects (source: INPO, CDE) Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 0 0 0 0 0 0 0 0 0 0 0 10.2 Unit Two Unit Two operated without a refueling outage during 2016.
9.6   SAMPLES RESULTS FROM GROUNDWATER WELLS THAT ARE NOT DESCRIBED IN THE ODCM AS PART OF THE REMP (NEI 07-07, Industry Groundwater Protection Initiative, August 2007), are included in Appendix D. This initiative provides added assurance that groundwater will not be adversely affected by PVNGS operations.
Maintenance outages: NONE   Estimated number of fuel defects (source: INPO, CDE) Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 0 0 0 0 0 0 0 0 0 0 0 10.3 Unit Three Unit Three operated with a refueling outage (3R19) from October 8, 2016 to November 5, 2016.
There were no NEI 07-07 reportable leaks or spills. There were no positive sample results.
Maintenance outages: 3M19A September 19, 2016 to September 23, 2016.
9.7   REPORT ADDENDUM There were two addendums to this report. The first is a correction to the 2013 ARERR and the second is a correction to the 2013 ARERR.
Estimated number of fuel defects (source: INPO, CDE) Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 0 0 0 0 0 0 0 0 0 0 0 10.4 Carbon-14 Carbon-14 is formed naturally in the upper atmosphere and also is formed in operating nuclear reactors.
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10.0   DISCUSSION 10.1 Unit One Unit One operated with a refueling outage (1R19) from April 9, 2016 to May 14, 2016.
Maintenance outages:
1M20A September 7, 2016 to September 13, 2016 Estimated number of fuel defects (source: INPO, CDE)
Jan   Feb   Mar   Apr   May     Jun     Jul Aug Sep Oct   Nov   Dec 0     0     0     0       0     0       0   0   0   0     0     0 10.2 Unit Two Unit Two operated without a refueling outage during 2016.
Maintenance outages:
NONE Estimated number of fuel defects (source: INPO, CDE)
Jan   Feb   Mar   Apr   May     Jun     Jul Aug Sep Oct   Nov   Dec 0     0     0     0       0     0       0   0   0   0     0     0 10.3 Unit Three Unit Three operated with a refueling outage (3R19) from October 8, 2016 to November 5, 2016.
Maintenance outages:
3M19A September 19, 2016 to September 23, 2016.
Estimated number of fuel defects (source: INPO, CDE)
Jan   Feb   Mar   Apr   May     Jun     Jul Aug Sep Oct   Nov   Dec 0     0     0     0       0     0       0   0   0   0     0     0 PVNGS 2016 ARERR                                                                        Page 14
 
10.4 Carbon-14 Carbon-14 is formed naturally in the upper atmosphere and also is formed in operating nuclear reactors.
Carbon-14 is not a new power plant emission. Because the overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations, carbon-14 may now qualify as a "principal radionuclide" under revised federal regulatory guidance. The levels of other releases have declined, so carbon-14 releases, expressed as a percentage of total releases, have the potential to achieve "principal radionuclide" status (anything greater than one percent of overall radioactivity in effluents) per updated federal regulatory guidance.
Carbon-14 is not a new power plant emission. Because the overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations, carbon-14 may now qualify as a "principal radionuclide" under revised federal regulatory guidance. The levels of other releases have declined, so carbon-14 releases, expressed as a percentage of total releases, have the potential to achieve "principal radionuclide" status (anything greater than one percent of overall radioactivity in effluents) per updated federal regulatory guidance.
The radiation dose to the public from carbon-14 is much lower than regulatory limits and has been a very small contributor to the total radiation dose that Americans receive each year from natural and man-made sources.
The radiation dose to the public from carbon-14 is much lower than regulatory limits and has been a very small contributor to the total radiation dose that Americans receive each year from natural and man-made sources.
Studies by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Research Council's BEIR VII study group and the National Council on Radiation Protection and Measurements all show that the risk associated with low-dose radiation from natural and man-made sources, including nuclear power plants, is negligible.
Studies by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Research Councils BEIR VII study group and the National Council on Radiation Protection and Measurements all show that the risk associated with low-dose radiation from natural and man-made sources, including nuclear power plants, is negligible.
Radiation is measured in units called millirem. The average American is exposed to 620 millirem of radiation every year. Approximately 311 millirem of this comes from natural sources. The majority of the remaining dose (approximately 300 millirem) comes from medical procedures such as CAT scans. Less than one-tenth of a percent of all radiation exposure is from nuclear facilities.  
Radiation is measured in units called millirem. The average American is exposed to 620 millirem of radiation every year. Approximately 311 millirem of this comes from natural sources. The majority of the remaining dose (approximately 300 millirem) comes from medical procedures such as CAT scans. Less than one-tenth of a percent of all radiation exposure is from nuclear facilities.  


==Reference:==
==Reference:==


NCRP Report No. 160, Table 1.1.
NCRPReport No. 160, Table 1.1.
Starting with the 2010 Annual Radioactive Effluent Release Report, PVNGS will include the estimated exposure from carbon-14 in the Appendix C, dose calculations. The PVNGS calculated production of carbon-14 is 18.5 Curies per cycle (500 days) or 13.5 curies per year. Based on published literature, twenty percent (20%) of the carbon-14 released is assumed to be in an inorganic form (CO 2). PVNGS will use an estimated value of 2.7 curies of carbon-14 released, per reactor, per year. The 2.7 curies will be divided equally between each quarter (0.68 curies per reactor, per quarter). Appendix C, dose calculations include this estimated carbon-14 dose. Appendix C also includes the dose excluding carbon-14 for comparison with historical reports.
Starting with the 2010 Annual Radioactive Effluent Release Report, PVNGS will include the estimated exposure from carbon-14 in the Appendix C, dose calculations. The PVNGS calculated production of carbon-14 is 18.5 Curies per cycle (500 days) or 13.5 curies per year. Based on published literature, twenty percent (20%) of the carbon-14 released is assumed to be in an inorganic form (CO2). PVNGS will use an estimated value of 2.7 curies of carbon-14 released, per reactor, per year. The 2.7 curies will be divided equally between each quarter (0.68 curies per reactor, per quarter). Appendix C, dose calculations include this estimated carbon-14 dose. Appendix C also includes the dose excluding carbon-14 for comparison with historical reports.
10.5 Tritium PVNGS does not have a liquid release pathway. Removal of tritium is performed by operation of the Boric Acid Concentrator (BAC) in the release m ode. Comparison of PVNGS annual tritium Curies released to other utilities should be made only after summing both liquid and gaseous tritium Curies released.
10.5 Tritium PVNGS does not have a liquid release pathway. Removal of tritium is performed by operation of the Boric Acid Concentrator (BAC) in the release mode.
10.6 Dose Summary Dose for 2016 was primarily due to the release of tritium. Tritium production is estimated to be 1000 curies per reactor per year. In order to control plant tritium concentrations, tritium releases should match tritium production. For 2016, PVNGS released a total of 2360 curies of tritium (see Table 39).
Comparison of PVNGS annual tritium Curies released to other utilities should be made only after summing both liquid and gaseous tritium Curies released.
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10.6 Dose Summary Dose for 2016 was primarily due to the release of tritium. Tritium production is estimated to be 1000 curies per reactor per year. In order to control plant tritium concentrations, tritium releases should match tritium production. For 2016, PVNGS released a total of 2360 curies of tritium (see Table 39).
Total dose due to releases from all three Units for 2016 were higher than 2015, primarily due to increased releases of tritium.
Total dose due to releases from all three Units for 2016 were higher than 2015, primarily due to increased releases of tritium.
Table 1: Evaporation Pond Data Evaporation Pond 1 (1A, 1B, 1C) Quarter1Quarter2Quarter3Quarter 4 YearHistorical volume of water evaporated (ml) 3.22E+11 8.85E+11 8.85E+11 3.22E+11  Tritium Concentration (uCi/cc) 2.84E-06 4.23E-06 2.38E-06 2.38E-06 Tritium Curies 3.22E-01 1.26E+00 7.22E-01 2.63E-01 2.57E+00Evaporation Pond 2 (2A and 2B)
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Q uarter 1 Q uarter 2 Q uarter 3 Quarter 4 YearHistorical volume of water evaporated (ml) 2.49E+11 7.97E+11 7.97E+11 2.90E+11  Tritium Concentration (uCi/cc) 1.36E-06 1.32E-06 1.80E-06 2.88E-06 Tritium curies 1.73E-01 4.60E-01 5.99E-01 3.66E-01 1.60E+00Evaporation Pond 3 (3A and 3B)
Q uarter 1 Q uarter 2 Q uarter 3 Quarter 4 YearHistorical volume of water evaporated (ml)2.20E+11 3.05E+11 3.05E+11 1.11E+11  3B Tritium Concentration (uCi/cc) 1.48E-06 1.51E-06 2.88E-06 2.27E-06  3B Tritium curies 1.63E-01 4.55E-01 8.69E-01 2.49E-01 1.74E+00Dose (mRem) Quarter 1Quarter 2Quarter 3Quarter 4 Year Pond 1 3.80E-031.34E-028.60E-033.13E-03 2.89E-02Pond 2 2.40E-03 6.38E-03 8.31E-03 5.08E-03 2.22E-02Pond 3 2.26E-03 6.31E-03 1.20E-02 3.45E-03 2.41E-02 Total 8.46E-03 2.61E-02 2.90E-02 1.17E-02 7.52E-02 Table 2: Batch ReleaseDataAll times are in hours Unit 1 Unit 2 Unit 3 Januar y - June Number of batch releases 442016 Total time period for batch releases 1901.2158.8276.17 Maximum time period for a batch release168.0035.2753.70 Avera ge time period for a batch release43.212.944.76 Minimum time period for a batch release0.100.310.60 July - December Number of batch releases 232447 Total time period for batch releases 322.131184.671908.40Maximum time period for a batch release100.851045.92168.00 Average time period for a batch release14.0149.3640.60 Minimum time period for a batch release0.570.570.02 January - December Number of batch releases 674463 Total time period for batch releases 2223.341243.501984.57Maximum time period for a batch release168.001045.92168.00 Average time period for a batch release33.1828.2631.50 Minimum time period for a batch release0.100.310.02 Table 3: Units 1, 2 & 3 Gaseous Effluents Average Lower Limit Of Detection
µCi/cc Nuclide Continuous Batch Nuclide Continuous Batch Antimony-122 2.20E-13 1.90E-11 Argon-41 4.50E-08 4.50E-08 Antimony-124 8.40E-14 1.70E-11 Krypton-85 7.40E-06 7.40E-06 Barium-140 3.40E-13 5.70E-11 Krypton-85m 2.20E-08 2.20E-08 Bromine-82 3.30E-13 1.40E-11 Krypton-87 5.70E-08 5.70E-08 Cerium-141 8.70E-14 3.10E-11 Krypton-88 7.40E-08 7.40E-08 Cerium-144 3.60E-13 6.50E-11 Xenon-125 2.20E-08 2.20E-08 Cesium-134 1.00E-13 2.60E-11 Xenon-127 2.10E-08 2.10E-08 Cesium-137 8.10E-14 1.70E-11 Xenon-131m 9.10E-07 9.10E-07 Cesium-138 5.20E-10 7.30E-10 Xenon-133 6.30E-08 6.30E-08 Chromium-51 6.90E-13 1.40E-10 Xenon-133m 1.90E-07 1.90E-07 Cobalt-58 8.50E-14 1.70E-11 Xenon-135 2.00E-08 2.00E-08 Cobalt-60 1.00E-13 1.90E-11 Xenon-135m 8.90E-08 8.90E-08 Iron-59 1.70E-13 3.20E-11 Xenon-138 2.00E-07 2.00E-07 Lanthanum-140 2.80E-13 2.10E-11 Iodine-131 8.00E-14 7.00E-12 Manganese-54 8.30E-14 1.70E-11 Iodine-132 6.60E-12 1.90E-11 Molybdenum-99 2.40E-13 2.80E-11 Iodine-133 4.70E-13 1.10E-11 Niobium-95 8.70E-14 1.80E-11 Iodine-134 5.90E-11 8.20E-11 Rubidium-88 1.90E-08 1.90E-08 Iodine-135 7.00E-12 5.50E-11 Ruthenium-103 7.40E-14 1.50E-11    Strontium-89 2.15E-15 (1)    Strontium-90 5.60E-16 (1)    Tellurium-123m 6.60E-14 1.50E-11    Tritium 3.80E-07 3.80E-07    Zinc-65 1.90E-13 3.80E-11    Zirconium-95 1.80E-13 4.10E-11    Gross Alpha 3.60E-15 (1)    (1) Not required for batch releases.   


Table 4: Unit 1 Gaseous Effluents - Summation Of All Releases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total For Year Est. Total Error % (1) A. Fission & activation gases
Table 1: Evaporation Pond Data Evaporation Pond 1 (1A, 1B, 1C)                Quarter 1  Quarter 2 Quarter 3 Quarter 4      Year Historical volume of water evaporated (ml) 3.22E+11    8.85E+11  8.85E+11  3.22E+11 Tritium Concentration (uCi/cc)                2.84E-06 4.23E-06 2.38E-06      2.38E-06 Tritium Curies                                3.22E-01 1.26E+00 7.22E-01      2.63E-01    2.57E+00 Evaporation Pond 2 (2A and 2B)                Quarter 1 Quarter 2 Quarter 3  Quarter 4    Year Historical volume of water evaporated (ml) 2.49E+11    7.97E+11  7.97E+11  2.90E+11 Tritium Concentration (uCi/cc)                1.36E-06 1.32E-06 1.80E-06      2.88E-06 Tritium curies                                1.73E-01 4.60E-01 5.99E-01      3.66E-01    1.60E+00 Evaporation Pond 3 (3A and 3B)                Quarter 1 Quarter 2 Quarter 3  Quarter 4    Year Historical volume of water evaporated (ml) 2.20E+11        3.05E+11  3.05E+11  1.11E+11 3B Tritium Concentration (uCi/cc)              1.48E-06    1.51E-06  2.88E-06  2.27E-06 3B Tritium curies                              1.63E-01    4.55E-01  8.69E-01  2.49E-01    1.74E+00 Dose (mRem)                                    Quarter 1 Quarter 2 Quarter 3  Quarter 4    Year Pond 1                                        3.80E-03    1.34E-02  8.60E-03  3.13E-03    2.89E-02 Pond 2                                        2.40E-03    6.38E-03  8.31E-03  5.08E-03    2.22E-02 Pond 3                                        2.26E-03    6.31E-03  1.20E-02  3.45E-03    2.41E-02 Total                                          8.46E-03    2.61E-02  2.90E-02  1.17E-02    7.52E-02 Table 2: Batch Release Data All times are in hours                    Unit 1        Unit 2      Unit 3 January - June Number of batch releases                                  44            20          16 Total time period for batch releases                    1901.21        58.82        76.17 Maximum time period for a batch release                  168.00        35.27        53.70 Average time period for a batch release                  43.21        2.94        4.76 Minimum time period for a batch release                  0.10          0.31        0.60 July - December Number of batch releases                                  23            24          47 Total time period for batch releases                    322.13        1184.67    1908.40 Maximum time period for a batch release                  100.85        1045.92      168.00 Average time period for a batch release                  14.01        49.36        40.60 Minimum time period for a batch release                  0.57          0.57        0.02 January - December Number of batch releases                                  67            44          63 Total time period for batch releases                    2223.34        1243.50    1984.57 Maximum time period for a batch release                  168.00        1045.92      168.00 Average time period for a batch release                  33.18        28.26        31.50 Minimum time period for a batch release                  0.10          0.31        0.02 PVNGS 2016 ARERR                                                                                Page 17
: 1. Total release Ci 1.14E-01 4.67E-01 6.17E-02 5.42E-02 6.97E-01 3.54E+01 2. Average release rate for period  
 
µCi/sec 1.45E-02 5.94E-02 7.76E-03 6.82E-03 2.20E-02
Table 3:
: 3. Percent of ODCM Requirement limit  
Units 1, 2 & 3 Gaseous Effluents Average Lower Limit Of Detection Ci/cc Nuclide          Continuous        Batch            Nuclide    Continuous    Batch Antimony-122          2.20E-13      1.90E-11        Argon-41        4.50E-08    4.50E-08 Antimony-124          8.40E-14      1.70E-11        Krypton-85      7.40E-06    7.40E-06 Barium-140            3.40E-13      5.70E-11        Krypton-85m    2.20E-08    2.20E-08 Bromine-82            3.30E-13      1.40E-11        Krypton-87      5.70E-08    5.70E-08 Cerium-141            8.70E-14      3.10E-11        Krypton-88      7.40E-08    7.40E-08 Cerium-144            3.60E-13      6.50E-11        Xenon-125      2.20E-08    2.20E-08 Cesium-134            1.00E-13      2.60E-11        Xenon-127      2.10E-08    2.10E-08 Cesium-137            8.10E-14      1.70E-11        Xenon-131m      9.10E-07    9.10E-07 Cesium-138            5.20E-10      7.30E-10        Xenon-133      6.30E-08    6.30E-08 Chromium-51          6.90E-13      1.40E-10        Xenon-133m      1.90E-07    1.90E-07 Cobalt-58            8.50E-14      1.70E-11        Xenon-135      2.00E-08    2.00E-08 Cobalt-60            1.00E-13      1.90E-11        Xenon-135m      8.90E-08    8.90E-08 Iron-59              1.70E-13      3.20E-11        Xenon-138      2.00E-07    2.00E-07 Lanthanum-140        2.80E-13      2.10E-11        Iodine-131      8.00E-14    7.00E-12 Manganese-54          8.30E-14      1.70E-11        Iodine-132      6.60E-12    1.90E-11 Molybdenum-99        2.40E-13      2.80E-11        Iodine-133      4.70E-13    1.10E-11 Niobium-95            8.70E-14      1.80E-11        Iodine-134      5.90E-11    8.20E-11 Rubidium-88          1.90E-08      1.90E-08        Iodine-135      7.00E-12    5.50E-11 Ruthenium-103        7.40E-14      1.50E-11 Strontium-89          2.15E-15      (1)
% NA (2) NA (2) NA (2) NA (2) NA (2)
Strontium-90          5.60E-16      (1)
Tellurium-123m        6.60E-14      1.50E-11 Tritium              3.80E-07      3.80E-07 Zinc-65              1.90E-13      3.80E-11 Zirconium-95          1.80E-13      4.10E-11 Gross Alpha          3.60E-15      (1)
(1) Not required for batch releases.
PVNGS 2016 ARERR                                                                          Page 18
 
Table 4:
Unit 1 Gaseous Effluents - Summation Of All Releases Total For  Est. Total Error Unit   Quarter 1     Quarter 2   Quarter 3       Quarter 4 Year           % (1)
A. Fission & activation gases
: 1. Total release                           Ci           1.14E-01     4.67E-01     6.17E-02       5.42E-02   6.97E-01       3.54E+01
: 2. Average release rate for period         Ci/sec     1.45E-02     5.94E-02     7.76E-03       6.82E-03   2.20E-02
: 3. Percent of ODCM Requirement limit       %
NA (2)       NA (2)       NA (2)         NA (2)     NA (2)
B. Iodine 131
B. Iodine 131
: 1. Total Iodine 131 Ci < LLD 1.72E-05 < LLD < LLD 1.72E-05 3.32E+01 2. Average release rate for period  
: 1. Total Iodine 131                         Ci           < LLD       1.72E-05     < LLD           < LLD     1.72E-05       3.32E+01
&#xb5;Ci/sec < LLD 2.19E-06 < LLD < LLD 5.44E-07
: 2. Average release rate for period         Ci/sec       < LLD       2.19E-06     < LLD           < LLD     5.44E-07 19                  3. Percent of ODCM Requirement limit       %
: 3. Percent of ODCM Requirement limit  
NA (2)       NA (2)       NA (2)         NA (2)     NA (2)
% NA (2) NA (2) NA (2) NA (2) NA (2)
C. Particulates
C. Particulates
: 1. Particulates with half- lives > 8 days Ci 1.33E-06 1.03E-02 1.52E-06 < LLD 1.03E-02 3.43E+01 2. Average release rate for period  
: 1. Particulates with half- lives > 8 days   Ci           1.33E-06     1.03E-02     1.52E-06         < LLD     1.03E-02       3.43E+01
&#xb5;Ci/sec 1.69E-07 1.31E-03 1.91E-07 < LLD 3.25E-04
: 2. Average release rate for period         Ci/sec     1.69E-07     1.31E-03     1.91E-07         < LLD     3.25E-04
: 3. Percent of ODCM Requirement limit  
: 3. Percent of ODCM Requirement limit       %             NA (2)       NA (2)       NA (2)         NA (2)     NA (2)
% NA (2) NA (2) NA (2) NA (2) NA (2)
: 4. Gross Alpha radioactivity               Ci           < LLD       1.46E-07     < LLD           < LLD       < LLD PVNGS ARERR 2016 D. Tritium
: 4. Gross Alpha radioactivity Ci < LLD 1.46E-07 < LLD < LLD < LLD D. Tritium
: 1. Total release                           Ci         4.95E+02     3.49E+02     1.08E+02       1.03E+02   1.06E+03       3.85E+01
: 1. Total release Ci 4.95E+02 3.49E+02 1.08E+02 1.03E+02 1.06E+03 3.85E+01 2. Average release rate for period  
: 2. Average release rate for period         Ci/sec     6.30E+01     4.44E+01     1.36E+01       1.30E+01   3.35E+01
&#xb5;Ci/sec 6.30E+01 4.44E+01 1.36E+01 1.30E+01 3.35E+01
: 3. Percent of ODCM Requirement limit       %         NA (2)         NA (2)       NA (2)         NA (2)     NA (2)
: 3. Percent of ODCM Requirement limit  
(1) Estimated total error methodology is presented in Table 40.
% NA (2) NA (2) NA (2) NA (2) NA (2)
(2) See Table 11 for percent of ODCM Requirement limits.
(1) Estimated total error methodology is presented in Table 40. (2) See Table 11 for percent of ODCM Requirement limits.
PVNGS 2016 ARERR                                                                                                                      Page 19
19 PVNGS A RERR2016 Table 5: Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02 2.IodinesI-131 Ci < LLD 1.72E-05 < LLD < LLD 1.72E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD < LLD 2.90E-04 Table 6: Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3.Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.59E-03 1.52E-06 < LLD 1.59E-03 Co-60 Ci 1.33E-06 5.21E-04 < LLD < LLD 5.22E-04 Cr-51 Ci < LLD 5.72E-03 < LLD < LLD 5.72E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 9.54E-05 < LLD < LLD 9.54E-05 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.31E-04 < LLD < LLD 1.31E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 1.98E-04 < LLD < LLD 1.98E-04 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.32E-04 < LLD < LLD 1.32E-04 Total Ci 1.33E-06 8.47E-03 1.52E-06 < LLD 8.47E-03 4.TritiumH-3 Ci 2.58E+01 3.73E+01 3.86E+01 2.27E+01 1.24E+02 Table 7: Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 1.14E-01 2.38E-01 6.14E-02 5.42E-02 4.68E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 3.28E-04 1.61E-01 2.28E-04 < LLD 1.62E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 < LLD < LLD 3.33E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 1.14E-01 4.05E-01 6.16E-02 5.42E-02 6.35E-01 2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Table 8: Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD < LLD 1.53E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD 4.01E-04 < LLD < LLD 4.01E-04 Co-60 Ci < LLD 1.52E-04 < LLD < LLD 1.52E-04 Cr-51 Ci < LLD 1.15E-03 < LLD < LLD 1.15E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 8.86E-06 < LLD < LLD 8.86E-06 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 3.44E-05 < LLD < LLD 3.44E-05 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 5.04E-05 < LLD < LLD 5.04E-05 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 5.29E-06 < LLD < LLD 5.29E-06 Total Ci < LLD 1.82E-03 < LLD < LLD 1.82E-03 4.Tritium H-3 Ci 4.69E+02 3.11E+02 6.96E+01 8.06E+01 9.30E+02 Note 1 - Not required for batch releases Table 9: Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 1.14E-01 2.38E-01 6.14E-02 5.42E-02 4.68E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 3.28E-04 2.23E-01 2.28E-04 < LLD 2.23E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 < LLD < LLD 3.33E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 1.14E-01 4.66E-01 6.16E-02 5.42E-02 6.97E-01 2. Iodines I-131 Ci < LLD 1.72E-05 < LLD < LLD 1.72E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD < LLD 2.90E-04 Table 10: Unit 1 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD < LLD 1.53E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.99E-03 1.52E-06 1.52E-06 1.99E-03 Co-60 Ci 1.33E-06 6.73E-04 < LLD < LLD 6.74E-04 Cr-51 Ci < LLD 6.87E-03 < LLD < LLD 6.87E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 1.04E-04 < LLD < LLD 1.04E-04 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.65E-04 < LLD < LLD 1.65E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 2.48E-04 < LLD < LLD 2.48E-04 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.37E-04 < LLD < LLD 1.37E-04 Total Ci 1.33E-06 1.03E-02 1.52E-06 1.52E-06 1.03E-02 Total > 8 days Ci 1.33E-06 1.03E-02 1.52E-06 < LLD 1.03E-02 4.Tritium H-3 Ci 4.95E+02 3.48E+02 1.08E+02 1.03E+02 1.05E+03 Table 11: Unit 1 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1Quarter 2Quarter 3Quarter 4 Year totalGamma Air Dose mrad 2.99E-04 6.50E-04 1.61E-04 1.42E-04 1.25E-03 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 % ODCM Limit
% 5.98E-03 1.30E-02 3.22E-03 2.84E-03 1.25E-02 Beta Air Dose mrad 1.06E-04 2.90E-04 5.70E-05 5.02E-05 5.03E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 % ODCM Limit
% 1.06E-03 2.90E-03 5.70E-04 5.02E-04 2.52E-03 Maximum Organ Dose (excluding skin) mrem 1.78E-01 1.29E-01 3.88E-02 3.71E-02 3.83E-01 Age  Teen Teen Teen Teen Teen Organ  Thyroid Lung Thyroid Thyroid Lung ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 % ODCM Limit
% 2.37E+00 1.72E+00 5.17E-01 4.95E-01 2.55E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present. 


Table 12: Unit 2 Gaseous Effluents - Summation Of All Releases Unit  Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total For Year Est. Total Error % (1) A. Fission & activation gases
Table 5:
: 1. Total release Ci 8.56E-02 7.08E-02 9.60E-02 8.95E-02 3.42E-01 3.54E+01 2. Average release rate for period
Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released       Unit     Quarter 1     Quarter 2   Quarter 3     Quarter 4     Year total
&#xb5;Ci/sec 1.09E-02 9.00E-03 1.21E-02 1.13E-02 1.08E-02
: 1. Fission gases Ar-41         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-83m         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-85         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-85m         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-87         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-88         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-89         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Kr-90         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Xe-131m         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Xe-133         Ci       < LLD       6.18E-02      < LLD         < LLD       6.18E-02 Xe-133m         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Xe-135         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Xe-135m         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Xe-137         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Xe-138         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Total       Ci       < LLD       6.18E-02      < LLD         < LLD       6.18E-02
: 3. Percent of ODCM Requirement limit
: 2. Iodines I-131        Ci       < LLD       1.72E-05      < LLD         < LLD       1.72E-05 I-132         Ci       < LLD       2.73E-04      < LLD         < LLD       2.73E-04 I-133         Ci       < LLD         < LLD         < LLD         < LLD         < LLD I-134         Ci       < LLD         < LLD         < LLD         < LLD         < LLD I-135         Ci       < LLD         < LLD         < LLD         < LLD         < LLD Total       Ci       < LLD       2.90E-04      < LLD         < LLD       2.90E-04 PVNGS 2016 ARERR                                                                        Page 20
% NA (2)  NA (2) NA (2) NA (2) NA (2)  B. Iodine 131
: 1. Total Iodine 131 Ci < LLD < LLD < LLD < LLD < LLD 3.32E+01 2. Average release rate for period
&#xb5;Ci/sec < LLD < LLD < LLD < LLD < LLD
: 3. Percent of ODCM Requirement limit
% NA (2)  NA (2)  NA (2) NA (2) NA (2)  C. Particulates
: 1. Particulates with half- lives > 8 days Ci < LLD < LLD < LLD < LLD < LLD 3.43E+01 2. Average release rate for period
&#xb5;Ci/sec < LLD < LLD < LLD < LLD < LLD
: 3. Percent of ODCM Requirement limit
%  NA (2)  NA (2)  NA (2) NA (2) NA (2)  4. Gross Alpha radioactivity Ci < LLD  < LLD < LLD  < LLD  < LLD  D. Tritium
: 1. Total release Ci 4.52E+01 2.93E+01 8.12E+01 9.55E+01 2.51E+02 3.85E+01 2. Average release rate for period
&#xb5;Ci/sec 5.75E+00 3.73E+00 1.02E+01 1.20E+01 7.94E+00
: 3. Percent of ODCM Requirement limit
% NA (2)  NA (2)  NA (2) NA (2) NA (2)  (1) Estimated total error methodology is presented in Table 40. (2) See Table 19 for percent of ODCM Requirement limits.
Table 13: Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD < LLD < LLD Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD 2.IodinesI-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Table 14: Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD 4. Tritium H-3 Ci 3.01E+01 2.93E+01 2.11E+01 1.85E+01 9.90E+01 Table 15: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 7.12E-02 4.88E-02 7.50E-02 7.21E-02 2.67E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci 1.43E-02 1.02E-02 2.09E-02 1.74E-02 6.28E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD 1.33E-04 5.78E-05 1.91E-04 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 8.55E-02 5.90E-02 9.60E-02 8.96E-02 3.30E-01 2.IodinesI-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Table 16: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD 4. Tritium H-3 Ci 1.50E+01 1.89E-02 6.00E+01 7.69E+01 1.52E+02 Note 1 - Not required for batch releases Table 17: Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 7.12E-02 4.88E-02 7.50E-02 7.21E-02 2.67E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci 1.43E-02 1.02E-02 2.09E-02 1.74E-02 6.28E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD 1.33E-04 5.78E-05 1.91E-04 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 8.55E-02 5.90E-02 9.60E-02 8.96E-02 3.30E-01 2.IodinesI-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Table 18: Unit 2 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Total > 8 days Ci < LLD < LLD < LLD < LLD < LLD 4. Tritium H-3 Ci 4.51E+01 2.93E+01 8.11E+01 9.54E+01 2.51E+02 Table 19: Unit 2 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1Quarter 2Quarter 3Quarter 4 Year totalUnit 2  Q1 Q2 Q3 Q4 year Gamma Air Dose mrad 1.89E-04 1.56E-04 1.99E-04 1.91E-04 7.34E-04 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 % ODCM Limit
% 3.78E-03 3.12E-03 3.98E-03 3.82E-03 7.34E-03 Beta Air Dose mrad 7.03E-05 5.80E-05 7.57E-05 7.20E-05 2.76E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 % ODCM Limit
% 7.03E-04 5.80E-04 7.57E-04 7.20E-04 1.38E-03 Maximum Organ Dose (excluding skin) mrem 1.62E-02 1.05E-02 2.91E-02 3.42E-02 9.01E-02 Age  Teen Teen Teen Teen Teen Organ  Thyroid Thyroid Thyroid Thyroid Thyroid ODCM Req. 4.2 Limit
% 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 % ODCM Limit % 2.16E-01 1.40E-01 3.88E-01 4.56E-01 6.01E-01 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present. 


Table 20: Unit 3 Gaseous Effluents - Summation Of All Releases Unit  Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total For Year Est. Total Error % (1) A. Fission & activation gases
Table 6:
: 1. Total release Ci 4.38E-02 4.81E-02 8.04E-02 1.03E-01 2.76E-01 3.54E+01 2. Average release rate for period  
Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released  Unit     Quarter 1      Quarter 2    Quarter 3    Quarter 4    Year total 3.Particulates Ag-110m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ba-140        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Br-82        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ce-141          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ce-144          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Co-57          Ci      < LLD      4.88E-06        < LLD        < LLD      4.88E-06 Co-58          Ci      < LLD      1.59E-03      1.52E-06        < LLD      1.59E-03 Co-60          Ci    1.33E-06      5.21E-04        < LLD        < LLD      5.22E-04 Cr-51        Ci      < LLD      5.72E-03        < LLD        < LLD      5.72E-03 Cs-134        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Cs-136        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Cs-137        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Cs-138        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Fe-59        Ci      < LLD      9.54E-05        < LLD        < LLD      9.54E-05 La-140        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Mn-54          Ci      < LLD      1.31E-04        < LLD        < LLD      1.31E-04 Mo-99          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Nb-95          Ci      < LLD      1.98E-04        < LLD        < LLD      1.98E-04 Os-191          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Rb-88          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ru-103          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ru-106          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sb-122        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sb-124        Ci      < LLD      7.86E-05        < LLD        < LLD      7.86E-05 Sb-125        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Se-75          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sn-113m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sr-89        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sr-90        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Tc-99m        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Te-123m        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Zn-65        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Zr-95        Ci      < LLD      1.32E-04        < LLD        < LLD      1.32E-04 Total        Ci    1.33E-06      8.47E-03      1.52E-06        < LLD      8.47E-03 4.Tritium H-3          Ci    2.58E+01      3.73E+01      3.86E+01      2.27E+01    1.24E+02 PVNGS 2016 ARERR                                                                          Page 21
&#xb5;Ci/sec 5.57E-03 6.12E-03 1.01E-02 1.30E-02 8.73E-03
 
: 3. Percent of ODCM Requirement limit  
Table 7:
% NA (2) NA (2) NA (2) NA (2) NA (2)
Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released    Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4    Year total
: 1. Fission gases Ar-41          Ci    1.14E-01      2.38E-01    6.14E-02      5.42E-02    4.68E-01 Kr-83m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-85          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-85m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-87          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-88          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-89          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-90          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-131m          Ci      < LLD        1.24E-03      < LLD        < LLD      1.24E-03 Xe-133          Ci    3.28E-04      1.61E-01    2.28E-04      < LLD      1.62E-01 Xe-133m          Ci      < LLD        1.02E-03      < LLD        < LLD      1.02E-03 Xe-135          Ci      < LLD        3.33E-03      < LLD        < LLD      3.33E-03 Xe-135m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-137          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-138          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Total          Ci    1.14E-01      4.05E-01    6.16E-02      5.42E-02    6.35E-01
: 2. Iodines I-131          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-132          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-133          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-134          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-135          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Total          Ci      < LLD        < LLD        < LLD        < LLD        < LLD PVNGS 2016 ARERR                                                                          Page 22
 
Table 8:
Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released  Unit    Quarter 1      Quarter 2      Quarter 3  Quarter 4  Year total
: 3. Particulates Ag-110m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ba-140        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Br-82        Ci      < LLD        1.53E-05        < LLD      < LLD    1.53E-05 Ce-141        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ce-144        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Co-57        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Co-58        Ci      < LLD        4.01E-04        < LLD      < LLD    4.01E-04 Co-60        Ci      < LLD        1.52E-04        < LLD      < LLD    1.52E-04 Cr-51        Ci      < LLD        1.15E-03        < LLD      < LLD    1.15E-03 Cs-134        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-136        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-137        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-138        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Fe-59        Ci      < LLD        8.86E-06        < LLD      < LLD    8.86E-06 La-140        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Mn-54        Ci      < LLD        3.44E-05        < LLD      < LLD    3.44E-05 Mo-99        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Nb-95        Ci      < LLD        5.04E-05        < LLD      < LLD    5.04E-05 Os-191        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Rb-88        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ru-103        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ru-106        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-122        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-124        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-125        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Se-75        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sn-113m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sr-89        Ci      Note 1          Note 1        Note 1      Note 1    Note 1 Sr-90        Ci      Note 1          Note 1        Note 1      Note 1    Note 1 Tc-99m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Te-123m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Zn-65        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Zr-95        Ci      < LLD        5.29E-06        < LLD      < LLD    5.29E-06 Total        Ci      < LLD        1.82E-03        < LLD      < LLD    1.82E-03 4.Tritium H-3        Ci    4.69E+02        3.11E+02      6.96E+01    8.06E+01  9.30E+02 Note 1 - Not required for batch releases PVNGS 2016 ARERR                                                                        Page 23
 
Table 9:
Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released  Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4  Year total
: 1. Fission gases Ar-41        Ci    1.14E-01        2.38E-01    6.14E-02    5.42E-02    4.68E-01 Kr-83m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-85        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-85m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-87        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-88        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-89        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-90        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-131m        Ci      < LLD        1.24E-03      < LLD        < LLD      1.24E-03 Xe-133        Ci    3.28E-04        2.23E-01    2.28E-04      < LLD      2.23E-01 Xe-133m        Ci      < LLD        1.02E-03      < LLD        < LLD      1.02E-03 Xe-135        Ci      < LLD        3.33E-03      < LLD        < LLD      3.33E-03 Xe-135m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-137        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-138        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci    1.14E-01        4.66E-01    6.16E-02    5.42E-02    6.97E-01
: 2. Iodines I-131        Ci      < LLD        1.72E-05      < LLD        < LLD      1.72E-05 I-132        Ci      < LLD        2.73E-04      < LLD        < LLD      2.73E-04 I-133        Ci      < LLD          < LLD        < LLD        < LLD      < LLD I-134        Ci      < LLD          < LLD        < LLD        < LLD      < LLD I-135        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci      < LLD        2.90E-04      < LLD        < LLD      2.90E-04 PVNGS 2016 ARERR                                                                        Page 24
 
Table 10:
Unit 1 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released  Unit  Quarter 1      Quarter 2    Quarter 3    Quarter 4 Year total
: 3. Particulates Ag-110m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ba-140        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Br-82        Ci      < LLD        1.53E-05      < LLD        < LLD    1.53E-05 Ce-141        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ce-144        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Co-57        Ci      < LLD        4.88E-06      < LLD        < LLD    4.88E-06 Co-58        Ci      < LLD        1.99E-03    1.52E-06      1.52E-06  1.99E-03 Co-60        Ci    1.33E-06        6.73E-04      < LLD        < LLD    6.74E-04 Cr-51        Ci      < LLD        6.87E-03      < LLD        < LLD    6.87E-03 Cs-134        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-136        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-137        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-138        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Fe-59        Ci      < LLD        1.04E-04      < LLD        < LLD    1.04E-04 La-140        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Mn-54        Ci      < LLD        1.65E-04      < LLD        < LLD    1.65E-04 Mo-99        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Nb-95        Ci      < LLD        2.48E-04      < LLD        < LLD    2.48E-04 Os-191        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Rb-88        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ru-103        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ru-106        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-122        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-124        Ci      < LLD        7.86E-05      < LLD        < LLD    7.86E-05 Sb-125        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Se-75        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sn-113m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sr-89        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sr-90        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Tc-99m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Te-123m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Zn-65        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Zr-95        Ci      < LLD        1.37E-04      < LLD        < LLD    1.37E-04 Total        Ci    1.33E-06        1.03E-02    1.52E-06      1.52E-06  1.03E-02 Total > 8 days    Ci    1.33E-06        1.03E-02    1.52E-06        < LLD    1.03E-02 4.Tritium H-3        Ci    4.95E+02      3.48E+02      1.08E+02      1.03E+02  1.05E+03 PVNGS 2016 ARERR                                                                        Page 25
 
Table 11:
Unit 1 Radiation Doses At And Beyond The Site Boundary Unit  Quarter 1   Quarter 2     Quarter 3   Quarter 4   Year total Gamma Air Dose      mrad  2.99E-04    6.50E-04      1.61E-04      1.42E-04    1.25E-03 ODCM Req 4.1 Limit    mrad  5.00E+00    5.00E+00      5.00E+00      5.00E+00    1.00E+01
        % ODCM Limit        %    5.98E-03    1.30E-02      3.22E-03      2.84E-03    1.25E-02 Beta Air Dose      mrad  1.06E-04    2.90E-04      5.70E-05      5.02E-05    5.03E-04 ODCM Req 4.1 Limit    mrad  1.00E+01    1.00E+01      1.00E+01      1.00E+01    2.00E+01
        % ODCM Limit        %    1.06E-03    2.90E-03      5.70E-04      5.02E-04    2.52E-03 Maximum Organ Dose mrem    1.78E-01    1.29E-01      3.88E-02      3.71E-02    3.83E-01 (excluding skin)
Age                    Teen        Teen          Teen        Teen        Teen Organ                  Thyroid        Lung        Thyroid      Thyroid      Lung ODCM Req. 4.2 Limit    mrem    7.50E+00    7.50E+00      7.50E+00      7.50E+00    1.50E+01
        % ODCM Limit        %    2.37E+00    1.72E+00      5.17E-01      4.95E-01    2.55E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.
PVNGS 2016 ARERR                                                                            Page 26
 
Table 12:
Unit 2 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit    Quarter 1    Quarter 2  Quarter 3    Quarter 4 Year        % (1)
A. Fission & activation gases
: 1. Total release                           Ci         8.56E-02     7.08E-02   9.60E-02     8.95E-02  3.42E-01   3.54E+01
: 2. Average release rate for period         Ci/sec   1.09E-02      9.00E-03   1.21E-02     1.13E-02 1.08E-02
: 3. Percent of ODCM Requirement limit       %
NA (2)       NA (2)     NA (2)       NA (2)   NA (2)
B. Iodine 131
B. Iodine 131
: 1. Total Iodine 131 Ci < LLD < LLD < LLD 2.35E-05 2.35E-05 3.32E+01 2. Average release rate for period  
: 1. Total Iodine 131                         Ci           < LLD         < LLD       < LLD       < LLD    < LLD    3.32E+01
&#xb5;Ci/sec < LLD < LLD < LLD 2.96E-06 7.43E-07
: 2. Average release rate for period         Ci/sec     < LLD         < LLD       < LLD        < LLD    < LLD
: 3. Percent of ODCM Requirement limit  
: 3. Percent of ODCM Requirement limit       %           NA (2)         NA (2)     NA (2)       NA (2)   NA (2)
% NA (2) NA (2) NA (2) NA (2) NA (2)
C. Particulates
C. Particulates
: 1. Particulates with half- lives > 8 days Ci < LLD < LLD < LLD 1.40E-04 1.40E-04 3.43E+01 2. Average release rate for period  
: 1. Particulates with half- lives > 8 days   Ci
&#xb5;Ci/sec < LLD < LLD < LLD 1.76E-05 4.41E-06
                                                          < LLD        < LLD      < LLD       < LLD     < LLD     3.43E+01
: 3. Percent of ODCM Requirement limit  
: 2. Average release rate for period         Ci/sec     < LLD         < LLD       < LLD        < LLD    < LLD
% NA (2) NA (2) NA (2) NA (2) NA (2)
: 3. Percent of ODCM Requirement limit       %           NA (2)       NA (2)     NA (2)       NA (2)   NA (2)
: 4. Gross Alpha radioactivity Ci < LLD 1.68E-08 < LLD < LLD < LLD D. Tritium
: 4. Gross Alpha radioactivity               Ci           < LLD        < LLD       < LLD       < LLD     < LLD D. Tritium
: 1. Total release Ci 6.92E+01 2.73E+01 5.82E+02 3.71E+02 1.05E+03 3.85E+01 2. Average release rate for period  
: 1. Total release                           Ci         4.52E+01     2.93E+01   8.12E+01    9.55E+01  2.51E+02    3.85E+01
&#xb5;Ci/sec 8.80E+00 3.47E+00 7.32E+01 4.67E+01 3.32E+01
: 2. Average release rate for period         Ci/sec   5.75E+00     3.73E+00   1.02E+01     1.20E+01 7.94E+00
: 3. Percent of ODCM Requirement limit  
: 3. Percent of ODCM Requirement limit       %
% NA (2) NA (2) NA (2) NA (2) NA (2)
NA (2)       NA (2)     NA (2)       NA (2)   NA (2)
(1) Estimated total error methodology is presented in Table 40. (2) See Table 27 for percent of ODCM Requirement limits.
(1) Estimated total error methodology is presented in Table 40.
Table 21: Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD < LLD < LLD Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD 2.IodinesI-131 Ci < LLD < LLD < LLD 2.35E-05 2.35E-05 I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD 3.28E-05 3.28E-05 Table 22: Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 2.19E-05 2.19E-05 Co-60 Ci < LLD < LLD < LLD 7.52E-06 7.52E-06 Cr-51 Ci < LLD < LLD < LLD 4.49E-06 4.49E-06 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD 3.53E-05 3.53E-05 4. Tritium H-3 Ci 2.92E+01 2.73E+01 2.43E+01 1.09E+02 1.90E+02 Table 23: Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 4.38E-02 4.81E-02 8.04E-02 5.10E-02 2.23E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD 5.23E-02 5.23E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 4.38E-02 4.81E-02 8.04E-02 1.03E-01 2.76E-01 2.IodinesI-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Table 24: Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD 3.07E-06 3.07E-06 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 3.33E-05 3.33E-05 Co-60 Ci < LLD < LLD < LLD 2.27E-05 2.27E-05 Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD 1.34E-07 1.34E-07 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD 2.72E-05 2.72E-05 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD 2.09E-05 2.09E-05 Total Ci < LLD < LLD < LLD 1.07E-04 1.07E-04 4. Tritium H-3 Ci 4.00E+01 2.48E-02 5.58E+02 2.62E+02 8.60E+02 Note 1 - Not required for batch releases Table 25: Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 4.38E-02 4.81E-02 8.04E-02 5.10E-02 2.23E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD 5.23E-02 5.23E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 4.38E-02 4.81E-02 8.04E-02 1.03E-01 2.76E-01 2.IodinesI-131 Ci < LLD < LLD < LLD 2.35E-05 2.35E-05 I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD 3.28E-05 3.28E-05 Table 26: Unit 3 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD 3.07E-06 3.07E-06 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 5.52E-05 5.52E-05 Co-60 Ci < LLD < LLD < LLD 3.02E-05 3.02E-05 Cr-51 Ci < LLD < LLD < LLD 4.49E-06 4.49E-06 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD 1.34E-07 1.34E-07 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD 2.72E-05 2.72E-05 Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD 2.09E-05 2.09E-05 Total Ci < LLD < LLD < LLD 1.43E-04 1.43E-04 Total > 8 days Ci < LLD < LLD < LLD 1.40E-04 1.40E-04 4. Tritium H-3 Ci 6.92E+01 2.73E+01 5.82E+02 3.71E+02 1.05E+03 Table 27: Unit 3 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1Quarter 2Quarter 3Quarter 4 Year totalGamma Air Dose mrad 1.15E-04 1.26E-04 2.11E-04 1.39E-04 5.92E-04 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 % ODCM Limit
(2) See Table 19 for percent of ODCM Requirement limits.
% 2.30E-03 2.52E-03 4.22E-03 2.78E-03 5.92E-03 Beta Air Dose mrad 4.06E-05 4.46E-05 7.45E-05 6.28E-05 2.22E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 % ODCM Limit
PVNGS 2016 ARERR                                                                                                              Page 27
% 4.06E-04 4.46E-04 7.45E-04 6.28E-04 1.11E-03 Maximum Organ Dose (excluding skin) mrem 2.48E-02 9.80E-03 2.09E-01 1.33E-01 3.77E-01 Age  Teen Teen Teen Teen Teen Organ  Thyroid Thyroid Thyroid Thyroid Thyroid ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 % ODCM Limit
 
% 3.31E-01 1.31E-01 2.79E+00 1.77E+00 2.51E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.
Table 13:
Table 28: Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines -
Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit     Quarter 1     Quarter 2   Quarter 3     Quarter 4   Year total
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02 2.IodinesI-131 Ci < LLD 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD 3.28E-05 3.23E-04 Table 29: Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates -
: 1. Fission gases Ar-41         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-83m         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-85         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-85m         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-87         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-88         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-89         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Kr-90         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-131m         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-133         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-133m         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-135         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-135m         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-137         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Xe-138         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Total         Ci     < LLD         < LLD       < LLD         < LLD       < LLD
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.59E-03 1.52E-06 2.19E-05 1.61E-03 Co-60 Ci 1.33E-06 5.21E-04 < LLD 7.52E-06 5.30E-04 Cr-51 Ci < LLD 5.72E-03 < LLD 4.49E-06 5.72E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 9.54E-05 < LLD < LLD 9.54E-05 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.31E-04 < LLD < LLD 1.31E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 1.98E-04 < LLD < LLD 1.98E-04 Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.32E-04 < LLD < LLD 1.32E-04 Total Ci 1.33E-06 8.47E-03 1.52E-06 3.53E-05 8.51E-03 4. Tritium H-3 Ci 8.51E+01 9.39E+01 8.40E+01 1.50E+02 4.13E+02 Table 30: Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines -
: 2. Iodines I-131         Ci     < LLD          < LLD      < LLD         < LLD       < LLD I-132         Ci     < LLD         < LLD       < LLD         < LLD       < LLD I-133         Ci     < LLD         < LLD       < LLD          < LLD        < LLD I-134         Ci     < LLD         < LLD       < LLD         < LLD       < LLD I-135         Ci     < LLD         < LLD       < LLD         < LLD       < LLD Total         Ci     < LLD          < LLD      < LLD         < LLD       < LLD PVNGS 2016 ARERR                                                                        Page 28
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 2.29E-01 3.35E-01 2.17E-01 1.77E-01 9.58E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 1.46E-02 1.71E-01 2.11E-02 6.97E-02 2.77E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 1.33E-04 5.78E-05 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 2.44E-01 5.12E-01 2.38E-01 2.47E-01 1.24E+00 2.IodinesI-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Table 31: Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates -
 
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD 3.07E-06 1.84E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD 4.01E-04 < LLD 3.33E-05 4.34E-04 Co-60 Ci < LLD 1.52E-04 < LLD 2.27E-05 1.75E-04 Cr-51 Ci < LLD 1.15E-03 < LLD < LLD 1.15E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 8.86E-06 < LLD < LLD 8.86E-06 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 3.44E-05 < LLD 1.34E-07 3.45E-05 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 5.04E-05 < LLD 2.72E-05 7.76E-05 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 5.29E-06 < LLD 2.09E-05 2.62E-05 Total Ci < LLD 1.82E-03 < LLD 1.07E-04 1.92E-03 4. Tritium H-3 Ci 5.24E+02 3.11E+02 6.88E+02 4.20E+02 1.94E+03 Note 1 - Not required for batch releases Table 32: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -
Table 14:
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 2.29E-01 3.35E-01 2.17E-01 1.77E-01 9.58E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 1.46E-02 2.33E-01 2.11E-02 6.97E-02 3.38E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 1.33E-04 5.78E-05 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 2.44E-01 5.73E-01 2.38E-01 2.47E-01 1.30E+00 2.IodinesI-131 Ci < LLD 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD 3.28E-05 3.23E-04 Table 33: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates -
Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released   Unit     Quarter 1     Quarter 2   Quarter 3     Quarter 4   Year total
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD 3.07E-06 1.84E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.99E-03 < LLD 5.52E-05 2.05E-03 Co-60 Ci 1.33E-06 6.73E-04 < LLD 3.02E-05 7.05E-04 Cr-51 Ci < LLD 6.87E-03 < LLD 4.49E-06 6.87E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 1.04E-04 < LLD < LLD 1.04E-04 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.65E-04 < LLD 1.34E-07 1.66E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 2.48E-04 < LLD 2.72E-05 2.76E-04 Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.37E-04 < LLD 2.09E-05 1.58E-04 Total Ci 1.33E-06 1.03E-02 < LLD 1.43E-04 1.04E-02 Total > 8 days Ci 1.33E-06 1.03E-02 < LLD 1.40E-04 1.04E-02 4. Tritium H-3 Ci 6.09E+02 4.05E+02 7.72E+02 5.70E+02 2.36E+03 Table 34: Units 1, 2 and 3 Gaseous Effluents- Continuous - Fission Gases and Iodine -
: 3. Particulates Ag-110m         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Ba-140         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Br-82         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Ce-141         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Ce-144         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Co-57         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Co-58         Ci       < LLD          < LLD        < LLD         < LLD       < LLD Co-60         Ci       < LLD          < LLD       < LLD         < LLD        < LLD Cr-51         Ci       < LLD          < LLD        < LLD         < LLD       < LLD Cs-134         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Cs-136         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Cs-137         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Cs-138         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Fe-59         Ci       < LLD         < LLD       < LLD         < LLD       < LLD La-140         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Mn-54         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Mo-99         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Nb-95         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Os-191         Ci       < LLD          < LLD        < LLD         < LLD       < LLD Rb-88         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Ru-103         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Ru-106         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Sb-122         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Sb-124         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Sb-125         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Se-75         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Sn-113m         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Sr-89         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Sr-90         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Tc-99m         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Te-123m         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Zn-65         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Zr-95         Ci       < LLD         < LLD       < LLD         < LLD       < LLD Total         Ci       < LLD         < LLD         < LLD       < LLD        < LLD
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD Xe-133 Ci 6.18E-02 < LLD < LLD 6.18E-02 Xe-133m Ci < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD Total Ci 6.18E-02 < LLD < LLD 6.18E-02 2.IodinesI-131 Ci 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci 2.90E-04 < LLD 3.28E-05 3.23E-04 Table 35: Units 1, 2 and 3 Gaseous Effluents- Continuous - Particulates -
: 4. Tritium H-3         Ci     3.01E+01       2.93E+01     2.11E+01     1.85E+01    9.90E+01 PVNGS 2016 ARERR                                                                          Page 29
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 3.ParticulatesAg-110m Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Co-57 Ci 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci 1.59E-03 < LLD 2.19E-05 1.62E-03 Co-60 Ci 5.22E-04 < LLD 7.52E-06 5.29E-04 Cr-51 Ci 5.72E-03 < LLD 4.49E-06 5.72E-03 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD Fe-59 Ci 9.54E-05 < LLD < LLD 9.54E-05 La-140 Ci < LLD < LLD < LLD < LLD Mn-54 Ci 1.31E-04 < LLD < LLD 1.31E-04 Mo-99 Ci < LLD < LLD < LLD < LLD Nb-95 Ci 1.98E-04 < LLD < LLD 1.98E-04 Os-191 Ci < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD Sb-124 Ci 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Zr-95 Ci 1.32E-04 < LLD < LLD 1.32E-04 Total Ci 8.47E-03 < LLD 3.53E-05 8.51E-03 4. Tritium H-3 Ci 1.24E+029.91E+011.89E+024.13E+02 Table 36: Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine -
 
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 1. Fission gases Ar-41 Ci 5.43E+00 2.77E-01 2.35E-01 5.94E+00 Kr-83m Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD Xe-131m Ci 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 1.62E-01 6.47E-02 5.23E-02 2.79E-01 Xe-133m Ci 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci 3.33E-03 1.90E-04 < LLD 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD Xe-138  < LLD < LLD < LLD < LLD Total Ci 5.60E+00 3.42E-01 2.87E-01 6.23E+00 2.IodinesI-131 Ci < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD Table 37: Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates -
Table 15:
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1,2 and 3 3.ParticulatesAg-110m Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD Br-82 Ci 1.44E-03 < LLD 4.20E-06 1.44E-03 Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD Co-58 Ci 4.01E-04 < LLD 3.33E-05 4.34E-04 Co-60 Ci 1.52E-04 < LLD 2.27E-05 1.75E-04 Cr-51 Ci 1.15E-03 < LLD < LLD 1.15E-03 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD Fe-59 Ci 8.86E-06 < LLD < LLD 8.86E-06 La-140 Ci < LLD < LLD < LLD < LLD Mn-54 Ci 3.44E-05 < LLD 1.34E-07 3.46E-05 Mo-99 Ci < LLD < LLD < LLD < LLD Nb-95 Ci 5.04E-05 < LLD 2.72E-05 7.76E-05 Os-191 Ci < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Zr-95 Ci 5.29E-06 < LLD 2.09E-05 2.62E-05 Total Ci 3.24E-03 < LLD 1.08E-04 3.34E-03 4. Tritium H-3 Ci 9.31E+02 1.52E+02 9.44E+02 2.03E+03 Note 1 - Not required for batch releases Table 38: Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released   Unit   Quarter 1     Quarter 2   Quarter 3     Quarter 4   Year total
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 1. Fission gases Ar-41 Ci 5.43E+00 2.77E-01 2.35E-01 5.94E+00 Kr-83m Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD Xe-131m Ci 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 2.24E-01 6.47E-02 5.23E-02 3.41E-01 Xe-133m Ci 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci 3.33E-03 1.90E-04 < LLD 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD Total Ci 5.66E+00 3.42E-01 2.87E-01 6.29E+00 2.IodinesI-131 Ci 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci 2.90E-04 < LLD 3.28E-05 3.23E-04
: 1. Fission gases Ar-41         Ci     7.12E-02       4.88E-02     7.50E-02     7.21E-02     2.67E-01 Kr-83m         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Kr-85         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Kr-85m         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Kr-87         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Kr-88         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Kr-89         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Kr-90         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Xe-131m         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Xe-133         Ci     1.43E-02      1.02E-02    2.09E-02      1.74E-02     6.28E-02 Xe-133m         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Xe-135         Ci       < LLD         < LLD       1.33E-04      5.78E-05    1.91E-04 Xe-135m          Ci      < LLD         < LLD       < LLD         < LLD         < LLD Xe-137         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Xe-138         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Total         Ci     8.55E-02       5.90E-02     9.60E-02     8.96E-02    3.30E-01
: 2. Iodines I-131         Ci       < LLD         < LLD       < LLD         < LLD         < LLD I-132         Ci       < LLD         < LLD       < LLD         < LLD         < LLD I-133         Ci       < LLD         < LLD       < LLD         < LLD         < LLD I-134         Ci       < LLD         < LLD       < LLD         < LLD         < LLD I-135         Ci       < LLD         < LLD       < LLD         < LLD         < LLD Total         Ci       < LLD         < LLD       < LLD         < LLD       < LLD PVNGS 2016 ARERR                                                                          Page 30
 
Table 16:
Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released   Unit     Quarter 1     Quarter 2       Quarter 3 Quarter 4 Year total
: 3. Particulates Ag-110m         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Ba-140       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Br-82       Ci       < LLD         < LLD           < LLD       < LLD      < LLD Ce-141         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Ce-144         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Co-57         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Co-58         Ci       < LLD          < LLD          < LLD       < LLD     < LLD Co-60         Ci       < LLD          < LLD          < LLD       < LLD     < LLD Cr-51       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Cs-134       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Cs-136       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Cs-137       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Cs-138       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Fe-59       Ci       < LLD         < LLD           < LLD       < LLD     < LLD La-140       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Mn-54         Ci       < LLD          < LLD           < LLD       < LLD      < LLD Mo-99         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Nb-95         Ci       < LLD         < LLD           < LLD      < LLD      < LLD Os-191         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Rb-88         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Ru-103         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Ru-106         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Sb-122       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Sb-124       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Sb-125       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Se-75         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Sn-113m         Ci       < LLD         < LLD           < LLD       < LLD     < LLD Sr-89       Ci       Note 1         Note 1         Note 1     Note 1     Note 1 Sr-90       Ci       Note 1         Note 1         Note 1     Note 1     Note 1 Tc-99m       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Te-123m       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Zn-65       Ci       < LLD         < LLD           < LLD       < LLD     < LLD Zr-95       Ci       < LLD          < LLD          < LLD       < LLD     < LLD Total       Ci       < LLD          < LLD          < LLD       < LLD     < LLD
: 4. Tritium H-3         Ci     1.50E+01       1.89E-02       6.00E+01    7.69E+01  1.52E+02 Note 1 - Not required for batch releases PVNGS 2016 ARERR                                                                        Page 31


Table 39: Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates -
Table 17:
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD Br-82 Ci 1.44E-03 < LLD 4.20E-06 1.44E-03 Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Co-57 Ci 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci 1.99E-03 < LLD 5.52E-05 2.05E-03 Co-60 Ci 6.74E-04 < LLD 3.02E-05 7.04E-04 Cr-51 Ci 6.86E-03 < LLD 4.49E-06 6.87E-03 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD Fe-59 Ci 1.04E-04 < LLD < LLD 1.04E-04 La-140 Ci < LLD < LLD < LLD < LLD Mn-54 Ci 1.65E-04 < LLD 1.34E-07 1.65E-04 Mo-99 Ci < LLD < LLD < LLD < LLD Nb-95 Ci 2.48E-04 < LLD 2.72E-05 2.75E-04 Os-191 Ci < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD Sb-124 Ci 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Zr-95 Ci 1.37E-04 < LLD 2.09E-05 1.58E-04 Total Ci 1.17E-02 < LLD 1.44E-04 1.19E-02 Total > 8 days Ci 1.33E-06 1.03E-02 1.52E-06 1.03E-02 4. Tritium H-3 Ci 1.06E+03 2.51E+02 1.13E+03 2.44E+03 1Table 40: Estimation of Total Percent Error The estimated total error is calculated as follows:
Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released   Unit   Quarter 1       Quarter 2   Quarter 3   Quarter 4  Year total
Total Percent Error = (E 2 + E 2 2 + E 3 2 + ... + E n 2 )1/2  Where E n = Percent error associated with each contributing parameter. Parameters contributing to errors in the measurement of gaseous effluents; process flow rates, sample collection, analytical counting and tank volumes.
: 1. Fission gases Ar-41        Ci     7.12E-02        4.88E-02    7.50E-02    7.21E-02    2.67E-01 Kr-83m        Ci      < LLD          < LLD       < LLD       < LLD       < LLD Kr-85        Ci       < LLD         < LLD       < LLD       < LLD       < LLD Kr-85m        Ci       < LLD          < LLD       < LLD        < LLD      < LLD Kr-87        Ci       < LLD          < LLD       < LLD       < LLD       < LLD Kr-88        Ci       < LLD          < LLD       < LLD       < LLD       < LLD Kr-89        Ci       < LLD          < LLD        < LLD        < LLD       < LLD Kr-90        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-131m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-133        Ci     1.43E-02        1.02E-02    2.09E-02    1.74E-02    6.28E-02 Xe-133m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-135        Ci      < LLD          < LLD       1.33E-04    5.78E-05   1.91E-04 Xe-135m        Ci       < LLD         < LLD       < LLD       < LLD       < LLD Xe-137        Ci       < LLD         < LLD       < LLD       < LLD       < LLD Xe-138         Ci       < LLD         < LLD       < LLD       < LLD       < LLD Total        Ci     8.55E-02        5.90E-02    9.60E-02    8.96E-02    3.30E-01
The following values (%) were used for error calculations.
: 2. Iodines I-131        Ci       < LLD          < LLD       < LLD       < LLD       < LLD I-132        Ci       < LLD         < LLD       < LLD       < LLD       < LLD I-133        Ci       < LLD          < LLD       < LLD       < LLD       < LLD I-134        Ci       < LLD          < LLD       < LLD       < LLD       < LLD I-135        Ci       < LLD         < LLD       < LLD       < LLD       < LLD Total        Ci      < LLD         < LLD       < LLD       < LLD       < LLD PVNGS 2016 ARERR                                                                        Page 32
Fission & Act gases  I-131  Particulates Tritium  25 25 25 25 Sample counting error 10 10 10 10 Counting system calibration error 5 5 5 5 Counting system source error 20 N/A N/A N/A Temperature/volume correction error 10 10 10 10 Process flow measuring device (1) N/A 15 15 15 Sample flow measuring device N/A 5 N/A N/A Iodine collection efficiency error N/A N/A 10 N/A Plateout error N/A N/A N/A 20 Bubbler collection efficiency error N/A N/A N/A 2 Sample volume transfer error (pipette) N/A N/A N/A 2 Sample volume error (graduate) Note 1 - % of full scale Table 41: Effluent Monitoring Instrumentation Out Of Service Greater Than 30 Days Unit Instrument Date span of inoperability Cause of inoperability Explanation 2 Unit 2 Fuel Building Ventilation Flow transmitter 2JHFBFT0093**I XMITR 2/11/2016 through 4/14/2016 Condition Report 16-02244 documents the flow transmitter failing its acceptance criteria for FUNCTIONALITY due to low flow indication. Condition Report 16-03957 determined that a ventilation inspection panel was found open, however, it took greater than 30 days to find and fix the problem. 
 
Table 18:
Unit 2 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released  Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4  Year total
: 3. Particulates Ag-110m        Ci      < LLD         < LLD         < LLD       < LLD       < LLD Ba-140        Ci      < LLD         < LLD         < LLD       < LLD       < LLD Br-82        Ci     < LLD         < LLD         < LLD       < LLD       < LLD Ce-141        Ci     < LLD          < LLD         < LLD       < LLD       < LLD Ce-144        Ci     < LLD          < LLD         < LLD       < LLD       < LLD Co-57        Ci     < LLD          < LLD         < LLD       < LLD       < LLD Co-58        Ci     < LLD         < LLD         < LLD       < LLD       < LLD Co-60        Ci      < LLD          < LLD         < LLD       < LLD       < LLD Cr-51        Ci     < LLD          < LLD        < LLD        < LLD       < LLD Cs-134        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-136        Ci     < LLD          < LLD        < LLD        < LLD      < LLD Cs-137        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-138        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Fe-59        Ci      < LLD          < LLD        < LLD        < LLD      < LLD La-140        Ci     < LLD          < LLD        < LLD        < LLD      < LLD Mn-54        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Mo-99        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Nb-95        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Os-191        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Rb-88        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ru-103        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ru-106        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-122        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-124        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-125        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Se-75        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sn-113m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sr-89        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sr-90        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Tc-99m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Te-123m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Zn-65        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Zr-95        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total > 8 days    Ci      < LLD          < LLD        < LLD        < LLD      < LLD
: 4. Tritium H-3        Ci    4.51E+01      2.93E+01      8.11E+01    9.54E+01    2.51E+02 PVNGS 2016 ARERR                                                                        Page 33
 
Table 19:
Unit 2 Radiation Doses At And Beyond The Site Boundary Unit    Quarter 1    Quarter 2    Quarter 3    Quarter 4  Year total Unit 2                    Q1            Q2            Q3          Q4        year Gamma Air Dose      mrad    1.89E-04      1.56E-04      1.99E-04      1.91E-04  7.34E-04 ODCM Req 4.1 Limit    mrad    5.00E+00    5.00E+00      5.00E+00      5.00E+00    1.00E+01
      % ODCM Limit          %    3.78E-03      3.12E-03      3.98E-03      3.82E-03  7.34E-03 Beta Air Dose      mrad    7.03E-05      5.80E-05      7.57E-05      7.20E-05  2.76E-04 ODCM Req 4.1 Limit    mrad    1.00E+01    1.00E+01      1.00E+01      1.00E+01    2.00E+01
      % ODCM Limit          %    7.03E-04      5.80E-04      7.57E-04      7.20E-04  1.38E-03 Maximum Organ Dose mrem    1.62E-02      1.05E-02      2.91E-02      3.42E-02  9.01E-02 (excluding skin)
Age                    Teen          Teen          Teen          Teen      Teen Organ                    Thyroid      Thyroid      Thyroid      Thyroid    Thyroid ODCM Req. 4.2 Limit      %    7.50E+00    7.50E+00      7.50E+00      7.50E+00    1.50E+01
      % ODCM Limit          %      2.16E-01      1.40E-01      3.88E-01      4.56E-01  6.01E-01 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.
PVNGS 2016 ARERR                                                                            Page 34
 
Table 20:
Unit 3 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit    Quarter 1    Quarter 2  Quarter 3    Quarter 4 Year        % (1)
A. Fission & activation gases
: 1. Total release                            Ci        4.38E-02      4.81E-02    8.04E-02    1.03E-01  2.76E-01    3.54E+01
: 2. Average release rate for period          Ci/sec    5.57E-03      6.12E-03    1.01E-02    1.30E-02  8.73E-03
: 3. Percent of ODCM Requirement limit        %          NA (2)        NA (2)      NA (2)      NA (2)    NA (2)
B. Iodine 131
: 1. Total Iodine 131                        Ci          < LLD        < LLD      < LLD      2.35E-05  2.35E-05    3.32E+01
: 2. Average release rate for period          Ci/sec      < LLD        < LLD      < LLD      2.96E-06  7.43E-07
: 3. Percent of ODCM Requirement limit        %          NA (2)        NA (2)    NA (2)      NA (2)    NA (2)
C. Particulates
: 1. Particulates with half- lives > 8 days  Ci          < LLD        < LLD      < LLD      1.40E-04  1.40E-04    3.43E+01
: 2. Average release rate for period          Ci/sec      < LLD        < LLD      < LLD      1.76E-05  4.41E-06
: 3. Percent of ODCM Requirement limit        %            NA (2)        NA (2)    NA (2)      NA (2)    NA (2)
: 4. Gross Alpha radioactivity                Ci          < LLD      1.68E-08    < LLD        < LLD    < LLD D. Tritium
: 1. Total release                            Ci        6.92E+01      2.73E+01  5.82E+02      3.71E+02  1.05E+03    3.85E+01
: 2. Average release rate for period          Ci/sec    8.80E+00      3.47E+00  7.32E+01      4.67E+01  3.32E+01
: 3. Percent of ODCM Requirement limit        %          NA (2)        NA (2)      NA (2)      NA (2)    NA (2)
(1) Estimated total error methodology is presented in Table 40.
(2) See Table 27 for percent of ODCM Requirement limits.
PVNGS 2016 ARERR                                                                                                              Page 35
 
Table 21:
Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released  Unit    Quarter 1      Quarter 2  Quarter 3      Quarter 4    Year total
: 1. Fission gases Ar-41        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-83m        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-85        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-85m        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-87        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-88        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-89        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Kr-90        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-131m        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-133        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-133m        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-135        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-135m        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-137        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Xe-138        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Total        Ci      < LLD          < LLD      < LLD          < LLD        < LLD
: 2. Iodines I-131        Ci      < LLD          < LLD      < LLD        2.35E-05    2.35E-05 I-132        Ci      < LLD          < LLD      < LLD          < LLD        < LLD I-133        Ci      < LLD          < LLD      < LLD        9.27E-06    9.27E-06 I-134        Ci      < LLD          < LLD      < LLD          < LLD        < LLD I-135        Ci      < LLD          < LLD      < LLD          < LLD        < LLD Total        Ci      < LLD          < LLD      < LLD        3.28E-05    3.28E-05 PVNGS 2016 ARERR                                                                          Page 36
 
Table 22:
Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released  Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4    Year total
: 3. Particulates Ag-110m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ba-140        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Br-82        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ce-141          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ce-144          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Co-57          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Co-58          Ci      < LLD        < LLD        < LLD      2.19E-05    2.19E-05 Co-60          Ci      < LLD        < LLD        < LLD      7.52E-06    7.52E-06 Cr-51        Ci      < LLD        < LLD        < LLD      4.49E-06    4.49E-06 Cs-134        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Cs-136        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Cs-137        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Cs-138        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Fe-59        Ci      < LLD        < LLD        < LLD        < LLD        < LLD La-140        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Mn-54          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Mo-99          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Nb-95          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Os-191          Ci      < LLD        < LLD        < LLD      1.38E-06    1.38E-06 Rb-88          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ru-103          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Ru-106          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sb-122        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sb-124        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sb-125        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Se-75          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sn-113m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sr-89        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Sr-90        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Tc-99m        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Te-123m        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Zn-65        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Zr-95        Ci      < LLD        < LLD        < LLD        < LLD        < LLD Total        Ci      < LLD        < LLD        < LLD      3.53E-05    3.53E-05
: 4. Tritium H-3          Ci    2.92E+01      2.73E+01      2.43E+01      1.09E+02    1.90E+02 PVNGS 2016 ARERR                                                                          Page 37
 
Table 23:
Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released    Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4    Year total
: 1. Fission gases Ar-41          Ci    4.38E-02      4.81E-02    8.04E-02      5.10E-02    2.23E-01 Kr-83m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-85          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-85m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-87          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-88          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-89          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Kr-90          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-131m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-133          Ci      < LLD        < LLD        < LLD        5.23E-02    5.23E-02 Xe-133m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-135          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-135m          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-137          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Xe-138          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Total          Ci    4.38E-02      4.81E-02    8.04E-02      1.03E-01    2.76E-01
: 2. Iodines I-131          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-132          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-133          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-134          Ci      < LLD        < LLD        < LLD        < LLD        < LLD I-135          Ci      < LLD        < LLD        < LLD        < LLD        < LLD Total          Ci      < LLD        < LLD        < LLD        < LLD        < LLD PVNGS 2016 ARERR                                                                          Page 38
 
Table 24:
Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released  Unit    Quarter 1      Quarter 2      Quarter 3  Quarter 4  Year total
: 3. Particulates Ag-110m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ba-140        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Br-82        Ci      < LLD          < LLD          < LLD    3.07E-06  3.07E-06 Ce-141        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ce-144        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Co-57        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Co-58        Ci      < LLD          < LLD          < LLD    3.33E-05  3.33E-05 Co-60        Ci      < LLD          < LLD          < LLD    2.27E-05  2.27E-05 Cr-51        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-134        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-136        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-137        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-138        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Fe-59        Ci      < LLD          < LLD          < LLD      < LLD      < LLD La-140        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Mn-54        Ci      < LLD          < LLD          < LLD    1.34E-07  1.34E-07 Mo-99        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Nb-95        Ci      < LLD          < LLD          < LLD    2.72E-05  2.72E-05 Os-191        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Rb-88        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ru-103        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ru-106        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-122        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-124        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-125        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Se-75        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sn-113m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sr-89        Ci      Note 1        Note 1          Note 1    Note 1    Note 1 Sr-90        Ci      Note 1        Note 1          Note 1    Note 1    Note 1 Tc-99m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Te-123m        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Zn-65        Ci      < LLD          < LLD          < LLD      < LLD      < LLD Zr-95        Ci      < LLD          < LLD          < LLD    2.09E-05  2.09E-05 Total        Ci      < LLD          < LLD          < LLD    1.07E-04  1.07E-04
: 4. Tritium H-3        Ci    4.00E+01        2.48E-02      5.58E+02    2.62E+02  8.60E+02 Note 1 - Not required for batch releases PVNGS 2016 ARERR                                                                        Page 39
 
Table 25:
Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released  Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4  Year total
: 1. Fission gases Ar-41          Ci    4.38E-02      4.81E-02    8.04E-02    5.10E-02    2.23E-01 Kr-83m          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-85          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-85m          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-87          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-88          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-89          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-90          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-131m          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-133          Ci      < LLD          < LLD        < LLD      5.23E-02    5.23E-02 Xe-133m          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-135          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-135m          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-137          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-138          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total          Ci    4.38E-02      4.81E-02    8.04E-02    1.03E-01    2.76E-01
: 2. Iodines I-131          Ci      < LLD          < LLD        < LLD      2.35E-05    2.35E-05 I-132          Ci      < LLD          < LLD        < LLD        < LLD      < LLD I-133          Ci      < LLD          < LLD        < LLD      9.27E-06    9.27E-06 I-134          Ci      < LLD          < LLD        < LLD        < LLD      < LLD I-135          Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total          Ci      < LLD          < LLD        < LLD      3.28E-05    3.28E-05 PVNGS 2016 ARERR                                                                        Page 40
 
Table 26:
Unit 3 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released  Unit  Quarter 1      Quarter 2    Quarter 3    Quarter 4  Year total
: 3. Particulates Ag-110m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ba-140        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Br-82        Ci      < LLD          < LLD        < LLD      3.07E-06  3.07E-06 Ce-141        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ce-144        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Co-57        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Co-58        Ci      < LLD          < LLD        < LLD      5.52E-05  5.52E-05 Co-60        Ci      < LLD          < LLD        < LLD      3.02E-05  3.02E-05 Cr-51        Ci      < LLD          < LLD        < LLD      4.49E-06  4.49E-06 Cs-134        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-136        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-137        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Cs-138        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Fe-59        Ci      < LLD          < LLD        < LLD        < LLD      < LLD La-140        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Mn-54        Ci      < LLD          < LLD        < LLD      1.34E-07  1.34E-07 Mo-99        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Nb-95        Ci      < LLD          < LLD        < LLD      2.72E-05  2.72E-05 Os-191        Ci      < LLD          < LLD        < LLD      1.38E-06  1.38E-06 Rb-88        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ru-103        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Ru-106        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-122        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-124        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sb-125        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Se-75        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sn-113m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sr-89        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Sr-90        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Tc-99m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Te-123m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Zn-65        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Zr-95        Ci      < LLD          < LLD        < LLD      2.09E-05  2.09E-05 Total        Ci      < LLD          < LLD        < LLD      1.43E-04  1.43E-04 Total > 8 days    Ci      < LLD          < LLD        < LLD      1.40E-04  1.40E-04
: 4. Tritium H-3        Ci    6.92E+01      2.73E+01      5.82E+02      3.71E+02  1.05E+03 PVNGS 2016 ARERR                                                                        Page 41
 
Table 27:
Unit 3 Radiation Doses At And Beyond The Site Boundary Unit  Quarter 1    Quarter 2      Quarter 3    Quarter 4  Year total Gamma Air Dose      mrad  1.15E-04    1.26E-04        2.11E-04    1.39E-04    5.92E-04 ODCM Req 4.1 Limit    mrad  5.00E+00    5.00E+00      5.00E+00      5.00E+00  1.00E+01
        % ODCM Limit        %    2.30E-03    2.52E-03        4.22E-03    2.78E-03    5.92E-03 Beta Air Dose      mrad  4.06E-05    4.46E-05        7.45E-05    6.28E-05    2.22E-04 ODCM Req 4.1 Limit    mrad  1.00E+01    1.00E+01      1.00E+01      1.00E+01  2.00E+01
        % ODCM Limit        %    4.06E-04    4.46E-04        7.45E-04    6.28E-04    1.11E-03 Maximum Organ Dose mrem    2.48E-02    9.80E-03        2.09E-01    1.33E-01    3.77E-01 (excluding skin)
Age                    Teen          Teen          Teen        Teen        Teen Organ                  Thyroid      Thyroid        Thyroid      Thyroid    Thyroid ODCM Req. 4.2 Limit    mrem    7.50E+00    7.50E+00      7.50E+00      7.50E+00  1.50E+01
        % ODCM Limit        %    3.31E-01    1.31E-01      2.79E+00      1.77E+00  2.51E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.
PVNGS 2016 ARERR                                                                            Page 42
 
Table 28:
Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines -
Total By Quarter Nuclides Released  Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4  Year total
: 1. Fission gases Ar-41        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-83m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-85        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-85m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-87        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-88        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-89        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Kr-90        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-131m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-133        Ci      < LLD        6.18E-02      < LLD        < LLD    6.18E-02 Xe-133m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-135        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-135m        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-137        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Xe-138        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci      < LLD        6.18E-02      < LLD        < LLD    6.18E-02
: 2. Iodines I-131        Ci      < LLD        1.72E-05      < LLD      2.35E-05  4.07E-05 I-132        Ci      < LLD        2.73E-04      < LLD        < LLD    2.73E-04 I-133        Ci      < LLD          < LLD        < LLD      9.27E-06  9.27E-06 I-134        Ci      < LLD          < LLD        < LLD        < LLD      < LLD I-135        Ci      < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci      < LLD        2.90E-04      < LLD      3.28E-05  3.23E-04 PVNGS 2016 ARERR                                                                        Page 43
 
Table 29:
Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates -
Total By Quarter Nuclides Released Unit  Quarter 1      Quarter 2    Quarter 3      Quarter 4  Year total
: 3. Particulates Ag-110m      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Ba-140      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Br-82      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Ce-141      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Ce-144      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Co-57      Ci      < LLD        4.88E-06        < LLD          < LLD    4.88E-06 Co-58      Ci      < LLD        1.59E-03      1.52E-06      2.19E-05  1.61E-03 Co-60      Ci    1.33E-06      5.21E-04        < LLD        7.52E-06  5.30E-04 Cr-51      Ci      < LLD        5.72E-03        < LLD        4.49E-06  5.72E-03 Cs-134      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Cs-136      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Cs-137      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Cs-138      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Fe-59      Ci      < LLD        9.54E-05        < LLD          < LLD    9.54E-05 La-140      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Mn-54      Ci      < LLD        1.31E-04        < LLD          < LLD    1.31E-04 Mo-99      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Nb-95      Ci      < LLD        1.98E-04        < LLD          < LLD    1.98E-04 Os-191      Ci      < LLD          < LLD        < LLD        1.38E-06  1.38E-06 Rb-88      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Ru-103      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Ru-106      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Sb-122      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Sb-124      Ci      < LLD        7.86E-05        < LLD          < LLD    7.86E-05 Sb-125      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Se-75      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Sn-113m      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Sr-89      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Sr-90      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Tc-99m      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Te-123m      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Zn-65      Ci      < LLD          < LLD        < LLD          < LLD      < LLD Zr-95      Ci      < LLD        1.32E-04        < LLD          < LLD    1.32E-04 Total      Ci    1.33E-06      8.47E-03      1.52E-06      3.53E-05  8.51E-03
: 4. Tritium H-3      Ci    8.51E+01      9.39E+01      8.40E+01      1.50E+02  4.13E+02 PVNGS 2016 ARERR                                                                      Page 44
 
Table 30:
Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines -
Total By Quarter Nuclides Released  Unit    Quarter 1      Quarter 2    Quarter 3    Quarter 4  Year total
: 1. Fission gases Ar-41        Ci  2.29E-01        3.35E-01      2.17E-01    1.77E-01  9.58E-01 Kr-83m        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Kr-85        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Kr-85m        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Kr-87        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Kr-88        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Kr-89        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Kr-90        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Xe-131m        Ci    < LLD        1.24E-03      < LLD        < LLD    1.24E-03 Xe-133        Ci  1.46E-02        1.71E-01      2.11E-02    6.97E-02  2.77E-01 Xe-133m        Ci    < LLD        1.02E-03      < LLD        < LLD    1.02E-03 Xe-135        Ci    < LLD        3.33E-03      1.33E-04    5.78E-05  3.52E-03 Xe-135m        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Xe-137        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Xe-138        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci  2.44E-01        5.12E-01      2.38E-01    2.47E-01  1.24E+00
: 2. Iodines I-131        Ci    < LLD          < LLD        < LLD        < LLD      < LLD I-132        Ci    < LLD          < LLD        < LLD        < LLD      < LLD I-133        Ci    < LLD          < LLD        < LLD        < LLD      < LLD I-134        Ci    < LLD          < LLD        < LLD        < LLD      < LLD I-135        Ci    < LLD          < LLD        < LLD        < LLD      < LLD Total        Ci    < LLD          < LLD        < LLD        < LLD      < LLD PVNGS 2016 ARERR                                                                      Page 45
 
Table 31:
Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates -
Total By Quarter Nuclides Released Unit  Quarter 1      Quarter 2      Quarter 3  Quarter 4  Year total
: 3. Particulates Ag-110m      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ba-140      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Br-82      Ci      < LLD        1.53E-05        < LLD    3.07E-06  1.84E-05 Ce-141      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ce-144      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Co-57      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Co-58      Ci      < LLD        4.01E-04        < LLD    3.33E-05  4.34E-04 Co-60      Ci      < LLD        1.52E-04        < LLD    2.27E-05  1.75E-04 Cr-51      Ci      < LLD        1.15E-03        < LLD      < LLD    1.15E-03 Cs-134      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-136      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-137      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Cs-138      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Fe-59      Ci      < LLD        8.86E-06        < LLD      < LLD    8.86E-06 La-140      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Mn-54      Ci      < LLD        3.44E-05        < LLD    1.34E-07  3.45E-05 Mo-99      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Nb-95      Ci      < LLD        5.04E-05        < LLD    2.72E-05  7.76E-05 Os-191      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Rb-88      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ru-103      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Ru-106      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-122      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-124      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sb-125      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Se-75      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sn-113m      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Sr-89      Ci    Note 1          Note 1          Note 1    Note 1    Note 1 Sr-90      Ci    Note 1          Note 1          Note 1    Note 1    Note 1 Tc-99m      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Te-123m      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Zn-65      Ci      < LLD          < LLD          < LLD      < LLD      < LLD Zr-95      Ci      < LLD        5.29E-06        < LLD    2.09E-05  2.62E-05 Total      Ci      < LLD        1.82E-03        < LLD    1.07E-04  1.92E-03
: 4. Tritium H-3      Ci    5.24E+02        3.11E+02      6.88E+02    4.20E+02  1.94E+03 Note 1 - Not required for batch releases PVNGS 2016 ARERR                                                                      Page 46
 
Table 32:
Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -
Total By Quarter Nuclides Released    Unit    Quarter 1      Quarter 2    Quarter 3  Quarter 4    Year total
: 1. Fission gases Ar-41          Ci    2.29E-01        3.35E-01    2.17E-01    1.77E-01    9.58E-01 Kr-83m          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Kr-85          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Kr-85m          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Kr-87          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Kr-88          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Kr-89          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Kr-90          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Xe-131m          Ci      < LLD          1.24E-03      < LLD      < LLD      1.24E-03 Xe-133          Ci    1.46E-02        2.33E-01    2.11E-02    6.97E-02    3.38E-01 Xe-133m          Ci      < LLD          1.02E-03      < LLD      < LLD      1.02E-03 Xe-135          Ci      < LLD          3.33E-03    1.33E-04    5.78E-05    3.52E-03 Xe-135m          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Xe-137          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Xe-138          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Total          Ci    2.44E-01        5.73E-01    2.38E-01    2.47E-01    1.30E+00
: 2. Iodines I-131          Ci      < LLD          1.72E-05      < LLD      2.35E-05    4.07E-05 I-132          Ci      < LLD          2.73E-04      < LLD      < LLD      2.73E-04 I-133          Ci      < LLD          < LLD        < LLD      9.27E-06    9.27E-06 I-134          Ci      < LLD          < LLD        < LLD      < LLD        < LLD I-135          Ci      < LLD          < LLD        < LLD      < LLD        < LLD Total          Ci      < LLD          2.90E-04      < LLD      3.28E-05    3.23E-04 PVNGS 2016 ARERR                                                                          Page 47


Table 42: Solid Waste Summary A. Solid Waste Shipped Offsite For Burial Or Disposal (not irradiated fuel) 1.0  Type of Waste Unit Jan-Dec  2016 estimated total error % 1.a. Spent resin, filters, sludges, evaporator bottoms, etc. m3 9.25E+01 2.50E+01 Ci 2.12E+02 2.50E+01 1.b. Dry compressible waste, contaminated equipment, etc m3 5.87E+02 2.50E+01 Ci 1.19E+01 2.50E+01 1.c. Irradiated components, control rods, etc. m3 3.56E-01 2.50E+01 Ci 6.05E+00 2.50E+01 1.d. Other (Oil) m3 5.36E+00 2.50E+01 Ci 8.12E-07 2.50E+01 2.0  Estimate of major nuclide composition 2.a. Spent resin, filters, sludge, evaporator bottoms, etc.
Table 33:
Nuclide Name Percent Abundance Curies Estimated Total Error % Ni-63 5.24E+01 1.11E+02 2.50E+01 Fe-55 1.76E+01 3.72E+01 2.50E+01 Co-60 1.28E+01 2.71E+01 2.50E+01 Co-58 6.82E+00 1.44E+01 2.50E+01 Cs-137 3.11E+00 6.58E+00 2.50E+01 C-14 2.19E+00 4.64E+00 2.50E+01 Mn-54 1.44E+00 3.06E+00 2.50E+01 Sb-125 1.40E+00 2.96E+00 2.50E+01 H-3 1.33E+00 2.81E+00 2.50E+01 Co-57 6.21E-01 1.31E+00 2.50E+01 Ni-59 6.74E-02 1.43E-01 2.50E+01 Sr-90 5.56E-02 1.18E-01 2.50E+01 Tc-99 5.25E-02 1.11E-01 2.50E+01 Ce-144 4.87E-02 1.03E-01 2.50E+01 Pu-241 1.74E-02 3.68E-02 2.50E+01 Ag-110m 1.68E-02 3.57E-02 2.50E+01 Cs-134 1.44E-02 3.05E-02 2.50E+01 Zr-95 1.32E-02 2.79E-02 2.50E+01 I-129 1.21E-02 2.57E-02 2.50E+01 Cr-51 8.18E-03 1.73E-02 2.50E+01 Zn-65 7.61E-03 1.61E-02 2.50E+01 Nb-95 7.21E-03 1.53E-02 2.50E+01 Sn-113 3.06E-03 6.48E-03 2.50E+01 Sb-124 2.82E-03 5.96E-03 2.50E+01 Am-241 1.22E-03 2.58E-03 2.50E+01 Pu-238 7.64E-04 1.62E-03 2.50E+01 Cm-243 6.56E-04 1.39E-03 2.50E+01 Pu-239 4.91E-04 1.04E-03 2.50E+01 Fe-59 4.33E-04 9.17E-04 2.50E+01 Sr-89 2.41E-04 5.11E-04 2.50E+01 Am-243 5.62E-05 1.19E-04 2.50E+01 Cm-242 2.11E-05 4.47E-05 2.50E+01 Te-123m 7.65E-06 1.62E-05 2.50E+01 Pu-242 6.89E-06 1.46E-05 2.50E+01 Be-7 4.16E-11 8.81E-11 2.50E+01 Hf-181 8.41E-18 1.78E-17 2.50E+01 Ru-103 2.99E-27 6.32E-27 2.50E+01 Ce-141 5.48E-30 1.16E-29 2.50E+01 Total 2.12E+02 2.b. Dry compressible waste, contaminated equip, etc.
Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates -
Nuclide Name Percent Abundance Curies Estimated Total Error
Total By Quarter Nuclides Released  Unit  Quarter 1       Quarter 2     Quarter 3   Quarter 4  Year total
% Cr-51 4.87E+01 5.82E+00 2.50E+01 Co-58 1.41E+01 1.69E+00 2.50E+01 Nb-95 1.25E+01 1.50E+00 2.50E+01 Zr-95 1.07E+01 1.27E+00 2.50E+01 Co-60 7.57E+00 9.05E-01 2.50E+01 Fe-55 2.04E+00 2.44E-01 2.50E+01 Mn-54 1.52E+00 1.82E-01 2.50E+01 Fe-59 7.88E-01 9.42E-02 2.50E+01 Ni-63 4.70E-01 5.62E-02 2.50E+01 H-3 2.90E-01 3.47E-02 2.50E+01 Sn-113 2.25E-01 2.69E-02 2.50E+01 Sb-125 1.84E-01 2.20E-02 2.50E+01 Zn-65 1.67E-01 1.99E-02 2.50E+01 Ce-144 1.56E-01 1.86E-02 2.50E+01 C-14 1.45E-01 1.73E-02 2.50E+01 Hf-181 9.76E-02 1.17E-02 2.50E+01 Te-123m 6.54E-02 7.82E-03 2.50E+01 Sb-124 6.05E-02 7.23E-03 2.50E+01 Co-57 5.36E-02 6.40E-03 2.50E+01 Cs-137 3.84E-02 4.59E-03 2.50E+01 Tc-99 3.53E-02 4.22E-03 2.50E+01 Sr-90 8.52E-03 1.02E-03 2.50E+01 I-129 7.06E-03 8.44E-04 2.50E+01 Cm-242 2.16E-04 2.58E-05 2.50E+01 Pu-239 8.84E-05 1.06E-05 2.50E+01 Am-241 7.03E-05 8.40E-06 2.50E+01 Sc-46 6.53E-05 7.80E-06 2.50E+01 Cm-243 5.98E-05 7.14E-06 2.50E+01 Sr-89 1.58E-05 1.89E-06 2.50E+01 Pu-241 1.73E-06 2.07E-07 2.50E+01 Pu-238 1.82E-08 2.18E-09 2.50E+01 1.00E+02 1.19E+01
: 3. Particulates Ag-110m        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Ba-140        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Br-82        Ci      < LLD        1.53E-05        < LLD      3.07E-06  1.84E-05 Ce-141        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Ce-144         Ci      < LLD          < LLD          < LLD        < LLD      < LLD Co-57        Ci      < LLD        4.88E-06        < LLD        < LLD    4.88E-06 Co-58        Ci      < LLD        1.99E-03        < LLD      5.52E-05  2.05E-03 Co-60        Ci    1.33E-06        6.73E-04        < LLD      3.02E-05  7.05E-04 Cr-51       Ci      < LLD        6.87E-03       < LLD      4.49E-06  6.87E-03 Cs-134        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Cs-136        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Cs-137        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Cs-138        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Fe-59        Ci      < LLD        1.04E-04       < LLD        < LLD    1.04E-04 La-140        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Mn-54        Ci      < LLD        1.65E-04       < LLD      1.34E-07  1.66E-04 Mo-99        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Nb-95        Ci      < LLD        2.48E-04       < LLD      2.72E-05   2.76E-04 Os-191        Ci      < LLD          < LLD          < LLD      1.38E-06   1.38E-06 Rb-88        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Ru-103         Ci      < LLD          < LLD          < LLD        < LLD      < LLD Ru-106        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Sb-122        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Sb-124        Ci      < LLD        7.86E-05        < LLD        < LLD    7.86E-05 Sb-125        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Se-75        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Sn-113m        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Sr-89        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Sr-90        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Tc-99m        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Te-123m        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Zn-65        Ci      < LLD          < LLD          < LLD        < LLD      < LLD Zr-95        Ci      < LLD        1.37E-04        < LLD      2.09E-05  1.58E-04 Total        Ci    1.33E-06        1.03E-02       < LLD      1.43E-04  1.04E-02 Total > 8 days    Ci    1.33E-06        1.03E-02       < LLD      1.40E-04  1.04E-02
: 4. Tritium H-3        Ci    6.09E+02       4.05E+02       7.72E+02    5.70E+02   2.36E+03 PVNGS 2016 ARERR                                                                      Page 48


2.c. Irradiated components, control rods, etc.
Table 34:
Nuclide Name Percent Abundance Curies Estimated Total Error
Units 1, 2 and 3 Gaseous Effluents- Continuous - Fission Gases and Iodine -
% Co-60 7.14E+01 4.32E+00 2.50E+01 Fe-55 1.75E+01 1.06E+00 2.50E+01 Ni-63 9.50E+00 5.75E-01 2.50E+01 Cr-51 4.69E-01 2.84E-02 2.50E+01 Co-58 4.26E-01 2.58E-02 2.50E+01 Zr-95 3.01E-01 1.82E-02 2.50E+01 Nb-95 1.80E-01 1.09E-02 2.50E+01 Mn-54 8.28E-02 5.01E-03 2.50E+01 Ni-59 6.21E-02 3.76E-03 2.50E+01 H-3 2.15E-02 1.30E-03 2.50E+01 C-14 2.08E-02 1.26E-03 2.50E+01 Fe-59 1.56E-02 9.44E-04 2.50E+01 Sb-125 1.07E-02 6.47E-04 2.50E+01 Sn-113 8.99E-03 5.44E-04 2.50E+01 Zn-65 8.42E-03 5.10E-04 2.50E+01 Ce-144 7.14E-03 4.32E-04 2.50E+01 Co-57 2.73E-03 1.65E-04 2.50E+01 Te-123m 2.66E-03 1.61E-04 2.50E+01 Cs-137 2.21E-03 1.34E-04 2.50E+01 Hf-181 1.82E-03 1.10E-04 2.50E+01 Sb-124 1.62E-03 9.80E-05 2.50E+01 Nb-94 1.05E-03 6.35E-05 2.50E+01 Sr-90 5.24E-04 3.17E-05 2.50E+01 I-129 9.71E-05 5.88E-06 2.50E+01 Tc-99 6.31E-05 3.82E-06 2.50E+01 Cm-242 9.90E-06 5.99E-07 2.50E+01 Pu-239 5.48E-06 3.32E-07 2.50E+01 Am-241 4.34E-06 2.63E-07 2.50E+01 Cm-243 3.68E-06 2.23E-07 2.50E+01 Ta-182 2.73E-11 1.65E-12 2.50E+01 Total 6.05E+00
Total By Unit Total Units Nuclides Released    Unit        Unit 1        Unit 2     Unit 3    1, 2 and 3
: 1. Fission gases Ar-41          Ci      < LLD          < LLD      < LLD          < LLD Kr-83m          Ci      < LLD          < LLD      < LLD          < LLD Kr-85          Ci      < LLD          < LLD      < LLD          < LLD Kr-85m          Ci      < LLD          < LLD      < LLD          < LLD Kr-87          Ci      < LLD          < LLD      < LLD          < LLD Kr-88          Ci      < LLD          < LLD      < LLD          < LLD Kr-89          Ci      < LLD          < LLD      < LLD          < LLD Kr-90          Ci      < LLD          < LLD      < LLD          < LLD Xe-131m          Ci      < LLD          < LLD      < LLD          < LLD Xe-133          Ci      6.18E-02         < LLD      < LLD        6.18E-02 Xe-133m          Ci      < LLD          < LLD      < LLD          < LLD Xe-135          Ci      < LLD          < LLD      < LLD          < LLD Xe-135m          Ci      < LLD          < LLD      < LLD          < LLD Xe-137          Ci      < LLD          < LLD      < LLD          < LLD Xe-138          Ci      < LLD          < LLD      < LLD          < LLD Total          Ci      6.18E-02         < LLD      < LLD        6.18E-02
: 2. Iodines I-131          Ci      1.72E-05        < LLD    2.35E-05      4.07E-05 I-132          Ci      2.73E-04         < LLD      < LLD        2.73E-04 I-133          Ci      < LLD          < LLD    9.27E-06      9.27E-06 I-134          Ci      < LLD          < LLD      < LLD          < LLD I-135          Ci      < LLD          < LLD      < LLD          < LLD Total          Ci      2.90E-04        < LLD    3.28E-05      3.23E-04 PVNGS 2016 ARERR                                                                          Page 49


2.d. Other (Soil/Oil)
Table 35:
Nuclide Name Percent Abundance Curies Estimated Total Error % H-3 6.70E+01 7.93E-04 2.50E+01Tc-99 2.43E+01 2.88E-04 2.50E+01C-14 8.53E+00 1.01E-04 2.50E+01I-129 1.01E-01 1.19E-06 2.50E+01Cs-137 2.95E-02 3.49E-07 2.50E+01Sb-125 2.95E-02 3.49E-07 2.50E+01Co-60 9.63E-03 1.14E-07 2.50E+01 Total 1.18E-03
Units 1, 2 and 3 Gaseous Effluents- Continuous - Particulates -
Total By Unit Total Units Nuclides Released    Unit      Unit 1          Unit 2      Unit 3  1, 2 and 3
: 3. Particulates Ag-110m          Ci      < LLD            < LLD      < LLD        < LLD Ba-140          Ci      < LLD            < LLD      < LLD        < LLD Br-82          Ci      < LLD            < LLD      < LLD        < LLD Ce-141          Ci      < LLD            < LLD      < LLD        < LLD Ce-144          Ci      < LLD            < LLD      < LLD        < LLD Co-57          Ci    4.88E-06          < LLD      < LLD      4.88E-06 Co-58          Ci    1.59E-03          < LLD    2.19E-05    1.62E-03 Co-60          Ci    5.22E-04          < LLD    7.52E-06    5.29E-04 Cr-51          Ci    5.72E-03          < LLD    4.49E-06    5.72E-03 Cs-134          Ci      < LLD            < LLD      < LLD        < LLD Cs-136          Ci      < LLD            < LLD      < LLD        < LLD Cs-137          Ci      < LLD            < LLD      < LLD        < LLD Cs-138          Ci      < LLD            < LLD      < LLD        < LLD Fe-59          Ci    9.54E-05          < LLD      < LLD      9.54E-05 La-140          Ci      < LLD            < LLD      < LLD        < LLD Mn-54          Ci    1.31E-04           < LLD      < LLD      1.31E-04 Mo-99          Ci      < LLD            < LLD      < LLD        < LLD Nb-95          Ci    1.98E-04          < LLD      < LLD      1.98E-04 Os-191          Ci      < LLD            < LLD    1.38E-06    1.38E-06 Rb-88          Ci      < LLD            < LLD      < LLD        < LLD Ru-103          Ci      < LLD            < LLD      < LLD        < LLD Ru-106          Ci      < LLD            < LLD      < LLD        < LLD Sb-122          Ci      < LLD            < LLD      < LLD        < LLD Sb-124          Ci    7.86E-05          < LLD      < LLD      7.86E-05 Sb-125          Ci      < LLD            < LLD      < LLD        < LLD Se-75          Ci      < LLD            < LLD      < LLD        < LLD Sn-113m          Ci      < LLD            < LLD      < LLD        < LLD Sr-89          Ci      < LLD            < LLD      < LLD        < LLD Sr-90          Ci      < LLD            < LLD      < LLD        < LLD Tc-99m          Ci      < LLD            < LLD      < LLD        < LLD Te-123m          Ci      < LLD            < LLD      < LLD        < LLD Zn-65          Ci      < LLD            < LLD      < LLD        < LLD Zr-95          Ci    1.32E-04          < LLD      < LLD      1.32E-04 Total          Ci    8.47E-03          < LLD      3.53E-05    8.51E-03
: 4. Tritium H-3          Ci        1.24E+02        9.91E+01   1.89E+02    4.13E+02 PVNGS 2016 ARERR                                                                        Page 50


3.b Irradiated Fuel Shipments: None 3.c Supplemental Information: Number of Shipments Mode Of TransportDestination 11 Highway EnergySolutions, UT (BWF) 20 Highway EnergySolutions, UT (Treatment Facility) 3 Highway EnergySolutions, UT (CWF) 8 Highway Waste Control Specialist, TX (CWDF) 1 Highway EnergySolutions, TN BWF = Bulk Waste Facility CWF = Containerized Waste Facility CWDF = Containerized Waste Dispoal Facility TSD = Treatment, Storage, Disposal
Table 36:
: 1) Container Volume in M 3 by Waste Class  Waste Class A Waste Class B Waste Class C a. material 8.10E+01 1.03E+01 1.20E+00  b. material 5.87E+02 0 0  c. material 3.56E-01 0 0  d. material 5.36E+00 0 0  2) Container Activity in Ci by Waste Class (calculated)  Waste Class A Waste Class B Waste Class C  a. material 5.13E+00 1.63E+02 4.39E+01  b. material 1.19E+01 0 0  c. material 6.05E+00 0 0  d. material 8.12E-07 0 0  3) Principal Radionuclides a. material See section 2.0 of the report b. material See section 2.0 of the report c. material See section 2.0 of the report d. material See section 2.0 of the report    4) Source of waste and processing employed  a. material spent resin-dewatered/dried, mech anical filters-no processing, concentrates-dried,concentrates as a liquid-no processing employed b. material non-compacted dry activ e waste - no processing employed c. material Activated mate rial - no processing empoyed d. material Oil - no processing empoyed
Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine -
: 5) Type of Container  a. material (1) Metal Tank or Liner transpor ted as LSA-I, (10) Type A transportation casks transported as LSA-I, (12) Type A transportation casks transported as LSA-II, (4)Type A tranportation casks transported
Total By Unit Total Units Nuclides Released  Unit        Unit 1           Unit 2    Unit 3  1, 2 and 3
: 1. Fission gases Ar-41        Ci      5.43E+00        2.77E-01  2.35E-01   5.94E+00 Kr-83m        Ci        < LLD          < LLD      < LLD        < LLD Kr-85        Ci        < LLD          < LLD      < LLD        < LLD Kr-85m        Ci        < LLD          < LLD      < LLD        < LLD Kr-87        Ci        < LLD          < LLD      < LLD        < LLD Kr-88        Ci        < LLD          < LLD      < LLD        < LLD Kr-89        Ci        < LLD          < LLD      < LLD        < LLD Kr-90        Ci        < LLD          < LLD      < LLD        < LLD Xe-131m        Ci     1.24E-03          < LLD      < LLD      1.24E-03 Xe-133        Ci      1.62E-01         6.47E-02  5.23E-02    2.79E-01 Xe-133m        Ci      1.02E-03          < LLD      < LLD      1.02E-03 Xe-135        Ci      3.33E-03        1.90E-04    < LLD      3.52E-03 Xe-135m        Ci        < LLD          < LLD      < LLD        < LLD Xe-137        Ci        < LLD          < LLD      < LLD        < LLD Xe-138                  < LLD          < LLD      < LLD        < LLD Total        Ci      5.60E+00        3.42E-01  2.87E-01    6.23E+00
: 2. Iodines I-131        Ci        < LLD          < LLD      < LLD        < LLD I-132        Ci        < LLD          < LLD      < LLD        < LLD I-133        Ci        < LLD          < LLD      < LLD        < LLD I-134        Ci        < LLD          < LLD      < LLD        < LLD I-135        Ci        < LLD          < LLD      < LLD        < LLD Total        Ci        < LLD          < LLD      < LLD        < LLD PVNGS 2016 ARERR                                                                      Page 51


as Type A b. material (20) 20' sea land containers transported as LSA-I, (3) Type A tranportation casks tran sported as Type A c. material (1) Type A transportation casks transported as LSA-I d. material (1) Type A tranportation casks transported as Exempt Quantity 6) Solidification agent or absorbent a. material No solidification agents or absorbents used to process material b. material No solidification agents or absorbents used to process material c. material No solidification agents or absorbents used to process material d. material No solidification agents or absorbents used to process material 
Table 37:
Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates -
Total By Unit Total Units Nuclides Released Unit        Unit 1          Unit 2        Unit 3  1,2 and 3
: 3. Particulates Ag-110m        Ci      < LLD            < LLD          < LLD      < LLD Ba-140        Ci      < LLD            < LLD          < LLD      < LLD Br-82        Ci    1.44E-03          < LLD        4.20E-06  1.44E-03 Ce-141        Ci      < LLD            < LLD          < LLD      < LLD Ce-144        Ci      < LLD            < LLD          < LLD      < LLD Co-57        Ci      < LLD            < LLD          < LLD      < LLD Co-58        Ci    4.01E-04          < LLD        3.33E-05  4.34E-04 Co-60        Ci    1.52E-04          < LLD        2.27E-05  1.75E-04 Cr-51        Ci    1.15E-03          < LLD          < LLD    1.15E-03 Cs-134        Ci      < LLD            < LLD          < LLD      < LLD Cs-136        Ci      < LLD            < LLD          < LLD      < LLD Cs-137        Ci      < LLD            < LLD          < LLD      < LLD Cs-138        Ci      < LLD            < LLD          < LLD      < LLD Fe-59        Ci    8.86E-06          < LLD          < LLD    8.86E-06 La-140        Ci      < LLD            < LLD          < LLD      < LLD Mn-54        Ci    3.44E-05          < LLD        1.34E-07  3.46E-05 Mo-99        Ci      < LLD            < LLD          < LLD      < LLD Nb-95        Ci    5.04E-05          < LLD        2.72E-05  7.76E-05 Os-191        Ci      < LLD            < LLD          < LLD      < LLD Rb-88        Ci      < LLD            < LLD          < LLD      < LLD Ru-103        Ci      < LLD            < LLD          < LLD      < LLD Ru-106        Ci      < LLD            < LLD          < LLD      < LLD Sb-122        Ci      < LLD            < LLD          < LLD      < LLD Sb-124        Ci      < LLD            < LLD          < LLD      < LLD Sb-125        Ci      < LLD            < LLD          < LLD      < LLD Se-75        Ci      < LLD            < LLD          < LLD      < LLD Sn-113m        Ci      < LLD            < LLD          < LLD      < LLD Sr-89        Ci      Note 1          Note 1         Note 1    Note 1 Sr-90        Ci      Note 1          Note 1          Note 1    Note 1 Tc-99m        Ci      < LLD            < LLD          < LLD      < LLD Te-123m        Ci      < LLD            < LLD          < LLD      < LLD Zn-65        Ci      < LLD            < LLD          < LLD      < LLD Zr-95        Ci    5.29E-06          < LLD        2.09E-05  2.62E-05 Total        Ci    3.24E-03          < LLD        1.08E-04  3.34E-03
: 4. Tritium H-3        Ci    9.31E+02        1.52E+02      9.44E+02  2.03E+03 Note 1 - Not required for batch releases PVNGS 2016 ARERR                                                                        Page 52


APPENDIX B METEOROLOGY
Table 38:
Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
Total By Unit Total Units Nuclides Released  Unit        Unit 1          Unit 2    Unit 3    1, 2 and 3
: 1. Fission gases Ar-41          Ci    5.43E+00          2.77E-01  2.35E-01      5.94E+00 Kr-83m          Ci      < LLD          < LLD      < LLD          < LLD Kr-85          Ci      < LLD          < LLD      < LLD          < LLD Kr-85m          Ci      < LLD          < LLD      < LLD          < LLD Kr-87          Ci      < LLD          < LLD      < LLD          < LLD Kr-88          Ci      < LLD          < LLD      < LLD          < LLD Kr-89          Ci      < LLD          < LLD      < LLD          < LLD Kr-90          Ci      < LLD          < LLD      < LLD          < LLD Xe-131m          Ci    1.24E-03          < LLD      < LLD        1.24E-03 Xe-133          Ci    2.24E-01        6.47E-02  5.23E-02      3.41E-01 Xe-133m          Ci    1.02E-03          < LLD      < LLD        1.02E-03 Xe-135          Ci    3.33E-03        1.90E-04    < LLD        3.52E-03 Xe-135m          Ci      < LLD          < LLD      < LLD          < LLD Xe-137          Ci      < LLD          < LLD      < LLD          < LLD Xe-138          Ci      < LLD          < LLD      < LLD          < LLD Total          Ci    5.66E+00          3.42E-01  2.87E-01      6.29E+00
: 2. Iodines I-131          Ci    1.72E-05          < LLD    2.35E-05      4.07E-05 I-132          Ci    2.73E-04          < LLD      < LLD        2.73E-04 I-133          Ci      < LLD          < LLD    9.27E-06      9.27E-06 I-134          Ci      < LLD          < LLD      < LLD          < LLD I-135          Ci      < LLD          < LLD      < LLD          < LLD Total          Ci    2.90E-04          < LLD    3.28E-05      3.23E-04 PVNGS 2016 ARERR                                                                        Page 53


JOINT FREQUENCY DISTRIBUTION TABLES The tables presented in this section are results obtained from processing the hourly meteorological data collected  at  the  Palo  Verde Nuclear  Generating  Station for  the  period  of January - December 2016. The joint frequency distribution (JFD) tables represent the frequency, in terms of the number of observations, that a particular wind speed, wind direction, and stability category occurred simultaneously. On a quarterly, semiannual and annual basis, the JFDs were produced for 35-foot wind speed and wind direction by atmospheric stability class corresponding to the seven Pasquill stability categories, and for wind speed and wind direction for all stability classes combined. Atmospheric stability was classified per Regulatory Guide 1.23, using the 200-foot to 35-foot temperature difference (delta T).
Table 39:
In accordance with NUREG-0133, the batch releases for the year were considered as "long term,"
Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates -
since the batch releases are sufficiently random in both time of day and duration. Consequently, the JFDs for the batch releases for all quarters are the same as for the continuous releases.
Total By Unit Total Units Nuclides Released  Unit        Unit 1          Unit 2    Unit 3    1, 2 and 3
Discussion A summary of 2016 Joint Frequency Distribution (JFD) shows a somewhat typical, but variable year. Of the 8784 hours available, 223 hours of data were lost due to data being overwritten for an effective 97.6% data recovery.
: 3. Particulates Ag-110m        Ci      < LLD            < LLD      < LLD        < LLD Ba-140        Ci      < LLD            < LLD      < LLD        < LLD Br-82        Ci    1.44E-03          < LLD    4.20E-06      1.44E-03 Ce-141        Ci      < LLD            < LLD      < LLD        < LLD Ce-144        Ci      < LLD            < LLD      < LLD        < LLD Co-57        Ci      4.88E-06          < LLD      < LLD      4.88E-06 Co-58        Ci      1.99E-03          < LLD    5.52E-05      2.05E-03 Co-60        Ci      6.74E-04          < LLD    3.02E-05      7.04E-04 Cr-51        Ci      6.86E-03          < LLD    4.49E-06      6.87E-03 Cs-134        Ci      < LLD            < LLD      < LLD        < LLD Cs-136        Ci      < LLD            < LLD      < LLD        < LLD Cs-137        Ci      < LLD            < LLD      < LLD        < LLD Cs-138        Ci      < LLD            < LLD      < LLD        < LLD Fe-59        Ci    1.04E-04          < LLD      < LLD      1.04E-04 La-140        Ci      < LLD            < LLD      < LLD        < LLD Mn-54        Ci    1.65E-04          < LLD    1.34E-07      1.65E-04 Mo-99        Ci      < LLD            < LLD      < LLD        < LLD Nb-95        Ci      2.48E-04          < LLD    2.72E-05      2.75E-04 Os-191        Ci      < LLD            < LLD    1.38E-06      1.38E-06 Rb-88        Ci      < LLD            < LLD      < LLD        < LLD Ru-103        Ci      < LLD            < LLD      < LLD        < LLD Ru-106        Ci      < LLD            < LLD      < LLD        < LLD Sb-122        Ci      < LLD            < LLD      < LLD        < LLD Sb-124        Ci    7.86E-05          < LLD      < LLD      7.86E-05 Sb-125        Ci      < LLD            < LLD      < LLD        < LLD Se-75        Ci      < LLD            < LLD      < LLD        < LLD Sn-113m        Ci      < LLD            < LLD      < LLD        < LLD Sr-89        Ci      < LLD            < LLD      < LLD        < LLD Sr-90        Ci      < LLD            < LLD      < LLD        < LLD Tc-99m        Ci      < LLD            < LLD      < LLD        < LLD Te-123m        Ci      < LLD            < LLD      < LLD        < LLD Zn-65        Ci      < LLD            < LLD      < LLD        < LLD Zr-95        Ci      1.37E-04          < LLD    2.09E-05      1.58E-04 Total        Ci      1.17E-02          < LLD    1.44E-04      1.19E-02 Total > 8 days    Ci      1.33E-06        1.03E-02  1.52E-06      1.03E-02
The average 35 foot mean wind speed was 6.7 mph. Distribution of directions was spread over the compass with a predominant direction (3 sectors of 22.5 degrees each) centered on southwest (29.9%). A secondary maximum of three sectors centered on the north contained 26.9% of the total. Southwesterly flow winds averaged higher speeds with the most frequent speed at 10 mph. With the northerly directions, the highest frequency occurred at 4.0 mph.
: 4. Tritium H-3          Ci    1.06E+03        2.51E+02    1.13E+03      2.44E+03 PVNGS 2016 ARERR                                                                        Page 54
Stability class summary:
Stability class E, F, G, (stable categories) 59.1%.
Stability class G, (extremely stable) 25.2%. Stability class A, B, C, (unstable categories) 21.8%.
Stability class D, (neutral category) 19.1%.
Overall stable conditions (E,F,G) existed for the year.
ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  3/31/2016                                                        
Table 40:
Estimation of Total Percent Error The estimated total error is calculated as follows:
Total Percent Error = (E 12 + E22 + E32 + ... + En2 )1/2 Where En = Percent error associated with each contributing parameter.
Parameters contributing to errors in the measurement of gaseous effluents; process flow rates, sample collection, analytical counting and tank volumes.
The following values (%) were used for error calculations.
Fission & Act gases          I-131    Particulates      Tritium 25          25            25            25                    Sample counting error 10          10            10            10              Counting system calibration error 5            5              5            5                Counting system source error 20          N/A          N/A            N/A            Temperature/volume correction error 10          10            10            10              Process flow measuring device (1)
N/A          15              15            15                Sample flow measuring device N/A            5          N/A            N/A              Iodine collection efficiency error N/A          N/A            10            N/A                        Plateout error N/A          N/A          N/A            20              Bubbler collection efficiency error N/A          N/A          N/A              2            Sample volume transfer error (pipette)
N/A          N/A          N/A              2              Sample volume error (graduate)
Note 1 - % of full scale PVNGS 2016 ARERR                                                                                      Page 55


                                                              *** 1ST QRTR ***                                                     
Table 41:
Effluent Monitoring Instrumentation Out Of Service Greater Than 30 Days Date span of            Cause of Unit      Instrument                                                      Explanation inoperability        inoperability 2      Unit 2 Fuel        2/11/2016      Condition Report 16-      Condition Report 16-03957 Building          through      02244 documents the        determined that a ventilation Ventilation Flow    4/14/2016    flow transmitter failing  inspection panel was found transmitter                      its acceptance criteria  open, however, it took greater 2JHFBFT0093**I                      for FUNCTIONALITY      than 30 days to find and fix the XMITR                              due to low flow                problem.
indication.
PVNGS 2016 ARERR                                                                              Page 56


STABILITY CLASS  A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
Table 42:
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  4.51- 5.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  5.51- 6.50      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0      0 1   6.51- 8.50      0      0      0      0      0      2      0      2      2      0      1     3      1      0      0      0 11  8.51-11.50      1      0      0      0      0      1      0      0      0      1      4      1      5      4      3     1 21  11.51-14.50      0      0      0      0      0      0      0      0      0      1      6     5      1      0      2     1 16  14.51-20.50      0      0      0      0      0      0      0      0      0      4      0      2     0      3      0      3 12    >20.50        0      0      0      0      0      0      0      0      0      1     0      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Solid Waste Summary A. Solid Waste Shipped Offsite For Burial Or Disposal (not irradiated fuel) 1.0 Type of Waste                    Unit     Jan-Dec 2016      estimated total error %
____    TOTAL         1      0      0      0      0      3      0      2     2      8    11    11      7      7      5      5 62                                                                                                                               
1.a. Spent resin, filters, sludges,        m3            9.25E+01        2.50E+01 evaporator bottoms, etc.                 Ci          2.12E+02        2.50E+01 1.b. Dry compressible waste,              m3            5.87E+02        2.50E+01 contaminated equipment, etc                Ci          1.19E+01        2.50E+01 1.c. Irradiated components, control rods,        m3            3.56E-01        2.50E+01 etc.                          Ci          6.05E+00        2.50E+01 m3            5.36E+00        2.50E+01 1.d. Other (Oil)
Ci          8.12E-07         2.50E+01 PVNGS 2016 ARERR                                                                    Page 57


STABILITY CLASS  B                                                   
2.0 Estimate of major nuclide composition 2.a. Spent resin, filters, sludge, evaporator bottoms, etc.
Nuclide            Percent                        Estimated Total Curies Name            Abundance                            Error %
Ni-63            5.24E+01          1.11E+02        2.50E+01 Fe-55            1.76E+01          3.72E+01        2.50E+01 Co-60            1.28E+01          2.71E+01        2.50E+01 Co-58            6.82E+00          1.44E+01        2.50E+01 Cs-137            3.11E+00          6.58E+00        2.50E+01 C-14            2.19E+00          4.64E+00        2.50E+01 Mn-54            1.44E+00          3.06E+00        2.50E+01 Sb-125            1.40E+00          2.96E+00        2.50E+01 H-3            1.33E+00          2.81E+00        2.50E+01 Co-57            6.21E-01          1.31E+00        2.50E+01 Ni-59            6.74E-02          1.43E-01        2.50E+01 Sr-90            5.56E-02          1.18E-01        2.50E+01 Tc-99            5.25E-02          1.11E-01        2.50E+01 Ce-144            4.87E-02          1.03E-01        2.50E+01 Pu-241            1.74E-02          3.68E-02        2.50E+01 Ag-110m            1.68E-02          3.57E-02        2.50E+01 Cs-134            1.44E-02          3.05E-02        2.50E+01 Zr-95            1.32E-02          2.79E-02        2.50E+01 I-129            1.21E-02          2.57E-02        2.50E+01 Cr-51            8.18E-03          1.73E-02        2.50E+01 Zn-65            7.61E-03          1.61E-02        2.50E+01 Nb-95            7.21E-03          1.53E-02        2.50E+01 Sn-113            3.06E-03          6.48E-03        2.50E+01 Sb-124            2.82E-03          5.96E-03        2.50E+01 Am-241            1.22E-03          2.58E-03        2.50E+01 Pu-238            7.64E-04          1.62E-03        2.50E+01 Cm-243            6.56E-04          1.39E-03        2.50E+01 Pu-239            4.91E-04          1.04E-03        2.50E+01 Fe-59            4.33E-04          9.17E-04        2.50E+01 Sr-89            2.41E-04          5.11E-04        2.50E+01 Am-243            5.62E-05          1.19E-04        2.50E+01 Cm-242            2.11E-05          4.47E-05        2.50E+01 Te-123m            7.65E-06          1.62E-05        2.50E+01 Pu-242            6.89E-06          1.46E-05        2.50E+01 Be-7            4.16E-11          8.81E-11        2.50E+01 Hf-181            8.41E-18          1.78E-17        2.50E+01 Ru-103            2.99E-27          6.32E-27        2.50E+01 Ce-141            5.48E-30          1.16E-29        2.50E+01 Total            2.12E+02 PVNGS 2016 ARERR                                                                Page 58


SPEED (MPH)        N    NNE     NE    ENE      E    ESE     SE    SSE      S    SSW     SW    WSW      W    WNW     NW    NNW  T OTAL  ___________                                                                                                                  _
2.b. Dry compressible waste, contaminated equip, etc.
____     CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      1     0      0      0      0      0      0      0 1   4.51- 5.50      0      1     0      1     0      0      0      1     0      1     0      0      0      1     1      0 6   5.51- 6.50      0      1      0      0      0      0      0      1      4      1      3      2     1      0      0      0 13  6.51- 8.50      0      1      3     3      1      1      0      2     1      3     6      4     2     1     0      0 28  8.51-11.50      0      1     0      1      0      1      0      0      0      2     3      4      1      1      0      2 16  11.51-14.50      0      0      0      0      0      0      0      0      0      2     5     1      0      0      0      0 8  14.51-20.50      0      0      0      0      0      0      0      0      0      1     1     0      0      0      0      0 2     >20.50        0      0      0      0      0      0      0      0      0      1     0      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Estimated Nuclide Percent Abundance          Curies     Total Error Name Cr-51          4.87E+01            5.82E+00     2.50E+01 Co-58          1.41E+01            1.69E+00     2.50E+01 Nb-95          1.25E+01            1.50E+00    2.50E+01 Zr-95          1.07E+01            1.27E+00    2.50E+01 Co-60          7.57E+00            9.05E-01     2.50E+01 Fe-55          2.04E+00            2.44E-01     2.50E+01 Mn-54          1.52E+00            1.82E-01    2.50E+01 Fe-59            7.88E-01            9.42E-02    2.50E+01 Ni-63            4.70E-01            5.62E-02    2.50E+01 H-3             2.90E-01            3.47E-02    2.50E+01 Sn-113            2.25E-01            2.69E-02    2.50E+01 Sb-125            1.84E-01            2.20E-02    2.50E+01 Zn-65            1.67E-01            1.99E-02    2.50E+01 Ce-144            1.56E-01            1.86E-02    2.50E+01 C-14            1.45E-01            1.73E-02    2.50E+01 Hf-181            9.76E-02            1.17E-02    2.50E+01 Te-6.54E-02            7.82E-03    2.50E+01 123m Sb-124            6.05E-02            7.23E-03    2.50E+01 Co-57            5.36E-02            6.40E-03    2.50E+01 Cs-137            3.84E-02            4.59E-03    2.50E+01 Tc-99            3.53E-02            4.22E-03    2.50E+01 Sr-90            8.52E-03            1.02E-03    2.50E+01 I-129            7.06E-03            8.44E-04    2.50E+01 Cm-242            2.16E-04            2.58E-05    2.50E+01 Pu-239            8.84E-05            1.06E-05    2.50E+01 Am-241            7.03E-05            8.40E-06    2.50E+01 Sc-46            6.53E-05            7.80E-06    2.50E+01 Cm-243            5.98E-05            7.14E-06    2.50E+01 Sr-89            1.58E-05            1.89E-06    2.50E+01 Pu-241            1.73E-06            2.07E-07     2.50E+01 Pu-238            1.82E-08            2.18E-09     2.50E+01 1.00E+02            1.19E+01 PVNGS 2016 ARERR                                                            Page 59
____     TOTAL        0      4      3      5      1     2     0      4      6     11    18    11      4      3      1     2 75 


STABILITY CLASS  C SPEED (MPH)         N    NNE    NE    ENE     E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
2.c. Irradiated components, control rods, etc.
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0   1.51- 2.50      1      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 1   2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      1      0      0      0      0 1   3.51- 4.50      0      0      0      0      0      0      0      0      1     2      1     2     2      0      0      1 9  4.51- 5.50      1      0      1      3      3      0      1      2     6     4      2     0      1      0      0      3 27   5.51- 6.50      2     2     4      1     1     1      0      2     5     8     5     2     0      1      0      2 36  6.51- 8.50      0      3      4     2     4      2     2     0      4      3      3      2     0      1     0      1 31  8.51-11.50      0      0      4      1     1     1     0      0      2     1     0      0      0      0      0      0 10  11.51-14.50      0      0      0      0      0      0      0      0      0      1      3     0      1      0      0      0 5 14.51-20.50      0      0      0      0      0      0      0      0      0      1      2     0      0      1      0      0 4    >20.50       0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Estimated Nuclide         Percent Curies     Total Error Name        Abundance Co-60        7.14E+01 4.32E+00        2.50E+01 Fe-55        1.75E+01 1.06E+00        2.50E+01 Ni-63        9.50E+00   5.75E-01      2.50E+01 Cr-51       4.69E-01  2.84E-02      2.50E+01 Co-58        4.26E-01   2.58E-02      2.50E+01 Zr-95        3.01E-01  1.82E-02      2.50E+01 Nb-95        1.80E-01  1.09E-02      2.50E+01 Mn-54        8.28E-02  5.01E-03      2.50E+01 Ni-59        6.21E-02  3.76E-03      2.50E+01 H-3         2.15E-02   1.30E-03      2.50E+01 C-14        2.08E-02  1.26E-03      2.50E+01 Fe-59        1.56E-02  9.44E-04      2.50E+01 Sb-125        1.07E-02  6.47E-04      2.50E+01 Sn-113        8.99E-03  5.44E-04      2.50E+01 Zn-65        8.42E-03  5.10E-04      2.50E+01 Ce-144        7.14E-03  4.32E-04      2.50E+01 Co-57        2.73E-03  1.65E-04      2.50E+01 Te-123m        2.66E-03  1.61E-04      2.50E+01 Cs-137        2.21E-03  1.34E-04      2.50E+01 Hf-181        1.82E-03  1.10E-04      2.50E+01 Sb-124        1.62E-03  9.80E-05      2.50E+01 Nb-94        1.05E-03  6.35E-05      2.50E+01 Sr-90        5.24E-04  3.17E-05      2.50E+01 I-129        9.71E-05  5.88E-06      2.50E+01 Tc-99        6.31E-05  3.82E-06      2.50E+01 Cm-242        9.90E-06  5.99E-07      2.50E+01 Pu-239       5.48E-06  3.32E-07      2.50E+01 Am-241        4.34E-06  2.63E-07      2.50E+01 Cm-243        3.68E-06  2.23E-07      2.50E+01 Ta-182        2.73E-11  1.65E-12      2.50E+01 Total    6.05E+00 PVNGS 2016 ARERR                                                    Page 60
____    TOTAL        4      5     13      7      9      4      3     4     18    20    16      7      4      3     0      7 124  ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO  3/31/2016    
2.d. Other (Soil/Oil)
                                                          *** 1ST QRTR ***
Estimated Nuclide Percent        Curies  Total Name Abundance                Error %
H-3  6.70E+01      7.93E-04 2.50E+01 Tc-99 2.43E+01      2.88E-04 2.50E+01 C-14  8.53E+00      1.01E-04 2.50E+01 I-129  1.01E-01      1.19E-06 2.50E+01 Cs-137  2.95E-02      3.49E-07 2.50E+01 Sb-125  2.95E-02      3.49E-07 2.50E+01 Co-60    9.63E-03      1.14E-07 2.50E+01 Total      1.18E-03 PVNGS 2016 ARERR                                          Page 61


STABILITY CLASS  D STABILITY BASED ON: DELTA T     BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT: 35.0 FEET
3.b Irradiated Fuel Shipments: None 3.c Supplemental Information:
Number of      Mode Of                    Destination Shipments     Transport 11        Highway          EnergySolutions, UT (BWF)
EnergySolutions, UT (Treatment 20        Highway                      Facility) 3        Highway          EnergySolutions, UT (CWF) 8        Highway      Waste Control Specialist, TX (CWDF) 1        Highway              EnergySolutions, TN BWF = Bulk Waste Facility CWF = Containerized Waste Facility CWDF = Containerized Waste Dispoal Facility TSD = Treatment, Storage, Disposal
: 1) Container Volume in M3 by Waste Class Waste Class A            Waste Class B          Waste Class C
: a. material            8.10E+01                  1.03E+01              1.20E+00
: b. material            5.87E+02                      0                    0
: c. material            3.56E-01                      0                    0
: d. material            5.36E+00                      0                    0
: 2) Container Activity in Ci by Waste Class (calculated)
Waste Class A            Waste Class B          Waste Class C
: a. material            5.13E+00                  1.63E+02              4.39E+01
: b. material            1.19E+01                      0                    0
: c. material            6.05E+00                      0                    0
: d. material            8.12E-07                      0                    0
: 3) Principal Radionuclides
: a. material    See section 2.0 of the report
: b. material    See section 2.0 of the report
: c. material    See section 2.0 of the report
: d. material    See section 2.0 of the report
: 4) Source of waste and processing employed spent resin-dewatered/dried, mechanical filters-no processing,
: a. material    concentrates-dried,concentrates as a liquid-no processing employed
: b. material    non-compacted dry active waste - no processing employed
: c. material    Activated material - no processing empoyed
: d. material    Oil - no processing empoyed PVNGS 2016 ARERR                                                                      Page 62
: 5) Type of Container (1) Metal Tank or Liner transported as LSA-I, (10) Type A transportation casks transported as LSA-I, (12) Type A transportation casks transported as LSA-II, (4)Type A tranportation casks transported
: a. material    as Type A (20) 20' sea land containers transported as LSA-I, (3) Type A
: b. material    tranportation casks transported as Type A
: c. material    (1) Type A transportation casks transported as LSA-I
: d. material    (1) Type A tranportation casks transported as Exempt Quantity
: 6) Solidification agent or absorbent
: a. material    No solidification agents or absorbents used to process material
: b. material    No solidification agents or absorbents used to process material
: c. material    No solidification agents or absorbents used to process material
: d. material    No solidification agents or absorbents used to process material PVNGS 2016 ARERR                                                                        Page 63


WIND THRESHOLD  AT:  .75 MPH 
APPENDIX B METEOROLOGY PVNGS 2016 ARERR            Page 61


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
JOINT FREQUENCY DISTRIBUTION TABLES The tables presented in this section are results obtained from processing the hourly meteorological data collected at the Palo Verde Nuclear Generating Station for the period of January -
____    CALM 0    .76- 1.50      0      0      1      0      0      0      0      0      0      0      0      0      0      0      0      0 1  1.51- 2.50      1      1      2      0      0      0      2      3      2      5      5      2      2      0      1      2 28  2.51- 3.50    12      4      1      3      3      3      5      7    16    15    13      8      3      6     2      5 106  3.51- 4.50      5      5      7     5      0      1      2      3     13    18    11      4      5      1      6      3 89  4.51- 5.50      6    11      9     5      1      1      6      5      9      7      9      4      2     3      1      3 82  5.51- 6.50      2      3      8      3      0      1      0      2      3      9     5      5      0      1      2      1 45  6.51- 8.50      5      4     5      6      1      0     0      0      2      3      6      4      3      1     1      1 42  8.51-11.50      0      0      4      1      6      3      0      0      0      4      6      6      4      0      2     1 37  11.51-14.50      0      0      0      1      4      0      0      0      0      4      7      3      2      0      0      1 22  14.51-20.50      0      0      0      0      6      0      0      0      2      3      2      1     4      6      0      0 24    >20.50        0      0      0      0      0      0      0      0      0      3      0      0      0      0      0      0 3  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
December 2016. The joint frequency distribution (JFD) tables represent the frequency, in terms of the number of observations, that a particular wind speed, wind direction, and stability category occurred simultaneously. On a quarterly, semiannual and annual basis, the JFDs were produced for 35-foot wind speed and wind direction by atmospheric stability class corresponding to the seven Pasquill stability categories, and for wind speed and wind direction for all stability classes combined. Atmospheric stability was classified per Regulatory Guide 1.23, using the 200-foot to 35-foot temperature difference (delta T).
____    TOTAL        31    28    37    24    21      9    15    20    47    71    64    37    25    18    15    17 479                                                          STABILITY CLASS  E                                                  
In accordance with NUREG-0133, the batch releases for the year were considered as long term, since the batch releases are sufficiently random in both time of day and duration. Consequently, the JFDs for the batch releases for all quarters are the same as for the continuous releases.
Discussion A summary of 2016 Joint Frequency Distribution (JFD) shows a somewhat typical, but variable year. Of the 8784 hours available, 223 hours of data were lost due to data being overwritten for an effective 97.6% data recovery.
The average 35 foot mean wind speed was 6.7 mph. Distribution of directions was spread over the compass with a predominant direction (3 sectors of 22.5 degrees each) centered on southwest (29.9%). A secondary maximum of three sectors centered on the north contained 2 6 .9% of the total. Southwesterly flow winds averaged higher speeds with the most frequent speed at 10 mph. With the northerly directions, the highest frequency occurred at 4.0 mph.
Stability class summary:
Stability class E, F, G, (stable categories) 59.1%.
Stability class G, (extremely stable) 25.2%.
Stability class A, B, C, (unstable categories) 21.8%.
Stability class D, (neutral category) 19.1%.
Overall stable conditions (E,F,G) existed for the year.
PVNGS 2016 ARERR                                                                              Page 62


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE     S   SSW    SW    WSW      W    WNW    NW    NNW T OTAL  ___________                                                                                                                  _
ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  3/31/2016
____    CALM 0    .76- 1.50      0      0      0      0      1      0      0      0      0      0      1      1      0      0      2      0 5  1.51- 2.50      5      4      0      0      1     0      0      2     0      2     1      5      0     2     2      1 25  2.51- 3.50      3     2     1      1      0      0      0      0      0      5     4     7      5      5      6     1 40  3.51- 4.50      3     1      0      1      0      0      0      0      2     5      6     6     3      2      5     4 38  4.51- 5.50      3      3      1      1      1      0      0      0      7     9     4     2      1      1      2      3 38  5.51- 6.50      2      2     2     0      0      0      0      0      1      2     4     0      0      3      2      2 20   6.51- 8.50      1      3      1      1      0      1      0      1      3     7     7     6     8     3      2      1 45  8.51-11.50      2      2      1      3     0      3     1      0      0      4      7     4      6     4      1      1 39  11.51-14.50      0      1      0      4     2     0      0      0      0      3     5     2     1    13     1      0 32  14.51-20.50      0      0      0      0     13     0      0      0      1     2      8     3     3     4     0      0 34     >20.50        0      0      0      0      1     0      0      0      3     0      2      2     0      0      0      0 8  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
                                                        *** 1ST QRTR ***
____    TOTAL       19     18      6    11    19     4      1     3     17    39    49    38    27    37    23    13 324                                                                                                                               
STABILITY CLASS    A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE       S   SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                         0
   .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 3.51- 4.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 4.51- 5.50      0      0      0      0      0      0      0      0      0      0    0      0      0     0      0      0      0 5.51- 6.50     0      0      0      0      0      0      0      0      0      1     0      0      0      0      0      0     1 6.51- 8.50      0      0      0     0      0      2      0     2      2      0    1      3      1     0      0      0    11 8.51-11.50     1      0      0      0      0      1      0      0      0      1    4      1     5      4     3      1    21 11.51-14.50     0      0      0     0      0      0     0      0      0     1     6     5     1     0      2      1     16 14.51-20.50      0      0      0      0      0      0      0      0      0      4    0      2      0      3      0      3     12
    >20.50       0     0      0      0      0      0      0     0      0     1     0      0      0      0      0      0     1 TOTAL        1      0      0      0      0     3     0      2      2      8    11    11     7     7      5      5     62 STABILITY CLASS    B SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0     0      0      0     0 1.51- 2.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 3.51- 4.50      0      0      0      0      0      0      0      0      1      0    0      0      0      0      0      0      1 4.51- 5.50      0     1      0      1      0      0      0      1      0      1    0      0      0      1      1      0     6 5.51- 6.50      0      1     0      0      0      0      0     1      4     1    3      2      1      0      0     0    13 6.51- 8.50     0      1     3      3      1      1     0      2      1      3    6      4      2     1      0      0     28 8.51-11.50      0      1      0      1     0      1     0     0      0     2     3      4     1      1     0     2     16 11.51-14.50      0      0      0      0      0      0      0      0      0     2    5     1      0      0      0      0      8 14.51-20.50     0      0      0      0      0      0      0      0      0      1    1      0      0      0      0      0     2
    >20.50        0     0     0     0      0      0      0      0      0      1     0     0      0      0     0     0      1 TOTAL        0     4     3     5      1     2     0      4      6    11    18    11      4      3      1     2     75 STABILITY CLASS    C SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S   SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      1      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      1 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    0     1     0      0      0      0     1 3.51- 4.50      0      0     0      0      0      0      0      0      1      2    1     2      2      0     0      1      9 4.51- 5.50     1     0     1     3     3     0      1     2       6      4    2      0     1     0      0      3    27 5.51- 6.50      2      2     4      1     1      1     0      2      5      8    5      2      0     1      0     2    36 6.51- 8.50     0     3     4      2     4      2      2     0      4     3    3      2      0     1     0     1     31 8.51-11.50      0     0      4      1     1     1      0      0      2      1    0      0      0      0     0      0    10 11.51-14.50     0     0      0      0      0      0     0     0      0     1    3      0     1      0     0      0      5 14.51-20.50      0      0      0      0      0      0      0      0      0      1     2      0     0     1     0     0      4
     >20.50        0      0      0      0      0     0      0      0      0      0    0     0      0     0      0      0      0 TOTAL         4      5     13      7      9      4      3      4      18     20    16     7     4      3      0      7    124 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  3/31/2016
                                                        *** 1ST QRTR ***
PVNGS 2016 ARERR                                                                                                            Page 63


STABILITY CLASS  F                                                  
STABILITY CLASS   D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S   SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      1      0      0      0      0      0      0      0    0      0      0      0      0      0      1 1.51- 2.50      1      1      2      0      0      0      2      3      2      5    5      2      2      0      1      2    28 2.51- 3.50    12      4      1      3      3      3      5      7    16    15    13      8      3      6      2      5    106 3.51- 4.50      5      5      7      5      0      1      2      3    13    18    11      4      5      1      6      3    89 4.51- 5.50      6    11      9      5      1      1      6      5      9      7    9      4      2      3      1      3    82 5.51- 6.50      2      3      8      3      0      1      0      2      3      9    5      5      0      1      2      1    45 6.51- 8.50      5      4      5      6      1      0      0      0      2      3    6      4      3      1      1      1    42 8.51-11.50      0      0      4      1      6      3      0      0      0      4    6      6      4      0      2      1    37 11.51-14.50      0      0      0      1      4      0      0      0      0      4    7      3      2      0      0      1    22 14.51-20.50      0      0      0      0      6      0      0      0      2      3    2      1      4      6      0      0    24
    >20.50        0      0      0      0      0      0      0      0      0      3    0      0      0      0      0      0      3 TOTAL        31    28    37    24    21      9    15      20    47    71    64    37    25    18    15    17    479 STABILITY CLASS    E SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      1      0      0      0      0      0    1      1      0      0      2      0      5 1.51- 2.50      5      4      0      0      1      0      0      2      0      2    1      5      0      2      2      1    25 2.51- 3.50      3      2      1      1      0      0      0      0      0      5    4      7      5      5      6      1    40 3.51- 4.50      3      1      0      1      0      0      0      0      2      5    6      6      3      2      5      4    38 4.51- 5.50      3      3      1      1      1      0      0      0      7      9    4      2      1      1      2      3    38 5.51- 6.50      2      2      2      0      0      0      0      0      1      2    4      0      0      3      2      2    20 6.51- 8.50      1      3      1      1      0      1      0      1      3      7    7      6      8      3      2      1    45 8.51-11.50      2      2      1      3      0      3      1      0      0      4    7      4      6      4      1      1    39 11.51-14.50      0      1      0      4      2      0      0      0      0      3    5      2      1    13      1      0    32 14.51-20.50      0      0      0      0    13      0      0      0      1      2    8      3      3      4      0      0    34
    >20.50        0      0      0      0      1      0      0      0      3      0    2      2      0      0      0      0      8 TOTAL        19    18      6    11    19      4      1      3    17    39    49    38    27    37    23    13    324 STABILITY CLASS    F SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      4      2      0      0      0      0      0      1      1      1    3      3      2      5      3      3    28 2.51- 3.50      4      1      1      3      2      0      0      1      0      2    5      2      5      4    13      7    50 3.51- 4.50      4      2      1      0      0      0      0      0      1      4    5      3      3      2    10    10    45 4.51- 5.50      4      0      1      0      0      0      1      0      1      5    2      4      3      1      5      4    31 5.51- 6.50      1      4      2      0      0      0      0      0      0      6    4      3      4      3      4      5    36 6.51- 8.50      2      3      1      2      1      0      0      2      0      6    10    10      2      5      5      7    56 8.51-11.50      0      1      0      0      0      0      0      0      0    11    4      1      1      9      4      4    35 11.51-14.50      0      0      0      0      0      0      0      0      0      1    0      0      1      0      0      2      4 14.51-20.50      0      0      0      0      1      0      0      0      0      0    0      0      0      0      0      0      1
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 TOTAL        19    13      6      5      4      0      1      4      3    36    33    26    21    29    44    42    286 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  3/31/2016
                                                        *** 1ST QRTR ***
STABILITY CLASS    G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      1      0      0      0      0      0      0      0      0    0      0      0      1      1      0      3 1.51- 2.50    11      3      3      1      2      0      0      0      0      2    1      4      6      7    16    18    74 2.51- 3.50    49    11      8      5      2      3      1      2      2      5    3      1      8    19    34    48    201 3.51- 4.50    68    13      3      3      1      1      1      2      1      2    1      2      7    12    26    71    214 4.51- 5.50    66    14      2      2      0      1      0      0      1      1    3      3      2      5    17    38    155 5.51- 6.50    36    19      3      1      0      0      0      0      0      2    1      1      2      5      5    12    87 6.51- 8.50    42    10      1      0      0      0      0      0      1      2    1      1      1      0      1    12    72 8.51-11.50    13    10      1      0      0      0      0      0      0      2    0      0      0      0      0      2    28 11.51-14.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 14.51-20.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 TOTAL      285    81    21    12      5      5      2      4      5    16    10    12    26    49    100    201    834 PVNGS 2016 ARERR                                                                                                            Page 64


SPEED (MPH)         N    NNE     NE   ENE     E    ESE     SE    SSE     S    SSW     SW    WSW      W    WNW    NW   NNW T OTAL  ___________                                                                                                                  _
STABILITY CLASS    ALL SPEED (MPH)       N    NNE     NE     ENE       E    ESE       SE    SSE         S   SSW   SW     WSW      W   WNW   NW   NNW TOTAL CALM                                                                                                                                 0
____    CALM 0    .76- 1.50      0      0      0     0     0     0     0     0      0     0     0     0     0     0     0      0 0  1.51- 2.50      4     2      0      0      0      0      0      1     1     1      3      3     2     5     3     3 28  2.51- 3.50     4      1      1      3      2     0      0     1      0      2      5      2     5     4     13     7 50   3.51- 4.50     4     2     1      0      0      0      0      0      1     4     5     3      3     2     10     10 45  4.51- 5.50      4     0      1      0      0      0      1     0      1     5      2      4      3     1      5      4 31  5.51- 6.50      1      4      2      0      0      0      0      0      0     6      4     3      4      3     4     5 36   6.51- 8.50      2     3     1     2      1     0      0     2      0     6     10     10      2      5     5     7 56  8.51-11.50      0      1      0     0     0     0      0     0     0    11      4      1     1     9      4      4 35  11.51-14.50      0      0      0     0     0      0     0     0      0     1      0     0      1      0     0      2 4  14.51-20.50      0      0      0      0      1     0     0      0     0     0     0     0      0     0      0     0 1     >20.50       0      0     0     0     0     0      0      0     0     0     0     0      0     0     0     0 0 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
   .76- 1.50      0      1        1      0        1        0      0      0         0     0     1        1    0     1    3    0       9 1.51- 2.50    22    10        5      1        3        0       2     6        3    10    10      14    10    14    22    24    156 2.51- 3.50    68    18     11      12        7        6      6    10      18    27    25      19    21    34    55    61    398 3.51- 4.50    80    21     11        9        1        2      3     5      19    31    24      17    20    17    47    89    396 4.51- 5.50    80    29     14      12        5        2      8     8      24    27    20      13    9    11    26    51    339 5.51- 6.50    43    31     19        5        1        2      0      5      13    29    22      13    7    13    13    22    238 6.51- 8.50    50    24      15      14        7        6      2     7      13    24    34      30    17    11    9    22    285 8.51-11.50     16    14     10        6        7        9      1     0        2   25    24      16    17    18    10    11    186 11.51-14.50     0      1        0      5        6        0      0     0        0    12    26      11    6    13    3    4      87 14.51-20.50     0      0        0      0      20        0      0      0         3    11    13        6    7    14    0    3     77
____     TOTAL        19     13      6      5      4      0     1     4     3    36     33     26     21     29     44     42 286  ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
     >20.50      0     0        0      0        1       0      0     0        3     5    2        2    0    0    0    0     13 TOTAL     359    149     86      64      59     27      22    41      98    201  201    142    114  146  188  287    2184 TOTAL NUMBER OF OBSERVATIONS: 2184 TOTAL NUMBER OF VALID OBSERVATIONS: 2184 TOTAL NUMBER OF MISSING OBSERVATIONS:          0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
MEAN WIND SPEED FOR THIS PERIOD:     5.9 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:          0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A            B        C            D          E        F        G 2.84        3.43      5.68        21.93      14.84    13.10    38.19 DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE        E    ESE      SE    SSE      S    SSW    SW  WSW        W  WNW    NW  NNW  CALM A          1    0      0        0      0        3        0      2     2        8  11    11        7    7    5    5    0 B          0    4      3        5      1       2        0      4     6      11    18    11        4    3    1     2    0 C          4    5    13        7      9        4        3      4    18        20    16     7        4    3     0    7    0 D        31  28    37      24      21        9      15     20    47        71    64    37      25    18    15    17     0 E        19  18      6     11     19        4        1       3    17        39    49    38      27    37    23    13     0 F        19  13      6        5      4        0        1      4     3      36    33    26      21    29    44    42      0 G        285  81    21      12        5        5        2       4     5       16    10    12      26    49  100  201      0 TOTAL     359  149    86      64     59      27      22     41     98      201    201  142     114  146  188   287      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD      4/01/2016 TO    6/30/2016
                                                                *** 2ND QRTR ***
STABILITY CLASS      A STABILITY BASED ON: DELTA T        BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE     NE     ENE        E    ESE        SE    SSE        S  SSW    SW    WSW     W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50     0      0      0        0        0        0      0      0         0    0    0        0    0    0    0    0      0 1.51- 2.50     0      0      0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 2.51- 3.50     0     0      0        0        0        0      0     0        0    0    0        0    0    0    0    0      0 3.51- 4.50      0     0      0        0        0        0      0     0        0    0    0        0    0    0     0     0      0 4.51- 5.50      0     0       0        1        1        1      2     1         3    0    1        0    0    0    0    0      10 5.51- 6.50     0      1      0        0        2        0       1      6      13     7    4        0    0    0    0    0      34 6.51- 8.50     0      0      1       4        3        2       6     8      25    10    18        4     3    3    1    0      88 8.51-11.50     0     1       0        4        8        9      0     4        8    18    21        9    5     0    2    1     90 11.51-14.50      1      1      5        1        1        1      4      0        7    13    16        5    3    3    4    2     67 14.51-20.50     0      0      5        3        2        2      0      1        5    8    3        0    2    1    0     1     33
    >20.50        0      0      1        0        0        0      0      0         0    1    6       1    0    1    1    0     11 TOTAL        1     3      12      13      17    15        13    20      61    57    69      19    13    8    8    4     333 STABILITY CLASS      B SPEED (MPH)        N    NNE     NE     ENE        E    ESE        SE    SSE        S  SSW    SW    WSW     W  WNW    NW   NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50      0     0      0        0        0        0      0     0        0    0    0        0    0    0    0    0      0 1.51- 2.50     0     0      0        0        0        0      0      0         0    0    0        0    0    0    0     0      0 2.51- 3.50     0     0      0        0        0        0      0     0        0    0    0        0    0    0    0    0      0 3.51- 4.50      0      0       0        0        0       0       0      0         0     0    1       0    0    0    0    0      1 4.51- 5.50      0      0       1        2        1        1      1      4      12     0     2        1    1    0     0     1     27 5.51- 6.50     1     1      0       2        1        1      2     3      17     9    4        5    1     2    2    0     51 6.51- 8.50     0      1      2        2        2        5      1      3        9    10    8        4    4    1    0     0      52 8.51-11.50      0      0       2        3        3        2      3     2        2    10    9        2    2    0    0    0     40 11.51-14.50     0      1       0        0       1        3      0      1        0     4    4        0     0     2    0     0      16 14.51-20.50     0      0       2        0       1        0      0      0         0    3    3        1    0     0     0     0      10
    >20.50        0      0       0       0       0       1      0      0         0     1    0       0     0    1    0     0       3 TOTAL        1      3       7        9        9    13        7     13      40     37    31      13     8     6     2     1     200 PVNGS 2016 ARERR                                                                                                                    Page 65


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  3/31/2016     
STABILITY CLASS    C SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    0      0      0      1      0      0      1 3.51- 4.50      0      0      0      0      0      0      0      0      2      2    1      0      0      0      0      0      5 4.51- 5.50      1      0      2      2      1      1      2      4    11      7    0      1      0      1      1      0    34 5.51- 6.50      0      0      2      1      0      0      1      1      6    11    2      5      3      1      0      0    33 6.51- 8.50      0      1      4      5      3      1      1      1      4      6    2      3      3      1      1      0    36 8.51-11.50      0      0      2      1      2      3      1      2      1      4    2      2      3      0      0      0    23 11.51-14.50      1      0      1      0      3      0      1      0      0      2    4      0      0      0      0      0    12 14.51-20.50      0      0      0      0      0      0      0      0      0      1    3      0      0      0      0      0      4
    >20.50        0      0      0      0      0      0      0      0      0      0    1      0      0      0      0      0      1 TOTAL        2      1    11      9      9      5      6      8    24    33    15    11      9      4      2      0    149 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  4/01/2016 TO  6/30/2016
                                                        *** 2ND QRTR ***
STABILITY CLASS    D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE     NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      1      0      0      0      0      0      1      0      0      1    0      0      0      0      0      0      3 1.51- 2.50      0      0      0      1      0      1      4      0      1      1    0      0      3      1      0      0    12 2.51- 3.50      2      1      3      1      3      1      5      4      4      5    6      1      2      2      0      4    44 3.51- 4.50      2      4      4      2      2      4      3      3      8      6    6      2      2      0      0      1    49 4.51- 5.50      0      4      2      0      2      2      3      3      3    10    7      2      3      1      0      0    42 5.51- 6.50      0      0      3      3      0      3      1      0      5      2    2      2      2      1      1      1    26 6.51- 8.50      0      1      4      6      2      0      1      1      4      3    5      4      2      1      0      0    34 8.51-11.50      0      3      2      2      2      5      2      3      2      7    5      4      7      2      0      0    46 11.51-14.50      0      0      1      2      1      0      0      1      2      5    6      1      2      3      0      1    25 14.51-20.50      1      2      1      1      0      2      2      0      2      5    11      2      0      0      2      0    31
    >20.50        0      0      0      0      0      0      0      1      0      1    2      0      0      0      0      0      4 TOTAL        6    15    20    18    12    18    22      16    31    46    50    18    23    11      3      7    316 STABILITY CLASS    E SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      1      1      0      0      0      0      0      0    0      0      0      0      0      0      2 1.51- 2.50      0      1      0      1      2      2      0      1      1      0    1      0      2      2      0      2    15 2.51- 3.50      4      3      0      1      2      1      2      0      0      0    0      1      3      1      7      2    27 3.51- 4.50      0      1      1      1      3      1      0      1      2      1    1      0      0      2      3      1    18 4.51- 5.50      1      1      1      0      0      0      1      0      1      4    4      1      0      1      2      0    17 5.51- 6.50      2      3      4      0      0      0      2      1      3      4    6      5      3      2      1      1    37 6.51- 8.50      3      3    13      3      2      1      3      2      4      9    21      5      6      2      0      3    80 8.51-11.50      4      4      5      3      0      1      2      2      4    12    33    13      8      2      1      7    101 11.51-14.50      4      0      3      0      2      2      3      1      5    14    17      1      0      4      9      4    69 14.51-20.50      1      0      0      0      5      0      0      2      0      6    12      1      2      2      5      3    39
    >20.50        0      0      0      0      1      0      0      1      0      0    0      0      0      0      0      0      2 TOTAL        19    16    28    10    17      8    13      11    20    50    95    27    24    18    28    23    407 STABILITY CLASS    F SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      1      1      0      1      0      0      0      0    0      0      0      0      0      0      3 1.51- 2.50      1      0      0      2      0      1      4      0      1      0    2      2      3      1      2      1    20 2.51- 3.50      5      6      1      4      2      3      3      1      1      1    3      2      5      5      4      6    52 3.51- 4.50      3      2      0      4      1      3      0      0      0      7    5      3      2      5      0      2    37 4.51- 5.50      1      5      5      1      1      1      3      0      0      4    10      9      3      4      1      4    52 5.51- 6.50      3      5      6      3      1      1      3      1      1      6    9      8      3      2      0      5    57 6.51- 8.50      4      5      6      2      0      2      1      0      2    14    20      4      4      2      4      1    71 8.51-11.50      3      0      2      2      0      1      0      0      1      7    16      6      3      3      5      5    54 11.51-14.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 14.51-20.50      0      0      0      1      0      0      0      0      0      0    1      0      0      0      0      0      2
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 TOTAL        20    23    21    20      5    13    14      2      6    39    66    34    23    22    16    24    348 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION PVNGS 2016 ARERR                                                                                                            Page 66


                                                          *** 1ST QRTR ***  
JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD        4/01/2016 TO    6/30/2016
                                                                  *** 2ND QRTR ***
STABILITY CLASS      G STABILITY BASED ON: DELTA T          BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE      NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW  NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      0      0        0        0        0        0      1      0        0    0    0        0    0    0    1    0      2 1.51- 2.50      4      2        0        0        2        1      1      0        0    0    0        1    3    3    2    4      23 2.51- 3.50    21      1        1        3        3        7      4      2        0    0    3        1    0    9    7    8      70 3.51- 4.50    25      9        5        5        0        4      6      0        0    2    3        6    4    6    9    15      99 4.51- 5.50    29    10        2        2        1        4      7      0        0    0    3        1    1    1    4    10      75 5.51- 6.50    11      5        2        0        1        0      2      2        1    1    0        2    0    1    0    4      32 6.51- 8.50      4      2        2        2        1        0      1      1        0    1    0        1    1    0    0    4      20 8.51-11.50      3      1        0        1        0        0      0      0        0    0    0        0    0    0    1    0      6 11.51-14.50      0      0        0        0        0        1      0      0        0    0    0        0    0    0    0    0      1 14.51-20.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0
    >20.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 TOTAL      97    30      12        13        8      17      22      5        1    4    9      12    9    20  24    45    328 STABILITY CLASS ALL SPEED (MPH)        N    NNE      NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW  NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      1      0        2        2        0        1      2      0        0    1    0        0    0    0    1    0      10 1.51- 2.50      5      3        0        4        4        5      9      1        3    1    3        3    11    7    4    7      70 2.51- 3.50    32    11        5        9      10      12      14      7        5    6    12        5    10    18  18    20    194 3.51- 4.50    30    16      10        12        6      12        9      4        12    18    17      11    8    13  12    19    209 4.51- 5.50    32    20      13        8        7      10      19    12        30    25    27      15    8    8    8    15    257 5.51- 6.50    17    15      17        9        5        5      12    14        46    40    27      27    12    9    4    11    270 6.51- 8.50    11    13      32        24      13      11      14    16        48    53    74      25    23    10    6    8    381 8.51-11.50    10      9      13        16      15      21        8    13        18    58    86      36    28    7    9    13    360 11.51-14.50      6      2      10        3        8        7      8      3        14    38    47        7    5    12  13    7    190 14.51-20.50      2      2        8        5        8        4      2      3        7    23    33        4    4    3    7    4    119
    >20.50      0      0        1        0        1        1      0      2        0    3    9        1    0    2    1    0      21 TOTAL      146    91    111        92      77      89      97    75      183  266  335    134    109    89  83  104    2081 TOTAL NUMBER OF OBSERVATIONS: 2088 TOTAL NUMBER OF VALID OBSERVATIONS: 2081 TOTAL NUMBER OF MISSING OBSERVATIONS:          7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.7 %
MEAN WIND SPEED FOR THIS PERIOD:      7.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:            0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A              B        C            D          E        F        G 16.00          9.61      7.16        15.19      19.56    16.72    15.76 DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE          E    ESE      SE    SSE      S      SSW    SW  WSW        W  WNW    NW  NNW  CALM A          1    3    12      13      17      15      13      20    61        57    69    19      13      8    8    4    0 B          1    3      7        9        9      13        7    13    40        37    31    13        8    6    2    1    0 C          2    1    11        9        9        5        6      8    24        33    15    11        9    4    2    0    0 D          6  15    20      18      12      18      22      16    31        46    50    18      23    11      3    7    0 E        19  16    28      10      17        8      13      11    20        50    95    27      24    18    28  23      0 F        20  23    21      20        5      13      14        2      6      39    66    34      23    22    16  24      0 G        97  30    12      13        8      17      22        5      1        4    9  12        9  20    24  45      0 TOTAL      146  91    111      92      77      89      97      75    183      266  335  134      109    89    83  104      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD        1/01/2016 TO    6/30/2016
                                                                  *** 1ST SEMI ***
STABILITY CLASS      A STABILITY BASED ON: DELTA T          BETWEEN 200.0 AND      35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE      NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW  NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 1.51- 2.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 2.51- 3.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 3.51- 4.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 4.51- 5.50      0      0        0        1        1        1      2      1        3    0    1        0    0    0    0    0      10 5.51- 6.50      0      1        0        0        2        0      1      6        13    8    4        0    0    0    0    0      35 6.51- 8.50      0      0        1        4        3        4      6    10        27    10    19        7    4    3    1    0      99 8.51-11.50      1      1        0        4        8      10        0      4        8    19    25      10    10    4    5    2    111 11.51-14.50      1      1        5        1        1        1      4      0        7    14    22      10    4    3    6    3      83 14.51-20.50      0      0        5        3        2        2      0      1        5    12    3        2    2    4    0    4      45
    >20.50      0      0        1        0        0        0      0      0        0    2    6        1    0    1    1    0      12 TOTAL        2      3      12        13      17      18      13    22        63    65    80      30    20    15  13    9    395 PVNGS 2016 ARERR                                                                                                                    Page 67


STABILITY CLASS  G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET  
STABILITY CLASS   B SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S   SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 3.51- 4.50      0      0      0      0      0      0      0      0      1      0    1      0      0      0      0      0      2 4.51- 5.50      0      1      1      3      1      1      1      5    12      1    2      1      1      1      1      1    33 5.51- 6.50      1      2      0      2      1      1      2      4    21    10    7      7      2      2      2      0    64 6.51- 8.50      0      2      5      5      3      6      1      5    10    13    14      8      6      2      0      0    80 8.51-11.50      0      1      2      4      3      3      3      2      2    12    12      6      3      1      0      2    56 11.51-14.50      0      1      0      0      1      3      0      1      0      6    9      1      0      2      0      0    24 14.51-20.50      0      0      2      0      1      0      0      0      0      4    4      1      0      0      0      0    12
    >20.50        0      0      0      0      0      1      0      0      0      2    0      0      0      1      0      0      4 TOTAL        1      7    10    14    10    15      7      17    46    48    49    24    12      9      3      3    275 STABILITY CLASS    C SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      1      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      1 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    0      1      0      1      0      0      2 3.51- 4.50      0      0      0      0      0      0      0      0      3      4    2      2      2      0      0      1    14 4.51- 5.50      2      0      3      5      4      1      3      6    17    11    2      1      1      1      1      3    61 5.51- 6.50      2      2      6      2      1      1      1      3    11    19    7      7      3      2      0      2    69 6.51- 8.50      0      4      8      7      7      3      3      1      8      9    5      5      3      2      1      1    67 8.51-11.50      0      0      6      2      3      4      1      2      3      5    2      2      3      0      0      0    33 11.51-14.50      1      0      1      0      3      0      1      0      0      3    7      0      1      0      0      0    17 14.51-20.50      0      0      0      0      0      0      0      0      0      2    5      0      0      1      0      0      8
    >20.50        0      0      0      0      0      0      0      0      0      0    1      0      0      0      0      0      1 TOTAL        6      6    24    16    18      9      9      12    42    53    31    18    13      7      2      7    273 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  6/30/2016
                                                        *** 1ST SEMI ***
STABILITY CLASS    D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      1      0      1      0      0      0      1      0      0      1    0      0      0      0      0      0      4 1.51- 2.50      1      1      2      1      0      1      6      3      3      6    5      2      5      1      1      2    40 2.51- 3.50    14      5      4      4      6      4    10      11    20    20    19      9      5      8      2      9    150 3.51- 4.50      7      9    11      7      2      5      5      6    21    24    17      6      7      1      6      4    138 4.51- 5.50      6    15    11      5      3      3      9      8    12    17    16      6      5      4      1      3    124 5.51- 6.50      2      3    11      6      0      4      1      2      8    11    7      7      2      2      3      2    71 6.51- 8.50      5      5      9    12      3      0      1      1      6      6    11      8      5      2      1      1    76 8.51-11.50      0      3      6      3      8      8      2      3      2    11    11    10    11      2      2      1    83 11.51-14.50      0      0      1      3      5      0      0      1      2      9    13      4      4      3      0      2    47 14.51-20.50      1      2      1      1      6      2      2      0      4      8    13      3      4      6      2      0    55
    >20.50        0      0      0      0      0      0      0      1      0      4    2      0      0      0      0      0      7 TOTAL        37    43    57    42    33    27    37      36    78  117    114    55    48    29    18    24    795 STABILITY CLASS    E SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      1      1      1      0      0      0      0      0    1      1      0      0      2      0      7 1.51- 2.50      5      5      0      1      3      2      0      3      1      2    2      5      2      4      2      3    40 2.51- 3.50      7      5      1      2      2      1      2      0      0      5    4      8      8      6    13      3    67 3.51- 4.50      3      2      1      2      3      1      0      1      4      6    7      6      3      4      8      5    56 4.51- 5.50      4      4      2      1      1      0      1      0      8    13    8      3      1      2      4      3    55 5.51- 6.50      4      5      6      0      0      0      2      1      4      6    10      5      3      5      3      3    57 6.51- 8.50      4      6    14      4      2      2      3      3      7    16    28    11    14      5      2      4    125 8.51-11.50      6      6      6      6      0      4      3      2      4    16    40    17    14      6      2      8    140 11.51-14.50      4      1      3      4      4      2      3      1      5    17    22      3      1    17    10      4    101 14.51-20.50      1      0      0      0    18      0      0      2      1      8    20      4      5      6      5      3    73
    >20.50        0      0      0      0      2      0      0      1      3      0    2      2      0      0      0      0    10 TOTAL        38    34    34    21    36    12    14      14    37    89  144    65    51    55    51    36    731 PVNGS 2016 ARERR                                                                                                            Page 68


WIND THRESHOLD AT:  .75 MPH  
STABILITY CLASS      F SPEED (MPH)        N    NNE    NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      0      0      1      1        0        1      0      0        0    0    0        0    0    0    0    0      3 1.51- 2.50      5      2      0      2        0        1      4      1        2    1    5        5    5    6    5    4      48 2.51- 3.50      9      7      2      7        4        3      3      2        1    3    8        4    10    9    17    13    102 3.51- 4.50      7      4      1      4        1        3      0      0        1  11    10        6    5    7    10    12      82 4.51- 5.50      5      5      6      1        1        1      4      0        1    9    12      13    6    5    6    8      83 5.51- 6.50      4      9      8      3        1        1      3      1        1  12    13      11    7    5    4    10      93 6.51- 8.50      6      8      7      4        1        2      1      2        2  20    30      14    6    7    9    8    127 8.51-11.50      3      1      2      2        0        1      0      0        1  18    20        7    4    12    9    9      89 11.51-14.50      0      0      0      0        0        0      0      0        0    1    0        0    1    0    0    2      4 14.51-20.50      0      0      0      1        1        0      0      0        0    0    1        0    0    0    0    0      3
    >20.50      0      0      0      0        0        0      0      0        0    0    0        0    0    0    0    0      0 TOTAL      39    36    27      25        9      13      15      6        9  75    99      60    44    51    60    66    634 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD      1/01/2016 TO    6/30/2016
                                                                *** 1ST SEMI ***
STABILITY CLASS      G STABILITY BASED ON: DELTA T        BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:   .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      0      1      0      0        0        0      1      0        0    0    0        0    0    1    2    0      5 1.51- 2.50    15      5      3      1        4        1      1      0        0    2    1        5    9    10    18    22      97 2.51- 3.50    70    12      9      8        5      10        5      4        2    5    6        2    8    28    41    56    271 3.51- 4.50    93    22      8      8        1        5      7      2        1    4    4        8    11    18    35    86    313 4.51- 5.50    95    24      4      4        1        5      7      0        1    1    6        4    3    6    21    48    230 5.51- 6.50    47    24      5      1        1        0      2      2        1    3    1        3    2    6    5    16    119 6.51- 8.50    46    12      3      2        1        0      1      1        1    3    1        2    2    0    1    16      92 8.51-11.50    16    11      1      1        0        0      0      0        0    2    0        0    0    0    1    2      34 11.51-14.50      0      0      0      0        0        1      0      0        0    0    0        0    0    0    0    0      1 14.51-20.50      0      0      0      0        0        0      0      0        0    0    0        0    0    0    0    0      0
    >20.50      0      0      0      0        0        0      0      0        0    0    0        0    0    0    0    0      0 TOTAL      382    111    33      25        13      22      24      9        6  20    19      24    35    69  124  246    1162 STABILITY CLASS ALL SPEED (MPH)        N    NNE    NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      1      1      3      2        1        1      2      0        0    1    1        1    0    1    4    0      19 1.51- 2.50    27    13      5      5        7        5      11      7        6  11    13      17    21    21    26    31    226 2.51- 3.50    100    29    16      21        17      18      20    17        23  33    37      24    31    52    73    81    592 3.51- 4.50    110    37    21      21        7      14      12      9        31  49    41      28    28    30    59  108    605 4.51- 5.50    112    49    27      20        12      12      27    20        54  52    47      28    17    19    34    66    596 5.51- 6.50    60    46    36      14        6        7      12    19        59  69    49      40    19    22    17    33    508 6.51- 8.50    61    37    47      38        20      17      16    23        61  77  108      55    40    21    15    30    666 8.51-11.50    26    23    23      22        22      30        9    13        20  83  110      52    45    25    19    24    546 11.51-14.50      6      3    10        8        14        7      8      3        14  50    73      18    11    25    16    11    277 14.51-20.50      2      2      8      5        28        4      2      3        10  34    46      10    11    17    7    7    196
    >20.50      0      0      1      0        2        1      0      2        3    8    11        3    0    2    1    0      34 TOTAL      505    240    197      156      136    116      119    116      281  467  536    276    223  235  271   391    4265 TOTAL NUMBER OF OBSERVATIONS: 4272 TOTAL NUMBER OF VALID OBSERVATIONS: 4265 TOTAL NUMBER OF MISSING OBSERVATIONS:        7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.8 %
MEAN WIND SPEED FOR THIS PERIOD:    6.8 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:          0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A            B          C            D          E        F        G 9.26        6.45        6.40        18.64      17.14    14.87    27.25 DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE        E      ESE      SE    SSE      S      SSW  SW  WSW        W  WNW    NW  NNW  CALM A          2    3    12      13      17        18      13      22    63        65  80    30      20    15    13      9    0 B          1    7    10      14      10        15        7    17    46        48  49    24      12      9    3    3    0 C          6    6    24      16      18          9        9    12    42        53  31    18      13      7    2    7    0 D        37  43    57      42      33        27      37      36    78      117  114    55      48    29    18    24      0 E        38  34    34      21      36        12      14      14    37        89  144    65      51    55    51    36      0 F        39  36    27      25        9      13      15        6      9      75   99    60      44    51    60    66      0 G        382  111    33      25      13        22      24        9      6      20  19    24      35    69  124  246      0 TOTAL      505  240    197    156      136      116    119      116    281      467 536  276      223  235  271  391      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD      7/01/2016 TO    9/30/2016 PVNGS 2016 ARERR                                                                                                                  Page 69


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E   ESE    SE    SSE     S   SSW    SW    WSW      W    WNW    NW    NNW T OTAL  ___________                                                                                                                  _
                                                          *** 3RD QRTR ***
____    CALM 0    .76- 1.50      0      1      0      0      0      0      0      0      0      0      0      0      0      1      1     0 3  1.51- 2.50    11     3      3      1      2      0      0      0      0     2      1      4      6     7     16     18 74  2.51- 3.50    49     11      8     5     2      3      1      2      2      5      3     1      8     19     34     48 201  3.51- 4.50    68     13     3      3      1      1      1      2      1      2     1      2      7     12     26    71 214  4.51- 5.50    66     14      2      2      0      1     0      0      1      1     3      3     2      5     17     38 155  5.51- 6.50    36     19     3      1     0      0      0      0      0      2     1      1      2     5     5     12 87  6.51- 8.50    42     10     1      0      0      0      0      0     1     2      1      1      1      0      1    12 72  8.51-11.50    13    10     1      0      0      0      0      0      0      2     0      0      0      0      0     2 28  11.51-14.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  14.51-20.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50       0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
STABILITY CLASS    A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E     ESE    SE    SSE       S SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                         0
____     TOTAL       285     81     21    12     5     5     2      4     5     16     10     12     26     49    100   201 834                                                                                                                               
   .76- 1.50      0      0      0      0      0      0      0      0      0    0    0      0      0      0      0      0      0 1.51- 2.50      0      0      0      0      0      0      0      0      0    0    0     0      0      0      0      0     0 2.51- 3.50     0      0      0      0     0      0      0      0      0    0    0      0      0      0      0      0      0 3.51- 4.50     0      0      1      0      0      0      0      0      0    0    0      0      0      0      0     0     1 4.51- 5.50     0      0      1      0      0      0      1      1      0    0     0      0      0      0      0      0     3 5.51- 6.50      0      0      0      2      2      4     3      7      14    5    1      2      0      0      0      1    41 6.51- 8.50      1     2      1     2     4      10     9     18      24    18    18     10      5      3      2     1    128 8.51-11.50     0      1      0      0      3      18      1      5      11    15    26     15     11      3      2      2    113 11.51-14.50      0      0      0     0     1      2      0      2      0    3   12      4     1      0      0      0    25 14.51-20.50      0      0      0      1      0      0      0      1      0    2     3      0      0      0      0      0      7
    >20.50        1      0      0      0      0      0      0      0      0    0    0      0      0      0      0      0     1 TOTAL        2     3      3     5     10      34    14    34      49    43    60    31    17      6      4      4    319 STABILITY CLASS    B SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW     W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0    0    0      0      0      0      0      0     0 1.51- 2.50      0      0      0      0      0      0      0     0      0    0     0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0      0      0      0     0     0      0      0      0      0      0      0 3.51- 4.50     0      0      0      0      0      0      0      0      0     0     0      0      0      0      0      0      0 4.51- 5.50      1      0      0      0      0      0      2     3       6    2    2      0      1      0      0      1    18 5.51- 6.50      0      2      2      0      1      0      0     3     10    6    7     1      1      1     0      0    34 6.51- 8.50      0     2      1      4      3      5      4      5      8    8    13      7      4      0      0     1     65 8.51-11.50      0      0     2      3      3      6      0      0      4     6    17      9      2      2      0      0     54 11.51-14.50     0      0      1      0      1      1      1      0      4    3     7      1      0      0      0      0     19 14.51-20.50      0      0      0      0     2       0      0     1      0    0    2      0      0      0      0      0      5
    >20.50        0      0      0      0      0      0      0      0      0    0    0      0      0      0     0      0      0 TOTAL        1      4      6      7    10      12      7    12      32    25    48    18      8     3      0     2   195 STABILITY CLASS    C SPEED (MPH)        N    NNE    NE    ENE     E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0     0     0      0      0      0      0      0      0 1.51- 2.50     0      0      0      0      0      0      0      0      0     0     0      0      0      0      0      0     0 2.51- 3.50      0      0      0      0      0      0      0      0      0    0    0      0      0      0     0     0      0 3.51- 4.50     0      0     1     0      0      1     1     0      0    0    0      0     1      0      1     0     5 4.51- 5.50     0      1      1      0      1      1      3      2      8     5     3     1      0      0     2      2    30 5.51- 6.50      1     0      0      0      2       0     1      1       8    4    6      4     1     0     0      1    29 6.51- 8.50      0      1      2      2      1      2      2      1      5    12   14      2      3      1      2      0    50 8.51-11.50     0      1      0      1      0      0      0      0      1     5    11      0     1      0      0      0     20 11.51-14.50      1      1      1     0      4      0      0      0      1    0    3     0      0      0      0      0     11 14.51-20.50     1      0      0      0      3      1      0      1      0    1    1      0      0     0      0      0      8
    >20.50        0      0      0      0      0      0      0      0      0    0    0      0      0      0      0      0      0 TOTAL        3      4      5      3    11      5      7      5      23    27    38      7      6      1      5      3    153 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  7/01/2016 TO  9/30/2016
                                                          *** 3RD QRTR ***
STABILITY CLASS    D STABILITY BASED ON: DELTA T     BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0    0    0      0      0      0      0      0      0 1.51- 2.50      2     0      0      3      1      0      0      0       1    0    1      1      1      3      0     1     14 2.51- 3.50      2      1      2      1      1      1      0      3      5    5    1      2      4      2      5      2    37 3.51- 4.50      2      2      2      3      2      2      1      1      8    5    6      2      1      4      0      3    44 4.51- 5.50     2      1      3      2      3      2      0     1      6    7    7      6      2      2     0     3    47 5.51- 6.50      1      2      1     0      0      0      0     2      5    7    9      6      2      1      1      1    38 6.51- 8.50      2      1      2      2      4      4      3      1      9    6    14      3      4      1      2     0     58 8.51-11.50      3      4      2      3      6      4      1     0       4    16    22      7      3      2      1     0     78 11.51-14.50      1      6      4      1    16      4     0     2      1    2    20      4     0      0      0      0     61 14.51-20.50     0     3     0      2    11      1      3      3      1    0   22      2      1      0     1      1    51
     >20.50        0      0      0      0      0      1      0      1       0     0     0      0      0      0     0     0     2 TOTAL        15    20    16    17    44      19     8    14     40    48  102     33     18     15     10     11   430 PVNGS 2016 ARERR                                                                                                            Page 70


STABILITY CLASS ALL SPEED (MPH)        N    NNE    NE   ENE     E   ESE     SE    SSE     S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL  ___________                                                                                                                  _
STABILITY CLASS     E SPEED (MPH)        N    NNE    NE     ENE       E ESE     SE    SSE       S SSW   SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                         0
____    CALM 0    .76- 1.50      0      1      1      0      1      0      0      0      0      0     1      1      0      1      3     0 9  1.51- 2.50    22     10     5     1      3      0     2      6      3    10    10     14    10     14     22    24 156  2.51- 3.50    68     18     11     12     7     6     6     10     18    27     25     19    21    34     55     61 398  3.51- 4.50    80     21     11     9     1     2      3      5     19     31     24     17     20     17     47     89 396   4.51- 5.50    80     29     14    12     5     2      8     8    24     27     20     13     9     11    26     51 339  5.51- 6.50    43     31     19     5     1      2      0      5    13     29     22     13     7     13     13     22 238  6.51- 8.50    50     24     15    14     7     6     2     7     13     24     34     30     17     11     9     22 285  8.51-11.50    16     14     10     6      7      9     1      0      2    25     24     16     17     18    10    11 186  11.51-14.50      0      1     0      5     6     0      0      0      0    12     26    11     6    13     3     4 87  14.51-20.50      0      0      0      0    20      0      0      0      3    11    13     6      7     14     0     3 77     >20.50       0      0      0      0      1      0      0      0      3      5      2      2     0      0     0     0 13  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
   .76- 1.50      0      0      0      0        0      0    0      0        1    0    0      0    0      0      0      0      1 1.51- 2.50      2     1      1      0       2     1     0     0       2    0    0      1    1      4      2      5    22 2.51- 3.50      7     1      3      2        0      1    0      0       1    0    4      2    2      4     8      3    38 3.51- 4.50      4      4      1     1       2     1     0     0       3    2    4      9    6      2      3      3    45 4.51- 5.50      5      1      4     1        1      2    1     0       2    9  12      6    2      1      2      1     50 5.51- 6.50     6      2      5      2        1      4     0      3        2  14    10      6     3      1     3     1     63 6.51- 8.50      3     5      3      6        7     6    2      6       4  18    36      7    4      2      2      2    113 8.51-11.50     3      2      3    10       14      6     4      4        4  25    62      15     1      4      1      3    161 11.51-14.50      2      0      0      3      21      4    3      1        0    9  33      7     0      1      0      1     85 14.51-20.50     3      2      2      0      18      4     0      0        1    2    9      0     0      0      0      0     41
____     TOTAL       359   149     86     64     59     27    22    41     98   201   201   142   114    146   188   287 2184   TOTAL NUMBER OF OBSERVATIONS: 2184 TOTAL NUMBER OF VALID OBSERVATIONS: 2184 TOTAL NUMBER OF MISSING OBSERVATIONS:     0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
     >20.50        0      0      0     0        0     0    0     0        0    0    0      0     0      0      0      0      0 TOTAL        35     18    22      25      66    29    10     14      20  79  170      53    19     19    21    19    619 STABILITY CLASS    F SPEED (MPH)        N    NNE    NE    ENE        E  ESE      SE    SSE        S SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
MEAN WIND SPEED FOR THIS PERIOD:   5.9 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         
  .76- 1.50      0      0      0      0        0      0     0      1        0    0    0      0     0      0      0      0      1 1.51- 2.50     3      1      1      0        1      0     1      0        0    0    3      1     3      3      2      1     20 2.51- 3.50     5     1       2      3       0     0     0      2        0    2    3      4     2      1      4      5     34 3.51- 4.50      6      5      4      0        0      0     0      0        0    3    3      5     7      8      7      5     53 4.51- 5.50     10      6      3      2        0      0     1      1        3    6   15      4     3      3      3      2    62 5.51- 6.50     1      4      1      1        0      0     1      1        1    3    7      2    2      0      2      3     29 6.51- 8.50     6     2      2      1        0      0    2     0        1    8   21      6     3      1      1      0     54 8.51-11.50      1      3      1      0        0      0     0      0        0    2    9      2     0      2      0     0     20 11.51-14.50      0      1      0      0        1      0     1      0        0    0    0      1     0      0      0      1      5 14.51-20.50     2      0      0      0        0      0     0      0        0    0    0      0    0      0      0      0      2
    >20.50        0      0      0      0        0      0     0      0        0    0    0      0     0     0     1      0      1 TOTAL        34    23    14      7        2      0     6     5       5  24    61      25    20    18    20     17    281 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 9/30/2016
                                                          *** 3RD QRTR ***
STABILITY CLASS     G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE     NE     ENE        E  ESE      SE    SSE        S SSW    SW    WSW     W    WNW     NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0        0      0     0      0        0    0    0      0     0      0      0      0      0 1.51- 2.50     4      0      0      0        0      0     0      0        0    0    0      1     0      0      5      3     13 2.51- 3.50     5     5      1     1        0     1     0      0        0    0    2      0     1      4      5     10     35 3.51- 4.50     24      5      1      1        0      0     0     0        1    0    0      1     2      0      1      8     44 4.51- 5.50    20    12      2      0        0      0     0      0        1    0    1      2     0      0      4     5    47 5.51- 6.50     7      5      2      0        0      0    0     0        1    0    1      1     0      0     0      2    19 6.51- 8.50     11      6      0      0        0      0     0      0        0    1    2      0     0      0      0      2     22 8.51-11.50      4      0      0      0        0      0    0     0        0    0    0      0    0      0     0     0      4 11.51-14.50      1      0      0      1        0      0    0      0        0    0    0      0     0      0     0     0     2 14.51-20.50     0      0      0      0        0      0    0      0        0    0    0      0    0     0      0      0      0
     >20.50        0     0      0      0        0      0    0     0        0    0    0      0    0      0      1      0      1 TOTAL        76    33      6     3       0      1     0     0        3    1    6       5    3     4    16    30    187 STABILITY CLASS ALL SPEED (MPH)        N    NNE    NE     ENE        E  ESE     SE    SSE        S SSW    SW    WSW     W    WNW     NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50     0      0      0      0        0      0    0      1       1    0    0      0    0     0      0      0     2 1.51- 2.50    11      2      2     3       4      1    1     0        3    0    4      4    5     10     9    10    69 2.51- 3.50    19     8      8      7        1     3    0      5        6    7  10      8    9    11    22    20    144 3.51- 4.50    36    16    10      5        4     4    2     1      12  10    13     17    17    14    12    19    192 4.51- 5.50    38    21    14      5        5      5    8      8      26 29    40      19    8      6    11    14    257 5.51- 6.50    16    15    11      5        6      8    5     17       41  39   41      22     9      3      6      9    253 6.51- 8.50     23     19     11      17      19    27    22    31      51  71  118      35    23      8      9      6    490 8.51-11.50    11    11      8    17      26    34      6      9      24  69  147      48    18     13      4      5   450 11.51-14.50      5      8      6      5      44   11      5      5        6  17   75      17    1      1      0      2    208 14.51-20.50      6      5      2      3      34      6    3      6        2    5  37      2    1      0      1      1   114
    >20.50        1      0      0      0        0      1    0      1        0   0   0      0    0      0      2      0      5 TOTAL      166   105    72      67      143  100      52    84      172 247  485    172    91    66    76    86  2184 TOTAL NUMBER OF OBSERVATIONS: 2184 TOTAL NUMBER OF VALID OBSERVATIONS: 2184 TOTAL NUMBER OF MISSING OBSERVATIONS:       0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
MEAN WIND SPEED FOR THIS PERIOD:   7.8 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:       0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A          B        C          D        E        F      G 14.61        8.93     7.01      19.69    28.34    12.87    8.56 PVNGS 2016 ARERR                                                                                                            Page 71


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A         B         C         D        E        F        G 2.84     3.43     5.68     21.93     14.84     13.10    38.19                                
DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE        E  ESE    SE    SSE      S    SSW    SW  WSW      W  WNW    NW    NNW  CALM A         2    3      3      5      10    34    14      34    49      43    60  31    17      6      4      4      0 B         1    4      6      7      10    12      7    12    32      25    48  18      8      3      0      2      0 C         3    4      5      3      11      5      7      5    23      27    38    7    6      1      5      3      0 D        15  20    16    17      44    19      8    14    40      48  102  33    18    15    10    11      0 E        35  18    22    25      66    29    10      14    20      79  170  53    19    19    21    19      0 F        34  23    14      7        2      0      6      5      5    24    61  25    20    18    20    17      0 G         76  33      6      3        0      1      0      0      3      1    6    5    3      4    16    30      0 TOTAL      166  105    72    67      143    100    52      84    172    247  485  172    91    66    76    86      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016
                                                            *** 4TH QRTR ***
STABILITY CLASS    A STABILITY BASED ON: DELTA T        BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE      ENE      E    ESE      SE    SSE      S  SSW  SW  WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 1.51- 2.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 2.51- 3.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 3.51- 4.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 4.51- 5.50      0      0      0        0      1      0      0      0      0    0    0    0      0      0      0      0      1 5.51- 6.50      0      0      0        1      0      0      2      1      1    0    0    0      0      0      0      0      5 6.51- 8.50      0      0      1        0      2      1      6      4      2    0    2    0      0      0      2      0      20 8.51-11.50      0      0      0        1      0      3      0      0      0    1    0    0      1      2      0      1      9 11.51-14.50      0      0      0        0      0      0      0      0      0    0    1    0      1      1      0      0      3 14.51-20.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0
    >20.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 TOTAL        0      0      1        2      3      4      8      5      3    1    3    0      2      3      2      1      38 STABILITY CLASS    B SPEED (MPH)        N    NNE    NE      ENE      E    ESE      SE    SSE      S  SSW  SW  WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 1.51- 2.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 2.51- 3.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 3.51- 4.50      0      0      0        0      0      0      1      0      0    1    0    0      0      0      0      0      2 4.51- 5.50      0      0      0        2      1      1      1      4      5    0    1    0      0      0      1      2      18 5.51- 6.50      0      0      2        2      1     1      3     4      2    2    0    1      0      0      0      0      18 6.51- 8.50      0      0      0        5     5     2      3      6      0    7    2    0      0      0      0      1      31 8.51-11.50      1      0      0        0      5      0      1      0      0     3    3    0      0      0      1      0      14 11.51-14.50      0      0      0        1      3      0      0      1      0    0    1     0      0      0      0      0      6 14.51-20.50      0      0      1        2      0      0      0      0      0    0    0    0      0      0      0      0      3
    >20.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 TOTAL        1      0      3      12    15      4      9     15      7    13   7    1      0      0      2      3      92 STABILITY CLASS    C SPEED (MPH)        N    NNE    NE      ENE      E    ESE      SE    SSE      S  SSW  SW  WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 1.51- 2.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 2.51- 3.50      0      0      0        0      0      0      0      0      0    0    1    0      0      0      0      0      1 3.51- 4.50      0      0      0        0      0      2      3      6      6    4    1    0      1      1      1      0      25 4.51- 5.50      1      2      2        5      2      0      1      8      10    3    0    1      1      1      1      0      38 5.51- 6.50      0      1      0        1      0      1      0      3      1    0    1    0      1      0      1      1      11 6.51- 8.50      0      0      2        3      1      0      1      0      2    2    3    1      0      0      1      1      17 8.51-11.50      0      1      4        0      3      2      0      0      0    3    4    0      0      0      0      2      19 11.51-14.50      0      1      0        0      7      0      0      0      0    2    0    1      0      1      0      1      13 14.51-20.50      0      0      0        0      1      0      0      0      0    0    2    0      0      0      0      0      3
    >20.50      0      0      0        0      0      0      0      0      0    0    0    0      0      0      0      0      0 TOTAL        1      5      8        9    14      5      5    17      19   14  12    3      3      3      4      5    127 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016
                                                            *** 4TH QRTR ***
PVNGS 2016 ARERR                                                                                                            Page 72


DISTRIBUTION OF WIND DIRECTION VS STABILITY N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW   CALM
STABILITY CLASS    D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      1      2      2      1      1      0      1      3      1      0    5      2      0      0      3      2    24 2.51- 3.50    10      2      3      5      2      1      1      4      6      9    7      6    10      8      2      7    83 3.51- 4.50      6      4      7      3      1      2      1      4    13    11    6      1      2      3      5      8    77 4.51- 5.50      1      3      4      3      3      1      4      3      3      4    6      4      3      1      0      4    47 5.51- 6.50      3      1      4      3      0      1      0      0      3      4    4      4      1      1      1      0    30 6.51- 8.50      5      4      1      2      1      3      1      1      2      5    12      4      1      0      3      3    48 8.51-11.50      0      1      6      3      5      1      2      0      0      4    8      3      1      1      1      2    38 11.51-14.50      0      1      0      1    15      3      2      0      0      0    9      3      2      0      0      0    36 14.51-20.50      0      0      1      0    18      0      1      0      1      1    2      1      0      0      0      0    25
    >20.50        0      0      0      0      1      0      0      0      0      0    0      0      0      0      0      0      1 TOTAL        26    18    28    21    47    12    13      15    29    38    59    28    20    14    15    26    409 STABILITY CLASS    E SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE       S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      1      0    0      0      0      0      0      0      1 1.51- 2.50      5      4      0      1      0      1      1      1      2     3    7      4      5    11      4      1    50 2.51- 3.50      3      2      0      1      1      3      0      1      4      3    3      3      3      4      2      6    39 3.51- 4.50      8      6      1      2      1      0      0      1      3      3    5      4      2      4      6      3    49 4.51- 5.50      1      6      0      2      0      0      1      3      2      2    8      7      1      0      3      5    41 5.51- 6.50      3      3      3      2      0      0      0      1      2      2    3      4      3      2      1      0    29 6.51- 8.50      4      3      4      2      2      3      1      1      0      5    9      3      3      0      1      1    42 8.51-11.50      1      2      0      3      6      8      1      1      3      3    2      3      0      1      1      2    37 11.51-14.50      0      1      1      0      6      4      1      0      0      1    1      5      1      1      1      0    23 14.51-20.50      0      0      0      0      6      0      0      0      0      1    6      1      0      3      0      1    18
    >20.50        0      0      0      0      0      0      0      0      0      0    0      1      1      3      0      0      5 TOTAL        25    27      9    13    22    19      5      9    17    23    44    35    19    29    19    19    334 STABILITY CLASS    F SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S   SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      1    0      0      0      0      0      0      1 1.51- 2.50      5      3      6      0      1      1      0      3      1      0    1      7      3      8      7      2    48 2.51- 3.50    11      4      4      0      0      0      2      0      0      2    3      2      5      7      5      4    49 3.51- 4.50      8      1      2      4      1      0      0      0      4      1    7      5      7      5    11      8    64 4.51- 5.50      7      1      3      0      1      0      0      0      2      2    9      6      0      2      5      3    41 5.51- 6.50      5      0      0      0      1      0      0      0      0      2    6      3      2      3      2      6    30 6.51- 8.50      4      1      2      5      0      0      1      0      1      4    10      2      1      2      4      5    42 8.51-11.50      1      2      3      4      0      0      1      1      0      0    2      0      1      2      0      3    20 11.51-14.50      0      0      1      1      1      0      0      0      0      0    0      0      0      0      0      1      4 14.51-20.50      0      0      0      1      4      0      0      0      0      0    0      0      0      0      0      0      5
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 TOTAL        41    12    21    15      9      1      4      4      8    12    38    25    19    29    34    32    304 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016
                                                        *** 4TH QRTR ***
STABILITY CLASS    G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE   SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                         0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      2      0      0      2      4 1.51- 2.50    20    12      3      2      1      1      1      1      2      2    2      4      8    15    16    20    110 2.51- 3.50    56    17      3      4      0      0      0      3      1      1    5      4      6    22    36    53    211 3.51- 4.50    79    37      5      6      2      1      0      1      2      1    3      0    10      7    20    52    226 4.51- 5.50    45    30      4      1      0      0      0      0      0      0    1      0      1      1      3    24    110 5.51- 6.50    23    14      7      2      0      0      0      0      0      1    0      1      0      0      4    10    62 6.51- 8.50    26    19      2      2      0      0      0      0      0      0    0      0      0      0      1    13    63 8.51-11.50      5      8      5      1      0      0      0      0      0      0    0      0      0      0      0      2    21 11.51-14.50      0      0      0      1      0      0      0      0      0      0    0      0      0      0      0      0      1 14.51-20.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 TOTAL      254    137    29    19      3      2      1      5      5      5    11      9    27    45    80    176    808 PVNGS 2016 ARERR                                                                                                            Page 73


A       1      0      0      0      0     3      0     2      2      8    11     11      7      7     5     5      0 B       0      4      3      5     1      2      0      4     6     11     18     11     4      3     1     2      0 C       4     5     13      7      9      4     3     4    18    20     16     7     4      3      0      7      0 D       31     28     37     24     21     9     15     20     47     71     64     37     25     18     15     17     0 E       19     18     6    11    19     4      1      3    17     39     49     38     27     37     23     13      0 F       19    13     6     5     4     0      1      4     3    36     33     26     21     29     44     42     0 G     285     81     21     12     5      5     2      4     5     16     10     12     26     49   100   201     0 TOTAL   359   149     86     64     59     27     22     41     98   201   201   142    114    146    188   287     0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
STABILITY CLASS    ALL SPEED (MPH)        N    NNE      NE      ENE        E    ESE       SE    SSE        S  SSW    SW    WSW    W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50     0      0        0        0        0        0      0      0         1    1    0        0    2    0    0    2      6 1.51- 2.50    31    21      11        4        3        3      3      8        6    5    15      17  16    34    30    25    232 2.51- 3.50    80    25     10        10        3        4      3     8      11    15    19      15  24    41    45    70    383 3.51- 4.50    101    48     15        15        5        5      5    12      28    21    22      10  22    20    43    71    443 4.51- 5.50    55    42     13        13        8        2       7    18      22    11    25      18    6    5    13    38    296 5.51- 6.50    34    19     16        11        2       3      5     9        9    11    14      13    7    6    9    17    185 6.51- 8.50     39     27      12        19        11       9     13    12        7   23    38      10    5    2    12    24    263 8.51-11.50     8    14     18        12        19     14        5      2        3    14    19       6    3    6    3    12    158 11.51-14.50      0      3        2        4       32        7      3     1        0    3   12        9    4    3    1    2      86 14.51-20.50     0     0        2        3        29        0      1      0        1    2    10        2   0    3    0    1      54
     >20.50      0      0        0        0        1        0      0     0        0    0    0        1    1     3     0     0      6 TOTAL      348    199      99        91      113     47      45    70      88    106  174    101    90  123  156  262    2112 TOTAL NUMBER OF OBSERVATIONS: 2112 TOTAL NUMBER OF VALID OBSERVATIONS: 2112 TOTAL NUMBER OF MISSING OBSERVATIONS:          0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
MEAN WIND SPEED FOR THIS PERIOD:      5.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:            0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A              B          C            D          E        F        G 1.80          4.36        6.01        19.37      15.81    14.39    38.26 DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE          E     ESE      SE    SSE      S    SSW    SW  WSW        W WNW    NW  NNW  CALM A          0    0     1       2       3        4        8      5     3        1    3    0        2    3    2    1    0 B          1    0      3      12      15          4       9     15      7      13      7     1        0    0    2    3    0 C          1    5     8        9      14          5        5    17    19        14    12     3       3    3    4    5    0 D        26  18    28      21      47        12      13      15    29        38    59    28      20   14    15    26      0 E        25  27      9     13      22        19        5      9    17        23    44    35      19  29    19    19     0 F        41  12    21      15        9        1        4      4      8      12    38    25      19  29    34    32      0 G        254  137    29      19        3         2        1      5      5        5  11      9      27  45    80  176     0 TOTAL      348  199    99      91      113        47      45      70    88      106    174  101      90  123  156  262     0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016
                                                                  *** 2ND SEMI ***
STABILITY CLASS      A STABILITY BASED ON: DELTA T          BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE     NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW    W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 1.51- 2.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 2.51- 3.50      0      0        0        0        0        0      0      0        0    0     0        0    0     0     0     0      0 3.51- 4.50      0      0        1        0        0        0      0     0        0     0     0        0    0     0     0     0      1 4.51- 5.50      0      0        1        0        1        0      1      1        0     0     0        0    0     0     0     0      4 5.51- 6.50      0     0       0        3        2        4      5      8       15      5    1        2    0    0    0     1      46 6.51- 8.50      1     2        2        2        6     11      15    22      26    18    20      10    5    3    4    1     148 8.51-11.50      0      1        0        1        3      21        1      5      11    16    26      15  12    5    2    3    122 11.51-14.50      0      0        0        0        1        2      0     2        0    3    13        4   2    1    0    0      28 14.51-20.50      0     0        0        1         0        0      0     1        0    2    3       0    0     0     0     0      7
    >20.50      1      0        0        0        0        0      0      0        0     0     0        0    0     0     0     0      1 TOTAL        2      3        4        7        13      38      22    39      52    44    63       31  19    9    6    5    357 STABILITY CLASS     B SPEED (MPH)        N    NNE     NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW    W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50     0     0        0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 1.51- 2.50     0      0        0        0        0        0      0     0        0    0    0        0    0    0    0    0      0 2.51- 3.50      0      0        0        0        0        0      0      0        0    0    0        0    0    0     0     0      0 3.51- 4.50      0      0        0        0        0        0      1      0        0     1     0        0    0     0     0     0      2 4.51- 5.50      1     0       0        2        1        1      3      7      11     2    3        0    1     0     1     3     36 5.51- 6.50     0     2       4        2        2        1      3     7      12     8     7        2    1     1     0     0      52 6.51- 8.50      0      2        1        9        8        7      7     11        8    15   15        7   4    0    0    2      96 8.51-11.50      1      0        2        3        8        6      1     0         4    9   20        9   2    2    1    0      68 11.51-14.50      0      0        1        1        4        1      1      1        4     3     8        1    0     0     0     0      25 14.51-20.50      0      0        1        2        2        0      0      1        0     0     2        0   0    0    0    0      8
    >20.50      0      0        0        0        0        0      0      0        0    0    0        0   0    0    0    0      0 TOTAL        2      4        9      19        25      16      16    27      39    38   55      19   8    3    2    5    287 PVNGS 2016 ARERR                                                                                                                    Page 74


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  4/01/2016 TO 6/30/2016                                                           
STABILITY CLASS    C SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0      0      0      0      0    1      0      0      0      0      0      1 3.51- 4.50      0      0      1      0      0      3      4      6      6      4    1      0      2      1      2      0    30 4.51- 5.50      1      3      3      5      3      1      4      10    18      8    3      2      1      1      3      2    68 5.51- 6.50      1      1      0      1      2      1      1      4      9      4    7      4      2      0      1      2    40 6.51- 8.50      0      1      4      5      2      2      3      1      7    14    17      3      3      1      3      1    67 8.51-11.50      0      2      4      1      3      2      0      0      1      8    15      0      1      0      0      2    39 11.51-14.50      1      2      1      0    11      0      0      0      1      2    3      1      0      1      0      1    24 14.51-20.50      1      0      0      0      4      1      0      1      0      1    3      0      0      0      0      0    11
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 TOTAL        4      9    13    12    25    10    12      22    42    41    50    10      9      4      9      8    280 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  7/01/2016 TO 12/31/2016
                                                         *** 2ND SEMI ***
STABILITY CLASS    D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      0      0    0      0      0      0      0      0      0 1.51- 2.50      3      2      2      4      2      0      1      3      2      0    6      3      1      3      3      3    38 2.51- 3.50    12      3      5      6      3      2      1      7    11    14    8      8    14    10      7      9    120 3.51- 4.50      8      6      9      6      3      4      2      5    21    16    12      3      3      7      5    11    121 4.51- 5.50      3      4      7      5      6      3      4      4      9    11    13    10      5      3      0      7    94 5.51- 6.50      4      3      5      3      0      1      0      2      8    11    13    10      3      2      2      1    68 6.51- 8.50      7      5      3      4      5      7      4      2    11    11    26      7      5      1      5      3    106 8.51-11.50      3      5      8      6    11      5      3      0      4    20    30    10      4      3      2      2    116 11.51-14.50      1      7      4      2    31      7      2      2      1      2    29      7      2      0      0      0    97 14.51-20.50      0      3      1      2    29      1      4      3      2      1    24      3      1      0      1      1    76
    >20.50        0      0      0      0      1      1      0      1      0      0    0      0      0      0      0      0      3 TOTAL        41    38    44    38    91    31    21      29    69    86  161    61    38    29    25    37    839 STABILITY CLASS    E SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      0      2      0    0      0      0      0      0      0      2 1.51- 2.50      7      5      1      1      2      2      1      1      4      3    7      5      6    15      6      6    72 2.51- 3.50    10      3      3      3      1      4      0      1      5      3    7      5      5      8    10      9    77 3.51- 4.50    12    10      2      3      3      1      0      1      6      5    9    13      8      6      9      6    94 4.51- 5.50      6      7      4      3      1      2      2      3      4    11    20    13      3      1      5      6    91 5.51- 6.50      9      5      8      4      1      4      0      4      4    16    13    10      6      3      4      1    92 6.51- 8.50      7      8      7      8      9      9      3      7      4    23    45    10      7      2      3      3    155 8.51-11.50      4      4      3    13    20    14      5      5      7    28    64    18      1      5      2      5    198 11.51-14.50      2      1      1      3    27      8      4      1      0    10    34    12      1      2      1      1    108 14.51-20.50      3      2      2      0    24      4      0      0      1      3    15      1      0      3      0      1    59
    >20.50        0      0      0      0      0      0      0      0      0      0    0      1      1      3      0      0      5 TOTAL        60    45    31    38    88    48    15      23    37  102    214    88    38    48    40    38    953 STABILITY CLASS    F SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      0      0      0      0      0      1      0      1    0      0      0      0      0      0      2 1.51- 2.50      8      4      7      0      2      1      1      3      1      0    4      8      6    11      9      3    68 2.51- 3.50    16      5      6      3      0      0      2      2      0      4    6      6      7      8      9      9    83 3.51- 4.50    14      6      6      4      1      0      0      0      4      4    10    10    14    13    18    13    117 4.51- 5.50    17      7      6      2      1      0      1      1      5      8    24    10      3      5      8      5    103 5.51- 6.50      6      4      1      1      1      0      1      1      1      5    13      5      4      3      4      9    59 6.51- 8.50    10      3      4      6      0      0      3      0      2    12    31      8      4      3      5      5    96 8.51-11.50      2      5      4      4      0      0      1      1      0      2    11      2      1      4      0      3    40 11.51-14.50      0      1      1      1      2      0      1      0      0      0    0      1      0      0      0      2      9 14.51-20.50      2      0      0      1      4      0      0      0      0      0    0      0      0      0      0      0      7
    >20.50        0      0      0      0      0      0      0      0      0      0    0      0      0      0      1      0      1 TOTAL        75    35    35    22    11      1    10      9    13    36    99    50    39    47    54    49    585 PVNGS 2016 ARERR                                                                                                            Page 75


                                                              *** 2ND QRTR ***                                                    
ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016
                                                                  *** 2ND SEMI ***
STABILITY CLASS      G STABILITY BASED ON: DELTA T        BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE      NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50      0      0        0      0        0        0      0      0        0    0    0        0    2    0    0    2      4 1.51- 2.50    24    12        3      2        1        1      1      1        2    2    2        5    8    15    21    23    123 2.51- 3.50    61    22        4      5        0        1      0      3        1    1    7        4    7    26    41    63    246 3.51- 4.50    103    42        6      7        2        1      0      1        3    1    3        1    12    7    21    60    270 4.51- 5.50    65    42        6      1        0        0      0      0        1    0    2        2    1    1    7    29    157 5.51- 6.50    30    19        9      2        0        0      0      0        1    1    1        2    0    0    4    12      81 6.51- 8.50    37    25        2      2        0        0      0      0        0    1    2        0    0    0    1    15      85 8.51-11.50      9      8        5      1        0        0      0      0        0    0    0        0    0    0    0    2      25 11.51-14.50      1      0        0      2        0        0      0      0        0    0    0        0    0    0    0    0      3 14.51-20.50      0      0        0      0        0        0      0      0        0    0    0        0    0    0    0    0      0
    >20.50      0      0        0      0        0        0      0      0        0    0    0        0    0    0    1    0      1 TOTAL      330    170      35      22        3        3      1      5        8    6    17      14    30    49    96  206    995 STABILITY CLASS    ALL SPEED (MPH)        N    NNE      NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50      0      0        0      0        0        0      0      1        2    1    0        0    2    0    0    2      8 1.51- 2.50    42    23      13        7        7        4      4      8        9    5    19      21    21    44    39    35    301 2.51- 3.50    99    33      18      17        4        7      3    13        17    22    29      23    33    52    67    90    527 3.51- 4.50    137    64      25      20        9        9      7    13        40    31    35      27    39    34    55    90    635 4.51- 5.50    93    63      27      18        13        7      15    26        48    40    65      37    14    11    24    52    553 5.51- 6.50    50    34      27      16        8      11      10    26        50    50    55      35    16    9    15    26    438 6.51- 8.50    62    46      23      36        30      36      35    43        58    94  156      45    28    10    21    30    753 8.51-11.50    19    25      26      29        45      48      11    11        27    83  166      54    21    19    7    17    608 11.51-14.50      5    11        8      9        76      18        8      6        6    20    87      26    5    4    1    4    294 14.51-20.50      6      5        4      6        63        6      4      6        3    7    47        4    1    3    1    2    168
    >20.50      1      0        0      0        1        1      0      1        0    0    0        1    1    3    2    0      11 TOTAL      514    304    171      158      256    147        97    154      260  353  659    273    181  189  232  348    4296 TOTAL NUMBER OF OBSERVATIONS: 4296 TOTAL NUMBER OF VALID OBSERVATIONS: 4296 TOTAL NUMBER OF MISSING OBSERVATIONS:          0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
MEAN WIND SPEED FOR THIS PERIOD:      6.7 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:            0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A            B          C            D          E        F        G 8.31        6.68        6.52        19.53      22.18    13.62    23.16 DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE        E      ESE      SE    SSE      S      SSW    SW  WSW        W  WNW    NW  NNW  CALM A          2    3      4      7      13        38      22      39    52        44    63    31      19      9    6    5    0 B          2    4      9    19      25        16      16      27    39        38    55    19        8    3    2    5    0 C          4    9    13      12      25        10      12      22    42        41    50    10        9    4    9    8    0 D        41  38    44      38      91        31      21      29    69        86  161    61      38    29    25    37      0 E        60  45    31      38      88        48      15      23    37      102  214    88      38    48    40    38      0 F        75  35    35      22      11          1      10        9    13        36    99    50      39    47    54    49      0 G        330  170    35      22        3        3        1      5      8        6  17    14      30    49    96  206      0 TOTAL      514  304    171    158      256      147      97    154    260      353  659  273      181  189  232  348      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 12/31/2016
                                                                  *** ANNUAL ***
STABILITY CLASS      A STABILITY BASED ON: DELTA T        BETWEEN 200.0 AND      35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE      NE      ENE        E    ESE        SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                  0
  .76- 1.50      0      0      0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 1.51- 2.50      0      0      0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 2.51- 3.50      0      0      0        0        0        0      0      0        0    0    0        0    0    0    0    0      0 3.51- 4.50      0      0      1        0        0        0      0      0        0    0    0        0    0    0    0    0      1 4.51- 5.50      0      0      1        1        2        1      3      2        3    0    1        0    0    0    0    0      14 5.51- 6.50      0      1      0        3        4        4      6    14        28    13    5        2    0    0    0    1      81 6.51- 8.50      1      2      3        6        9    15        21    32        53    28    39      17    9    6    5    1    247 8.51-11.50      1      2      0        5        11    31        1      9        19    35    51      25    22    9    7    5    233 11.51-14.50      1      1      5        1        2        3      4      2        7    17    35      14    6    4    6    3    111 14.51-20.50      0      0      5        4        2        2      0      2        5    14    6        2    2    4    0    4      52
    >20.50      1      0      1        0        0        0      0      0        0    2    6        1    0    1    1    0      13 TOTAL        4      6      16      20        30    56        35    61      115  109  143      61    39    24    19    14    752 PVNGS 2016 ARERR                                                                                                                    Page 76


STABILITY CLASS   A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE     NE    ENE      E    ESE    SE   SSE      S   SSW    SW    WSW      W    WNW    NW    NNW T OTAL  ___________                                                                                                                  _
STABILITY CLASS   B SPEED (MPH)        N    NNE     NE    ENE      E    ESE    SE     SSE      S SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                         0
____    CALM 0    .76- 1.50      0      0      0      0      0     0      0      0     0     0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0     0      0      0     0     0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0     0      0      0     0     0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0   4.51- 5.50      0      0      0      1      1      1      2      1      3      0      1     0      0      0      0      0 10  5.51- 6.50      0      1     0      0      2      0      1     6    13     7     4     0      0      0      0      0 34  6.51- 8.50      0      0      1     4      3      2      6      8     25     10     18     4      3      3      1      0 88  8.51-11.50      0      1      0      4      8      9     0      4     8     18     21     9     5     0      2     1 90 11.51-14.50      1      1      5     1      1      1      4      0     7    13    16      5      3      3      4      2 67  14.51-20.50      0     0     5      3      2     2     0      1      5      8     3      0     2     1     0     1 33     >20.50        0      0      1      0      0      0      0      0      0      1      6     1      0      1      1      0 11 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
   .76- 1.50      0      0      0      0      0      0       0      0      0     0     0      0      0      0      0      0      0 1.51- 2.50      0      0      0      0      0      0       0      0      0     0     0      0      0      0      0      0      0 2.51- 3.50      0      0      0      0      0      0       0      0      0     0     0      0      0      0      0      0      0 3.51- 4.50      0      0      0      0      0      0       1     0     1    1    1     0      0      0      0      0     4 4.51- 5.50      1      1      1      5      2      2      4    12    23    3    5      1      2      1      2      4    69 5.51- 6.50      1      4      4      4      3      2      5    11    33    18    14      9      3      3      2     0   116 6.51- 8.50     0     4      6    14    11    13      8    16    18    28    29    15    10      2     0     2    176 8.51-11.50      1      1      4      7    11      9      4      2      6    21    32    15      5      3      1      2    124 11.51-14.50     0     1      1      1      5      4      1      2      4    9    17      2     0     2      0      0     49 14.51-20.50      0      0       3     2      3      0      0      1     0    4    6     1     0      0      0      0    20
____     TOTAL        1     3    12    13    17     15    13     20    61     57     69     19    13     8     8     4 333                                                                                                                               
    >20.50        0      0      0      0      0     1       0     0      0    2     0      0      0     1      0      0      4 TOTAL        3     11      19    33    35    31    23      44    85    86  104    43    20    12      5      8    562 STABILITY CLASS    C SPEED (MPH)        N    NNE      NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50     0      0      0      0      0      0      0      0      0    0    0      0     0      0      0      0      0 1.51- 2.50     1     0      0      0      0      0      0      0      0    0    0      0      0      0     0      0      1 2.51- 3.50     0      0      0     0     0     0      0     0      0     0    1      1     0     1     0      0     3 3.51- 4.50      0     0      1     0      0     3      4      6      9    8    3      2      4      1      2      1    44 4.51- 5.50      3      3      6     10      7     2      7     16     35    19     5      3      2      2     4     5    129 5.51- 6.50     3      3       6      3      3      2      2      7    20    23    14    11      5      2     1     4    109 6.51- 8.50     0     5      12    12      9      5      6      2    15    23    22      8      6      3      4      2    134 8.51-11.50      0     2      10      3      6      6      1      2      4    13    17      2      4      0      0      2    72 11.51-14.50      2      2      2      0    14      0      1      0      1    5    10      1      1     1     0      1    41 14.51-20.50      1      0      0     0      4      1      0      1      0    3    8      0      0      1      0      0    19
    >20.50        0      0      0      0     0      0      0      0     0     0     1      0     0     0     0      0     1 TOTAL        10    15      37    28    43    19    21      34    84    94    81    28    22    11    11    15    553 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO 12/31/2016
                                                          ***  ANNUAL ***
STABILITY CLASS    D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE      NE    ENE      E    ESE    SE    SSE      S SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      1      0      1      0      0     0      1      0      0    1     0      0      0      0      0      0      4 1.51- 2.50      4      3      4      5      2     1       7      6      5    6    11      5      6      4      4      5    78 2.51- 3.50    26      8      9    10      9      6    11     18    31    34    27    17    19    18      9    18    270 3.51- 4.50    15    15      20    13     5     9      7     11    42    40    29      9    10      8    11    15    259 4.51- 5.50      9    19      18    10      9      6     13     12    21    28    29    16    10      7      1    10    218 5.51- 6.50      6      6      16      9      0      5      1      4     16   22    20    17      5      4     5      3   139 6.51- 8.50    12    10      12    16      8      7      5     3     17    17    37    15    10      3      6     4   182 8.51-11.50      3      8     14     9    19    13      5      3      6    31    41    20    15      5      4      3    199 11.51-14.50      1     7      5     5     36      7      2      3     3   11    42    11     6     3     0     2    144 14.51-20.50     1      5       2      3    35     3      6     3      6    9    37      6     5     6     3     1   131
     >20.50        0      0      0      0      1      1      0     2      0    4    2     0      0      0      0      0     10 TOTAL        78    81    101    80    124    58    58      65  147  203    275    116    86    58    43    61  1634 STABILITY CLASS    E SPEED (MPH)        N    NNE      NE    ENE      E    ESE    SE    SSE      S  SSW    SW    WSW      W    WNW    NW    NNW TOTAL CALM                                                                                                                          0
  .76- 1.50      0      0      1      1     1      0      0      0      2    0    1     1      0      0      2      0      9 1.51- 2.50    12    10      1      2      5      4      1      4      5    5    9    10      8    19      8      9    112 2.51- 3.50    17      8      4      5      3      5      2     1      5    8    11    13    13    14    23    12    144 3.51- 4.50    15    12      3      5      6      2      0     2    10    11    16    19    11    10    17    11    150 4.51- 5.50    10    11      6      4      2      2      3     3    12   24    28    16      4      3      9      9    146 5.51- 6.50     13    10      14      4      1      4      2      5      8    22    23     15     9      8      7      4    149 6.51- 8.50     11    14      21    12    11    11      6    10    11    39    73    21    21      7      5      7    280 8.51-11.50    10    10      9    19     20    18      8      7    11    44  104    35    15    11      4    13    338 11.51-14.50      6      2      4      7    31     10      7      2      5    27    56     15      2     19    11      5    209 14.51-20.50      4      2      2      0    42      4      0      2      2    11    35      5      5     9     5     4   132
    >20.50        0      0      0      0      2      0      0      1      3    0    2      3      1      3      0      0    15 TOTAL        98    79      65    59    124    60    29      37    74  191    358    153    89    103    91    74  1684 STABILITY CLASS    F PVNGS 2016 ARERR                                                                                                            Page 77


STABILITY CLASS  B                                                  
SPEED (MPH)        N  NNE      NE      ENE        E    ESE      SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      0    0        1      1        0        1      0      1        0    1      0        0    0    0    0    0      5 1.51- 2.50      13    6        7      2        2        2      5      4        3    1      9      13    11  17    14    7    116 2.51- 3.50      25    12        8      10        4        3      5      4        1    7    14      10    17  17    26    22    185 3.51- 4.50      21    10        7      8        2        3      0      0        5  15    20      16    19  20    28    25    199 4.51- 5.50      22    12      12        3        2        1      5      1        6  17    36      23    9  10    14    13    186 5.51- 6.50      10    13        9      4        2        1      4      2        2  17    26      16    11    8    8    19    152 6.51- 8.50      16    11      11      10        1        2      4      2        4  32    61      22    10  10    14    13    223 8.51-11.50      5    6        6      6        0        1      1      1        1  20    31        9    5  16    9    12    129 11.51-14.50      0    1        1      1        2        0      1      0        0    1      0        1    1    0    0    4      13 14.51-20.50      2    0        0      2        5        0      0      0        0    0      1        0    0    0    0    0      10
    >20.50        0    0        0      0        0        0      0      0        0    0      0        0    0    0    1    0      1 TOTAL      114    71      62      47        20      14      25    15        22  111    198    110    83  98  114  115    1219 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD        1/01/2016 TO 12/31/2016
                                                                *** ANNUAL ***
STABILITY CLASS      G STABILITY BASED ON: DELTA T        BETWEEN 200.0 AND      35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:    .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N  NNE      NE      ENE        E    ESE      SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      0    1        0      0        0        0      1      0        0    0      0        0    2    1    2    2      9 1.51- 2.50      39    17        6      3        5        2      2      1        2    4      3      10    17  25    39    45    220 2.51- 3.50    131    34      13      13        5      11      5      7        3    6    13        6    15  54    82  119    517 3.51- 4.50    196    64      14      15        3        6      7      3        4    5      7        9    23  25    56  146    583 4.51- 5.50    160    66      10        5        1        5      7      0        2    1      8        6    4    7    28    77    387 5.51- 6.50      77    43      14        3        1        0      2      2        2    4      2        5    2    6    9    28    200 6.51- 8.50      83    37        5      4        1        0      1      1        1    4      3        2    2    0    2    31    177 8.51-11.50      25    19        6      2        0        0      0      0        0    2      0        0    0    0    1    4      59 11.51-14.50      1    0        0      2        0        1      0      0        0    0      0        0    0    0    0    0      4 14.51-20.50      0    0        0      0        0        0      0      0        0    0      0        0    0    0    0    0      0
    >20.50        0    0        0      0        0        0      0      0        0    0      0        0    0    0    1    0      1 TOTAL      712  281      68      47        16      25      25    14        14  26    36      38    65  118  220  452    2157 STABILITY CLASS     ALL SPEED (MPH)        N  NNE      NE      ENE        E    ESE      SE    SSE        S  SSW    SW    WSW      W  WNW    NW  NNW TOTAL CALM                                                                                                                                0
  .76- 1.50      1    1        3      2        1        1      2      1        2    2      1        1    2    1    4    2      27 1.51- 2.50      69    36      18      12        14        9    15    15        15  16    32      38    42  65    65    66    527 2.51- 3.50    199    62      34      38        21      25      23    30        40  55    66      47    64  104  140  171    1119 3.51- 4.50    247  101      46      41        16      23      19    22        71  80    76      55    67  64  114  198    1240 4.51- 5.50    205  112      54      38        25      19      42    46      102  92    112      65    31  30    58  118    1149 5.51- 6.50    110    80      63      30        14      18      22    45      109  119    104      75    35  31    32    59    946 6.51- 8.50    123    83      70      74        50      53      51    66      119  171    264    100    68  31    36    60    1419 8.51-11.50      45    48      49      51        67      78      20    24        47  166    276    106    66  44    26    41    1154 11.51-14.50      11    14      18      17        90      25      16      9        20  70    160      44    16  29    17    15    571 14.51-20.50      8    7      12      11        91      10      6      9        13  41    93      14    12  20    8    9    364
    >20.50        1    0        1      0        3        2      0      3        3    8    11        4    1    5    3    0      45 TOTAL      1019  544    368      314      392    263      216    270      541  820  1195    549    404  424  503  739    8561 TOTAL NUMBER OF OBSERVATIONS: 8568 TOTAL NUMBER OF VALID OBSERVATIONS: 8561 TOTAL NUMBER OF MISSING OBSERVATIONS:          7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.9 %
MEAN WIND SPEED FOR THIS PERIOD:      6.7 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:            0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A            B          C            D          E        F          G 8.78        6.56        6.46      19.09      19.67    14.24      25.20 DISTRIBUTION OF WIND DIRECTION VS STABILITY N  NNE    NE    ENE        E      ESE      SE    SSE      S      SSW  SW    WSW        W  WNW  NW  NNW  CALM A          4      6  16      20      30        56      35    61    115      109  143    61      39    24   19    14      0 B         3    11    19      33      35        31      23    44    85        86  104    43      20    12    5    8    0 C        10    15    37      28      43        19      21    34    84        94  81    28      22    11  11    15      0 D        78    81  101      80    124        58      58    65    147      203  275    116      86    58  43    61      0 E        98    79    65      59    124        60      29    37    74      191  358    153      89  103  91    74      0 F        114    71    62      47      20        14      25    15    22      111  198    110      83    98  114  115      0 G        712  281    68      47      16        25      25    14    14        26  36    38      65  118  220  452      0 TOTAL    1019  544  368    314      392      263    216    270    541      820 1195    549      404  424  503  739      0 PVNGS 2016 ARERR                                                                                                                  Page 78


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
APPENDIX C DOSE CALCULATIONS PVNGS 2016 ARERR                  Page 79
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0 1  4.51- 5.50      0      0      1      2      1      1      1      4    12      0      2      1      1      0      0      1 27  5.51- 6.50      1      1      0      2      1      1      2      3    17      9      4      5      1      2      2      0 51  6.51- 8.50      0      1      2      2      2      5      1      3      9    10      8      4      4      1      0      0 52  8.51-11.50      0      0      2      3      3      2      3      2      2    10      9      2      2      0      0      0 40  11.51-14.50      0      1      0      0      1      3      0      1      0      4      4      0      0      2      0      0 16  14.51-20.50      0      0      2      0      1      0      0      0      0      3      3      1      0      0      0      0 10    >20.50        0      0      0      0      0      1      0      0      0      1      0      0      0      1      0      0 3  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        1      3      7      9      9    13      7    13    40    37    31    13      8      6      2      1 200 STABILITY CLASS  C                                                  


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
GASEOUS EFFLUENT DOSE CALCULATIONS Doses to the maximum individual and the surrounding population resulting from the release of radioactive material in gaseous effluents from the Palo Verde Nuclear Generating Station were calculated using the GASPAR computer program. The radionuclides considered in the dose calculations were tritium, iodine-131, iodine-132, iodine-133, iodine-135, all noble gases, and particulates having a half-life greater than eight days and for which dose factors are contained in NUREG-0172. Locations selected for individual dose calculations included for each sector, the site boundary, and within five miles, if present, the nearest residence, the nearest garden, and the nearest milk animal. GASPAR implements the radiological dose models of Regulatory Guide 1.109 to determine the radiation exposure to man from four principal atmospheric exposure pathways:
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      1     0      0 1  3.51- 4.50      0      0      0      0      0      0      0      0      2      2      1      0      0      0      0      0 5  4.51- 5.50      1      0      2      2      1      1      2      4    11      7      0      1      0      1      1     0 34  5.51- 6.50      0     0      2      1      0      0      1      1      6    11      2      5      3      1      0      0 33  6.51- 8.50      0      1     4      5      3      1      1      1      4      6      2      3      3      1      1      0 36  8.51-11.50      0      0      2      1      2      3      1      2      1      4      2      2      3      0      0      0 23  11.51-14.50      1      0      1      0      3      0      1      0      0      2      4      0      0      0      0      0 12  14.51-20.50      0      0      0      0      0      0      0      0      0      1      3      0      0      0      0      0 4    >20.50        0      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
plume, ground deposition, inhalation, and ingestion. Doses to the maximum individual and the population were calculated as a function of age group and pathway for significant body organs.
____    TOTAL        2      1    11      9      9      5      6      8     24    33    15    11      9      4      2      0 149 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  4/01/2016 TO  6/30/2016    
Table 43 presents the doses on a quarterly, semiannual and annual basis for the Energy Information Center. An occupancy factor of 1.0 (implying continuous occupancy over the entire year) was considered for the Energy Information Center and the exposure pathways considered to calculate its doses were plume, ground deposition, and inhalation. Dose to the special location for 2016 was 1.65 millirem. This is well within the 25 mrem/yr limit of 40 CFR 190.
Table 44 presents the population dose.
Table 45 summarizes the individual doses and compares the result to PVNGS ODCM Requirement limits. The site boundary and residence locations for which data are presented represent the highest annual doses.
Based on results obtained by placing TLDs on the site boundary in each sector, the net dose for this reporting period, from direct-radiation, (plume and ground deposition) from all three units was indistinguishable from preoperational values of 8 - 14 R/hr (17 - 30 mR/Std Qtr).
There were no liquid effluents associated with the operation of this facility.
PVNGS 2016 ARERR                                                                                Page 80


                                                        *** 2ND QRTR ***
Dose Calculation Models The GASPAR computer code was used to evaluate the radiological consequences of the routine release of gaseous effluents. GASPAR implements the dose calculational methodologies of Regu-latory Guide 1.109, Revision 1.
Source terms for each quarter are combined with station-specific demographic data and each quarters atmospheric diffusion estimates for gaseous dose calculations.
Atmospheric diffusion estimates are generated by the XOQDOQ computer code using onsite meteorological data as input. Additional input to GASPAR includes the following site-specific data:
0 to 5 mile nearest residence, milk animal and garden in each of the 16 compass sectors, based on the 2016 Land Use Census.
0 to 10 mile population from the PVNGS Emergency Plan, Rev 47.
The 10 to 50 mile population distribution from the PVNGS UFSAR, Figure 2.1-12.
The population distribution of metropolitan Phoenix greater than 50 miles from PVNGS, based on the 1980 federal census results, is conservatively included in the 40 to 50 mile sectors (NE=123; ENE=140,097; E=621,130; ESE=8,392).
Absolute humidity of 6.0 g/m3 from the PVNGS UFSAR, Table 2.3-16.
The fraction of the year that vegetables are grown (0.667) from the PVNGS ER-OL, Section 2.1.3.4, Table 2.1-8.
The fraction of daily feed derived from pasture while on pasture (0.35) and length of grazing season for milk animals beyond 5 miles (0.75) from the PVNGS ER-OL, Section 2.1.3.4.3.
The fraction of daily feed derived from pasture while on pasture (0.05) and length of grazing season for meat animals (0.25) from the PVNGS ER-OL, Section 2.1.3.4.4.
There were three (3) sectors containing milk animal (goat or cow) locations within five (5) miles. For calculation purposes these milk animals are assumed to be fed 100% on pasture grass during the year.
Other values used for input to GASPAR are default values from Regulatory Guide 1.109, Rev. 1.
PVNGS 2016 ARERR                                                                            Page 81


STABILITY CLASS  D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET
Table 43:
Doses To Special Locations For 2016 ENERGY INFORMATION CENTER LOCATED ONSITE 0.45 MILE S FROM UNIT 1, 0.29 MILE SSE FROM UNIT 2 AND 0.20 MILE ESE FROM UNIT 3.
(MREM)      T.BODY    GI-TRACT    BONE          LIVER      KIDNEY        THYROID      LUNG          SKIN 1ST QUARTER ADULT    6.71E-01  6.71E-01    1.22E-03      6.71E-01    6.71E-01      6.71E-01  6.71E-01      6.71E-01 TEEN    6.75E-01  6.75E-01    1.22E-03      6.75E-01    6.75E-01      6.75E-01  6.75E-01      6.76E-01 CHILD    5.97E-01  5.97E-01    1.22E-03      5.97E-01    5.97E-01      5.97E-01  5.97E-01      5.98E-01 INFANT    3.44E-01  3.44E-01    1.22E-03      3.44E-01    3.44E-01      3.44E-01  3.44E-01      3.44E-01 2ND QUARTER ADULT    1.95E-01  1.95E-01    9.72E-03      1.95E-01    1.95E-01      1.95E-01  1.97E-01      1.97E-01 TEEN    1.97E-01  1.97E-01    9.72E-03      1.97E-01    1.97E-01      1.97E-01  2.01E-01      1.99E-01 CHILD    1.75E-01  1.75E-01    9.72E-03      1.75E-01    1.75E-01      1.75E-01  1.78E-01      1.77E-01 INFANT    1.05E-01  1.05E-01    9.72E-03      1.05E-01    1.05E-01      1.05E-01  1.07E-01      1.07E-01 1ST SEMI-ANNUAL ADULT    8.66E-01  8.66E-01    1.09E-02      8.66E-01    8.66E-01      8.66E-01  8.68E-01      8.69E-01 TEEN    8.72E-01  8.72E-01    1.09E-02      8.72E-01    8.72E-01      8.72E-01  8.76E-01      8.75E-01 CHILD    7.72E-01  7.72E-01    1.09E-02      7.72E-01    7.72E-01      7.72E-01  7.75E-01      7.75E-01 INFANT    4.49E-01  4.49E-01    1.09E-02      4.49E-01    4.49E-01      4.49E-01  4.50E-01      4.51E-01 3RD QUARTER ADULT    2.30E-01  2.30E-01    3.39E-04      2.30E-01    2.30E-01      2.30E-01  2.30E-01      2.31E-01 TEEN    2.32E-01  2.32E-01    3.39E-04      2.32E-01    2.32E-01      2.32E-01  2.32E-01      2.32E-01 CHILD    2.05E-01  2.05E-01    3.39E-04     2.05E-01    2.05E-01      2.05E-01  2.05E-01      2.05E-01 INFANT    1.18E-01  1.18E-01    3.39E-04      1.18E-01    1.18E-01      1.18E-01  1.18E-01      1.18E-01 4TH QUARTER ADULT    5.56E-01  5.56E-01    2.08E-03      5.56E-01    5.56E-01      5.56E-01  5.56E-01      5.56E-01 TEEN    5.60E-01  5.60E-01    2.08E-03      5.60E-01    5.60E-01      5.60E-01  5.60E-01      5.60E-01 CHILD    4.95E-01  4.95E-01    2.08E-03      4.95E-01    4.95E-01      4.96E-01  4.96E-01      4.95E-01 INFANT    2.86E-01  2.86E-01    2.08E-03      2.86E-01    2.86E-01      2.86E-01  2.86E-01      1.29E-01 2ND SEMI-ANNUAL ADULT    7.86E-01  7.86E-01    2.42E-03      7.86E-01    7.86E-01      7.86E-01  7.86E-01      7.86E-01 TEEN    7.92E-01  7.92E-01    2.42E-03      7.92E-01    7.92E-01      7.92E-01  7.92E-01      7.92E-01 CHILD    7.00E-01  7.00E-01    2.42E-03      7.00E-01    7.00E-01      7.01E-01  7.01E-01      6.99E-01 INFANT    4.04E-01  4.04E-01    2.42E-03      4.04E-01    4.04E-01      4.04E-01  4.04E-01      2.47E-01 ANNUAL ADULT    1.65E+00  1.65E+00    1.34E-02    1.65E+00    1.65E+00      1.65E+00    1.65E+00      1.65E+00 TEEN    1.66E+00  1.66E+00    1.34E-02    1.66E+00    1.66E+00      1.66E+00    1.67E+00      1.67E+00 CHILD    1.47E+00  1.47E+00    1.34E-02    1.47E+00    1.47E+00      1.47E+00    1.48E+00      1.47E+00 INFANT    8.52E-01  8.52E-01    1.34E-02      8.52E-01    8.52E-01      8.52E-01  8.54E-01      6.98E-01 PVNGS 2016 ARERR                                                                                      Page 82


WIND THRESHOLD AT:   .75 MPH  
Table 44:
Integrated Population Dose for 2016 January through March PLUME      1.20E-04  1.20E-04    1.20E-04  1.20E-04  1.20E-04    1.20E-04 1.20E-04 2.23E-04 0.00%    0.00%    90.84%      0.00%      0.00%      0.00%    0.00%    0.00%
GROUND      1.21E-05  1.21E-05    1.21E-05  1.21E-05  1.21E-05    1.21E-05 1.21E-05 1.42E-05 0.00%    0.00%      9.16%    0.00%      0.00%      0.00%    0.00%    0.00%
INHAL    2.15E+00  2.15E+00        < LLD  2.15E+00  2.15E+00    2.15E+00 2.15E+00 2.15E+00 25.83%    25.83%        0.00%    25.83%    25.83%      25.83%  25.83%  25.83%
VEGET      5.33E+00  5.33E+00        < LLD  5.33E+00  5.33E+00    5.33E+00 5.33E+00 5.33E+00 64.04%    64.04%        0.00%    64.04%    64.04%      64.04%  64.04%  64.04%
COW MILK      5.79E-01 5.79E-01      < LLD  5.79E-01  5.79E-01    5.79E-01 5.79E-01 5.79E-01 6.96%    6.96%      0.00%    6.96%      6.96%      6.96%    6.96%    6.96%
MEAT      2.64E-01  2.64E-01      < LLD  2.64E-01  2.64E-01    2.64E-01 2.64E-01 2.64E-01 3.17%    3.17%      0.00%    3.17%      3.17%      3.17%    3.17%    3.17%
  *TOTAL*    8.33E+00  8.33E+00    1.32E-04  8.33E+00  8.33E+00    8.33E+00 8.33E+00 8.33E+00 PER CAPITA DOSE (REM)    4.25E-06  4.25E-06    6.74E-11  4.25E-06  4.25E-06    4.25E-06 4.25E-06 4.25E-06 April through June PLUME      1.87E-04  1.87E-04    1.87E-04  1.87E-04  1.87E-04    1.87E-04 1.87E-04 4.23E-04 0.01%    0.01%        2.48%    0.01%      0.01%      0.01%    0.01%    0.02%
GROUND      7.29E-03  7.29E-03    7.29E-03  7.29E-03  7.29E-03    7.29E-03 7.29E-03 8.57E-03 0.26%    0.26%      96.94%      0.26%      0.26%      0.26%    0.26%    0.31%
INHAL      8.24E-01  8.24E-01    2.14E-05  8.24E-01  8.24E-01    8.24E-01 8.30E-01 8.24E-01 29.90%    29.89%        0.28%    29.90%    29.90%      29.90%  30.05%  29.88%
VEGET      1.65E+00  1.66E+00    2.11E-05  1.65E+00  1.65E+00    1.65E+00 1.65E+00 1.65E+00 60.04%    60.05%        0.28%    60.04%    60.04%      60.04%  59.91%  60.01%
COW      2.08E-01  2.08E-01    5.34E-07  2.08E-01  2.08E-01    2.08E-01 2.08E-01 2.08E-01 7.56%    7.56%        0.01%    7.56%      7.56%      7.56%    7.55%    7.56%
MEAT      6.14E-02  6.14E-02    3.47E-07  6.14E-02  6.14E-02    6.14E-02 6.14E-02 6.14E-02 2.23%    2.23%        0.00%    2.23%      2.23%      2.23%    2.22%    2.23%
  *TOTAL*      2.76E+00  2.76E+00    7.52E-03  2.76E+00   2.75E+00    2.76E+00 2.76E+00 2.76E+00 PER CAPITA DOSE (REM)    1.41E-06 1.41E-06    3.84E-09  1.41E-06  1.40E-06    1.41E-06 1.41E-06 1.41E-06 PVNGS 2016 ARERR                                                                          Page 83


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)         N    NNE    NE    ENE     E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL  ___________                                                                                                                  _
Table 44: (continued) Integrated Population Dose for 2016 January through June PLUME     3.07E-04 3.07E-04 3.07E-04 3.07E-04  3.07E-04  3.07E-04 3.07E-04 6.45E-04 0.00%    0.00%    4.01%    0.00%     0.00%     0.00%    0.00%    0.01%
____    CALM 0    .76- 1.50      1      0     0     0      0      0     1      0     0      1      0      0      0      0      0      0 3   1.51- 2.50      0     0      0     1     0     1      4     0     1      1      0     0      3      1      0      0 12  2.51- 3.50      2     1      3      1      3      1      5      4      4      5      6      1      2     2     0      4 44   3.51- 4.50      2      4      4      2      2      4      3      3      8      6     6     2      2      0     0      1 49   4.51- 5.50      0      4      2      0      2      2     3     3     3     10      7      2      3     1      0      0 42   5.51- 6.50      0      0      3     3     0     3      1      0      5     2      2     2     2     1     1     1 26   6.51- 8.50      0      1     4      6      2      0      1     1      4      3     5      4     2      1     0      0 34  8.51-11.50      0      3      2     2     2     5      2     3      2     7      5      4      7      2     0     0 46  11.51-14.50     0      0     1      2      1      0      0      1     2      5      6      1     2      3      0      1 25  14.51-20.50      1     2      1     1     0     2     2     0      2     5    11      2     0      0     2     0 31     >20.50        0     0      0      0      0      0      0      1      0      1     2     0      0      0      0      0 4  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
GROUND     7.30E-03 7.30E-03 7.30E-03  7.30E-03  7.30E-03   7.30E-03 7.30E-03 8.59E-03 0.07%    0.07%  95.42%     0.07%     0.07%     0.07%    0.07%    0.08%
____     TOTAL        6     15    20    18    12    18    22    16    31    46    50    18    23    11     3      7 316                                                          STABILITY CLASS   E                                                   
INHAL     2.97E+00 2.98E+00 2.14E-05  2.97E+00  2.97E+00  2.98E+00  2.98E+00 2.97E+00 26.84%  26.84%    0.28%    26.84%    26.84%    26.84%    26.88%  26.84%
VEGET     6.99E+00 6.99E+00 2.11E-05  6.99E+00   6.99E+00  6.99E+00  6.99E+00 6.99E+00 63.04%  63.05%    0.28%    63.04%    63.04%    63.04%    63.01%   63.03%
COW      7.88E-01 7.88E-01 5.34E-07  7.88E-01  7.88E-01  7.88E-01 7.88E-01 7.88E-01 7.11%    7.10%    0.01%    7.11%     7.11%     7.11%    7.10%    7.10%
MEAT      3.26E-01 3.26E-01 3.47E-07  3.26E-01   3.26E-01  3.26E-01 3.26E-01 3.26E-01 2.94%    2.94%    0.00%    2.94%     2.94%     2.94%    2.94%    2.94%
  *TOTAL*    1.11E+01 1.11E+01 7.65E-03  1.11E+01  1.11E+01  1.11E+01  1.11E+01 1.11E+01 PER CAPITA DOSE (REM)    5.67E-06 5.67E-06 3.91E-09  5.67E-06  5.67E-06  5.67E-06 5.67E-06 5.67E-06 July through September PLUME     6.45E-05 6.45E-05 6.45E-05  6.45E-05  6.45E-05  6.45E-05 6.45E-05 1.19E-04 0.00%    0.00%  99.59%     0.00%     0.00%     0.00%    0.00%    0.00%
GROUND     2.66E-07 2.66E-07 2.66E-07  2.66E-07  2.66E-07  2.66E-07 2.66E-07 3.11E-07 0.00%    0.00%    0.41%    0.00%     0.00%     0.00%    0.00%    0.00%
INHAL     8.81E-01 8.81E-01    < LLD  8.81E-01  8.81E-01  8.81E-01 8.81E-01 8.81E-01 29.86%  29.86%    0.00%    29.86%    29.86%    29.86%    29.86%  29.86%
VEGET     1.78E+00 1.78E+00    < LLD  1.78E+00  1.78E+00  1.78E+00  1.78E+00 1.78E+00 60.44%  60.44%    0.00%    60.44%    60.44%    60.44%    60.44%  60.44%
COW      2.14E-01 2.14E-01    < LLD  2.14E-01  2.14E-01  2.14E-01 2.14E-01 2.14E-01 7.27%    7.27%    0.00%    7.27%     7.27%     7.27%    7.27%    7.27%
MEAT      7.19E-02 7.19E-02    < LLD  7.19E-02  7.19E-02  7.19E-02 7.19E-02 7.19E-02 2.44%    2.44%    0.00%     2.44%     2.44%     2.44%    2.44%    2.44%
  *TOTAL*     2.95E+00 2.95E+00 6.47E-05  2.95E+00  2.95E+00  2.95E+00  2.95E+00 2.95E+00 PER CAPITA DOSE (REM)    1.51E-06 1.51E-06 3.30E-11 1.51E-06  1.51E-06   1.51E-06 1.51E-06 1.51E-06 PVNGS 2016 ARERR                                                                    Page 84


SPEED (MPH)         N    NNE    NE    ENE     E    ESE     SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
Table 44: (continued) Integrated Population Dose for 2016 October through December PLUME     1.11E-04 1.11E-04  1.11E-04     1.11E-04  1.11E-04  1.11E-04 1.11E-04 2.49E-04 0.00%    0.00%    31.22%        0.00%     0.00%     0.00%    0.00%    0.00%
____    CALM 0    .76- 1.50      0     0     1      1      0      0      0     0     0      0     0     0      0      0     0     0 2  1.51- 2.50      0     1      0     1     2      2     0      1     1      0      1      0     2     2     0      2 15   2.51- 3.50      4      3     0      1     2     1      2     0      0      0      0      1      3     1     7      2 27   3.51- 4.50      0     1     1     1     3      1     0      1     2      1     1     0     0     2      3      1 18  4.51- 5.50      1      1      1      0      0      0     1      0     1      4      4      1      0      1      2     0 17   5.51- 6.50      2      3      4     0     0     0     2      1      3     4      6      5      3     2      1      1 37   6.51- 8.50      3     3     13      3     2     1      3     2     4     9     21     5      6      2      0      3 80   8.51-11.50      4      4      5      3      0      1     2      2      4     12    33    13      8      2     1     7 101  11.51-14.50      4      0      3      0      2      2     3      1     5    14    17      1     0      4     9      4 69  14.51-20.50      1     0      0      0      5      0      0      2      0      6    12      1     2      2      5      3 39    >20.50        0      0      0      0      1     0      0      1     0      0      0      0      0      0      0      0 2 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
GROUND     2.35E-04 2.35E-04  2.35E-04    2.35E-04  2.35E-04  2.35E-04 2.35E-04 2.77E-04 0.00%    0.00%    66.34%        0.00%     0.00%     0.00%    0.00%    0.00%
____    TOTAL        19    16    28    10    17      8    13    11    20    50    95    27    24    18    28    23 407                                                                                                                               
INHAL    2.41E+00  2.41E+00   6.97E-06    2.41E+00  2.41E+00    2.42E+00 2.41E+00 2.41E+00 27.37%    27.37%     1.97%     27.37%    27.37%     27.37%  27.37%  27.37%
VEGET    5.48E+00  5.48E+00  1.50E-06    5.48E+00  5.48E+00    5.48E+00 5.48E+00 5.48E+00 62.11%    62.11%     0.42%     62.11%    62.11%     62.10%  62.10%  62.11%
COW MILK    6.71E-01 6.71E-01  1.59E-07    6.71E-01  6.71E-01  6.71E-01 6.71E-01 6.71E-01 7.61%    7.61%     0.04%        7.61%     7.61%     7.61%    7.61%    7.61%
MEAT      2.57E-01 2.57E-01  2.06E-09    2.57E-01  2.57E-01   2.57E-01 2.57E-01 2.57E-01 2.92%    2.92%     0.00%        2.92%     2.92%     2.92%    2.92%    2.92%
  *TOTAL*    8.82E+00  8.82E+00  3.54E-04    8.82E+00  8.82E+00    8.82E+00 8.82E+00 8.82E+00 PER CAPITA DOSE (REM)    4.50E-06 4.50E-06  1.81E-10    4.50E-06  4.50E-06   4.50E-06 4.50E-06 4.50E-06 July through December PLUME     1.75E-04 1.75E-04  1.75E-04    1.75E-04  1.75E-04  1.75E-04 1.75E-04 3.68E-04 0.00%    0.00%    41.78%        0.00%     0.00%     0.00%    0.00%    0.00%
GROUND     2.35E-04 2.35E-04  2.35E-04    2.35E-04  2.35E-04   2.35E-04 2.35E-04 2.77E-04 0.00%    0.00%    56.16%        0.00%     0.00%     0.00%    0.00%    0.00%
INHAL    3.30E+00  3.30E+00   6.97E-06    3.30E+00  3.30E+00    3.30E+00 3.30E+00 3.30E+00 27.99%    27.99%     1.66%     27.99%    27.99%     27.99%  27.99%  27.99%
VEGET    7.26E+00  7.26E+00  1.50E-06    7.26E+00  7.26E+00    7.26E+00 7.26E+00 7.26E+00 61.69%    61.69%     0.36%     61.69%     61.69%     61.69%  61.69%   61.69%
COW      8.85E-01 8.85E-01  1.59E-07     8.85E-01  8.85E-01  8.86E-01 8.85E-01 8.85E-01 7.52%    7.52%     0.04%        7.52%     7.52%     7.52%    7.52%    7.52%
MEAT      3.29E-01 3.29E-01  2.06E-09    3.29E-01  3.29E-01  3.29E-01 3.29E-01 3.29E-01 2.80%    2.80%     0.00%        2.80%     2.80%     2.80%    2.80%    2.80%
  *TOTAL*    1.18E+01  1.18E+01  4.19E-04    1.18E+01  1.18E+01    1.18E+01 1.18E+01 1.18E+01 PER CAPITA DOSE (REM)    6.02E-06 6.02E-06  2.14E-10    6.02E-06  6.02E-06  6.02E-06 6.02E-06 6.02E-06 PVNGS 2016 ARERR                                                                        Page 85


STABILITY CLASS   F                                                   
Table 44: (continued)
Integrated Population Dose for 2016 January through December PLUME    4.82E-04 4.82E-04    4.82E-04    4.82E-04   4.82E-04 4.82E-04 4.82E-04 1.01E-03 0.00%    0.00%      5.97%        0.00%      0.00%    0.00%    0.00%    0.00%
GROUND    7.54E-03 7.54E-03    7.54E-03    7.54E-03  7.54E-03 7.54E-03 7.54E-03 8.86E-03 0.03%    0.03%    93.39%        0.03%      0.03%    0.03%    0.03%    0.04%
6.27E+0  6.27E+0                            6.27E+0  6.27E+0          6.27E+0 INHAL 0        0  2.84E-05    6.27E+00          0        0 6.28E+00        0 27.43%  27.43%      0.35%      27.43%    27.43%  27.44%  27.45%  27.43%
1.43E+0  1.43E+0                            1.43E+0  1.43E+0          1.43E+0 VEGET            1        1  2.26E-05    1.43E+01          1        1 1.43E+01        1 62.35%  62.35%      0.28%      62.35%    62.35%  62.34%  62.33%  62.34%
1.67E+0  1.67E+0                            1.67E+0  1.67E+0          1.67E+0 COW 0        0  6.93E-07    1.67E+00          0        0 1.67E+00        0 7.32%    7.32%      0.01%        7.32%      7.32%    7.32%    7.32%    7.32%
MEAT      6.55E-01 6.55E-01    3.49E-07    6.55E-01  6.55E-01 6.55E-01 6.55E-01 6.55E-01 2.87%    2.87%      0.00%        2.87%      2.87%    2.87%    2.86%    2.87%
2.29E+0  2.29E+0                            2.29E+0  2.29E+0          2.29E+0
  *TOTAL*
1        1  8.07E-03    2.29E+01          1        1 2.29E+01        1 PER CAPITA DOSE (REM)  1.17E-05 1.17E-05    4.12E-09    1.17E-05  1.17E-05 1.17E-05 1.17E-05 1.17E-05 PVNGS 2016 ARERR                                                                      Page 86


SPEED (MPH)        N   NNE     NE   ENE     E   ESE     SE    SSE     S   SSW    SW   WSW     W   WNW    NW   NNW T OTAL  ___________                                                                                                                  _
Table 45:
____     CALM 0   .76- 1.50     0      0     1     1     0      1      0     0      0      0      0      0      0      0      0      0 3  1.51- 2.50      1     0      0      2      0     1     4     0     1      0     2     2      3      1     2     1 20  2.51- 3.50      5      6      1     4     2     3      3      1     1     1     3     2     5      5      4      6 52   3.51- 4.50      3     2     0      4      1      3     0      0      0      7      5      3     2     5      0      2 37  4.51- 5.50      1      5      5      1      1      1      3     0      0      4     10     9      3     4     1     4 52  5.51- 6.50      3      5      6      3      1     1     3      1      1      6     9     8      3     2      0      5 57  6.51- 8.50      4     5      6      2      0     2     1      0      2     14    20      4     4      2      4      1 71   8.51-11.50      3     0      2     2     0      1     0      0     1     7    16      6      3      3      5      5 54  11.51-14.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  14.51-20.50      0      0      0      1     0      0      0      0      0      0      1     0      0      0      0      0 2     >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Summary of Individual Doses for 2016 Unit   Quarter 1     Quarter 2  Quarter 3      Quarter 4        Year total Gamma Air Dose                    mrad   5.07E-04     3.29E-04    1.23E-04        3.72E-04        1.17E-03 ODCM Req. 4.1 Limit                mrad  5.00E+00      5.00E+00   5.00E+00        5.00E+00          1.00E+01
____    TOTAL        20    23    21    20      5    13    14      2     6    39    66    34    23    22    16    24 348 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
% ODCM Limit                          %     1.01E-02     6.58E-03   2.46E-03        7.44E-03        1.17E-02 Beta Air Dose                      mrad   1.82E-04     1.41E-04   4.46E-05        1.49E-04        4.53E-04 ODCM Req. 4.1 Limit                mrad  1.00E+01      1.00E+01   1.00E+01        1.00E+01          2.00E+01
  % ODCM Limit                          %     1.82E-03      1.41E-03   4.46E-04        1.49E-03        2.27E-03 Maximum Individual Total Body                        mrem    3.37E-04     2.18E-04    8.14E-05        2.47E-04        7.78E-04 Skin                              mrem    5.41E-04     3.57E-04    1.31E-04        3.99E-04        1.26E-03 Site Boundary Location Unit 1                             miles  1.70 SSE     0.78 NW    1.40 SSW          1.70 SSE        1.70 SSE Unit 2                             miles  1.88 SSE     0.74 NW    1.14 SSW          1.88 SSE        1.88 SSE Unit 3                            miles  1.73 SSE     0.65 NW    1.00 SSW          1.73 SSE        1.73 SSE Age     Infant        Infant     Infant          Teen            Teen Maximum Organ Dose                Organ (excluding skin)                              Bone        Bone        Bone          Thyroid (2)        Lung mrem    1.85E-01      1.01E-01    7.94E-02        1.90E-01        4.86E-01 ODCM Req. 4.2 Limit                mrem  7.50E+00      7.50E+00    7.50E+00        7.50E+00        1.50E+01
% ODCM Limit (1)                      %    2.47E+00      1.35E+00    1.06E+00        2.53E+00        3.24E+00 Location Unit 1                            miles  2.84 NNE      2.84 NNE   2.84 NNE          2.74 S          2.74 S Unit 2                            miles  3.05 NNE      3.05 NNE  3.05 NNE          2.56 S          2.56 S Unit 3                            miles  3.28 NNE      3.28 NNE  3.28 NNE          2.35 S          2.35 S Maximum Organ Dose                  Age      Teen        Infant      Teen            Teen              Teen excluding C-14 (3)                  Organ  Thyroid (2)     Thyroid  Thyroid (2)     Thyroid (2)          Lung (excluding skin)                    mrem    1.74E-01     4.88E-02    7.41E-02        1.90E-01        4.86E-01 ODCM Req. 4.2 Limit                      7.50E+00      7.50E+00    7.50E+00        7.50E+00          1.50E+01
% ODCM Limit (1)                          2.32E+00      6.51E-01    9.88E-01        2.53E+00          3.24E+00 Organ dose from tritium only for Unit 2 location            mrem above                                      1.74E-01     4.72E-02    7.41E-02        1.90E-01        4.84E-01 Fraction of organ dose from tritium only for Unit 2 location     %     100.00%      96.72%    100.00%          100.00%          99.59%
above(2,3)
X/Q for Unit 2 location above     sec/m3   8.75E-07      4.73E-07    3.76E-07        7.96E-06        5.16E-06 D/Q for Unit 2 location above        m-2   1.31E-09     1.82E-09    1.61E-09        2.58E-09        1.86E-09 Note 1: ODCM Requirement 5.1 has higher limits than ODCM Requirement 4.2, therefore the percent of limits are more conservative based on ODCM Requirement 4.2 than on ODCM Requirement 5.1.
Note 2: All organs except bone Note 3 Refer to discussion in section 10.4 PVNGS 2016 ARERR                                                                                              Page 87


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  4/01/2016 TO  6/30/2016   
APPENDIX D NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING PVNGS 2016 ARERR                                                Page 88


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AERIALPHOTO: HELICOPTER PHOTOS, F EXPLANATION PVNGS Well Locations and Aquifer Monitored A StiallowAquiferWell 85-Acre WSR Piezometer FIGURE 1 A Palo Verde Clay Aquifer Well                                                          SITE MAP Brown AND,1                                    A RegionalAquiferWell PVNGS Boundary                                                    PALO VERDE NUCLEAR GENERATING STATION Caldwell                                                                                                                      ARIZONA PUBLIC SERVICES PVNGS2016ARERR                                                                                                                                            Page 89


STABILITY CLASS   G STABILITY BASED ON: DELTA T     BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:   .75 MPH  
Repo  Det Locati              Parameter  Report   rt  ect  Sample Field Sample ID  on ID Sample Date     Name    Result Units ed  Purpose PV-APP-10-0216    APP-10  02/04/2016 Tritium    <  303  pCi/L N  REG PV-APP-10-0216    APP-10  02/04/2016 Cesium-137  <  1.0  pCi/L N  REG PV-APP-10-0216    APP-10  02/04/2016 Cobalt-60  <  2.0  pCi/L N  REG PV-APP-10-0216    APP-10  02/04/2016 Cesium-134  <  2.1  pCi/L N  REG PV-APP-10-0516    APP-10  05/26/2016 Tritium    <  287  pCi/L N  REG PV-APP-10-0516    APP-10  05/26/2016 Cesium-137  <  2.1  pCi/L N  REG PV-APP-10-0516    APP-10  05/26/2016 Cobalt-60  <  1.4  pCi/L N  REG PV-APP-10-0516    APP-10  05/26/2016 Cesium-134  <  1.7  pCi/L N  REG PV-APP-10-0916    APP-10  09/21/2016 Tritium    <  288  pCi/L N  REG PV-APP-10-0916    APP-10  09/21/2016 Cesium-137  <  1.5  pCi/L N  REG PV-APP-10-0916    APP-10  09/21/2016 Cobalt-60  <  0.5  pCi/L N  REG PV-APP-10-0916    APP-10  09/21/2016 Cesium-134  <  1.3  pCi/L N  REG PV-APP-10-1116    APP-10  11/16/2016 Tritium    <  308  pCi/L N  REG PV-APP-10-1116    APP-10  11/16/2016 Cesium-137  <  1.5  pCi/L N  REG PV-APP-10-1116    APP-10  11/16/2016 Cobalt-60  <  0.7  pCi/L N  REG PV-APP-10-1116    APP-10  11/16/2016 Cesium-134  <  1.0  pCi/L N  REG PV-APP-12-0216    APP-12  02/04/2016 Tritium    <  303  pCi/L N  REG PV-APP-12-0216    APP-12  02/04/2016 Cesium-137  <  1.0  pCi/L N  REG PV-APP-12-0216    APP-12  02/04/2016 Cobalt-60  <  1.4  pCi/L N  REG PV-APP-12-0216    APP-12  02/04/2016 Cesium-134  <  1.6  pCi/L N  REG PV-APP-12-0516    APP-12  05/26/2016 Tritium    <  287  pCi/L N  REG PV-APP-12-0516    APP-12  05/26/2016 Cesium-137  <  1.0  pCi/L N  REG PV-APP-12-0516    APP-12  05/26/2016 Cobalt-60  <  1.4  pCi/L N  REG PV-APP-12-0516    APP-12  05/26/2016 Cesium-134  <  1.5  pCi/L N  REG PV-APP-12-0916    APP-12  09/21/2016 Tritium    <  288  pCi/L N  REG PV-APP-12-0916    APP-12  09/21/2016 Cesium-137  <  0.8  pCi/L N  REG PV-APP-12-0916    APP-12  09/21/2016 Cobalt-60  <  0.5  pCi/L N  REG PV-APP-12-0916    APP-12  09/21/2016 Cesium-134  <  1.1 pCi/L N  REG PV-APP-12-1116    APP-12 11/08/2016 Tritium    <  289 pCi/L N PV-APP-12-1116    APP-12  11/08/2016 Cesium-137  <  1.0  pCi/L N PV-APP-12-1116    APP-12  11/08/2016 Cobalt-60  <  1.2  pCi/L N PV-APP-12-1116    APP-12  11/08/2016 Cesium-134  <  10.0  pCi/L N PV-APP-15-0216    APP-15  02/01/2016 Tritium    <  242  pCi/L N  REG PV-APP-15-0216    APP-15  02/01/2016 Cesium-137  <  1.0  pCi/L N  REG PV-APP-15-0216    APP-15  02/01/2016 Cobalt-60  <   1.4 pCi/L N  REG PV-APP-15-0216    APP-15  02/01/2016 Cesium-134  <  1.4  pCi/L N  REG PV-APP-15-1016    APP-15  10/04/2016 Tritium    <  288.0 pCi/L N PV-APP-15-1016    APP-15  10/04/2016 Cesium-137  <  1.4  pCi/L N PV-APP-15-1016    APP-15  10/04/2016 Cobalt-60  <  1.1  pCi/L N PV-APP-15-1016    APP-15  10/04/2016 Cesium-134  <  1.0  pCi/L N PV-APP-18-0316    APP-18  03/16/2016 Tritium    <  287  pCi/L N  REG PVNGS 2016 ARERR                                                          Page 90


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET
PV-APP-18-0316  APP-18 03/16/2016 Cesium-137 < 3.4 pCi/L N REG PV-APP-18-0316  APP-18 03/16/2016 Cobalt-60  < 1.3 pCi/L N REG PV-APP-18-0316  APP-18 03/16/2016 Cesium-134 < 2.8 pCi/L N REG PV-APP-18-1116  APP-18 11/02/2016 Tritium    < 285 pCi/L N REG PV-APP-18-1116  APP-18 11/02/2016 Cesium-137 < 0.9 pCi/L N REG PV-APP-18-1116  APP-18 11/02/2016 Cobalt-60  < 0.3 pCi/L N REG PV-APP-18-1116  APP-18 11/02/2016 Cesium-134 < 1.0 pCi/L N REG PV-APP-19-0216  APP-19 02/03/2016 Tritium    < 303 pCi/L N REG PV-APP-19-0216  APP-19 02/03/2016 Cesium-137 < 1.1 pCi/L N REG PV-APP-19-0216  APP-19 02/03/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-19-0216  APP-19 02/03/2016 Cesium-134 < 2.1 pCi/L N REG PV-APP-19-1116  APP-19 11/16/2016 Tritium    < 308 pCi/L N REG PV-APP-19-1116  APP-19 11/16/2016 Cesium-137 < 0.5 pCi/L N REG PV-APP-19-1116  APP-19 11/16/2016 Cobalt-60  < 0.8 pCi/L N REG PV-APP-19-1116  APP-19 11/16/2016 Cesium-134 < 1.0 pCi/L N REG PV-APP-20-0216  APP-20 02/10/2016 Tritium    < 303 pCi/L N REG PV-APP-20-0216  APP-20 02/10/2016 Cesium-137 < 1.4 pCi/L N REG PV-APP-20-0216  APP-20 02/10/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-20-0216  APP-20 02/10/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-20-1116  APP-20 11/02/2016 Tritium    < 285 pCi/L N REG PV-APP-20-1116  APP-20 11/02/2016 Cesium-137 < 1.1 pCi/L N REG PV-APP-20-1116  APP-20 11/02/2016 Cobalt-60  < 1.0 pCi/L N REG PV-APP-20-1116  APP-20 11/02/2016 Cesium-134 < 0.8 pCi/L N REG PV-APP-21-0216  APP-21 02/10/2016 Tritium    < 303 pCi/L N REG PV-APP-21-0216  APP-21 02/10/2016 Cesium-137 < 1.2 pCi/L N REG PV-APP-21-0216  APP-21 02/10/2016 Cobalt-60  < 1.5 pCi/L N REG PV-APP-21-0216  APP-21 02/10/2016 Cesium-134 < 1.2 pCi/L N REG PV-APP-21-1116  APP-21 11/02/2016 Tritium    < 285 pCi/L N REG PV-APP-21-1116  APP-21 11/02/2016 Cesium-137 < 0.9 pCi/L N REG PV-APP-21-1116  APP-21 11/02/2016 Cobalt-60  < 1.0 pCi/L N REG PV-APP-21-1116  APP-21 11/02/2016 Cesium-134 < 0.9 pCi/L N REG PV-APP-22-0216  APP-22 02/22/2016 Tritium    < 299 pCi/L N REG PV-APP-22-0216  APP-22 02/22/2016 Cesium-137 < 1.2 pCi/L N REG PV-APP-22-0216  APP-22 02/22/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-22-0216  APP-22 02/22/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-22-1016  APP-22 10/04/2016 Tritium    < 288 pCi/L N PV-APP-22-1016  APP-22 10/04/2016 Cesium-137 < 1.4 pCi/L N PV-APP-22-1016  APP-22 10/04/2016 Cobalt-60  < 0.8 pCi/L N PV-APP-22-1016  APP-22 10/04/2016 Cesium-134 < 1.0 pCi/L N PV-APP-23-0216  APP-23 02/10/2016 Tritium    < 303 pCi/L N REG PV-APP-23-0216  APP-23 02/10/2016 Cesium-137 < 1.3 pCi/L N REG PV-APP-23-0216  APP-23 02/10/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-23-0216  APP-23 02/10/2016 Cesium-134 < 1.8 pCi/L N REG PV-APP-23-1016  APP-23 10/12/2016 Tritium    < 288 pCi/L N REG PVNGS 2016 ARERR                                                Page 91


SPEED (MPH)        N   NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
PV-APP-23-1016  APP-23 10/12/2016 Cesium-137 < 0.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Cobalt-60 < 0.8 pCi/L N REG PV-APP-23-1016  APP-23 10/12/2016 Cesium-134 < 0.7 pCi/L N REG PV-APP-3-0216   APP-3 02/11/2016 Tritium    < 303 pCi/L N REG PV-APP-3-0216   APP-3 02/11/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-3-0216  APP-3 02/11/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-3-0216  APP-3 02/11/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-4R-0216  APP-4R 02/11/2016 Tritium    < 303 pCi/L N REG PV-APP-4R-0216  APP-4R 02/11/2016 Cesium-137 < 1.1 pCi/L N REG PV-APP-4R-0216  APP-4R 02/11/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-4R-0216  APP-4R 02/11/2016 Cesium-134 < 2.7 pCi/L N REG PV-APP-4R-1116  APP-4R 11/01/2016 Tritium    < 285 pCi/L N PV-APP-4R-1116  APP-4R 11/01/2016 Cesium-137 < 1.7 pCi/L N PV-APP-4R-1116  APP-4R 11/01/2016 Cobalt-60  < 0.3 pCi/L N PV-APP-4R-1116  APP-4R 11/01/2016 Cesium-134 < 1.4 pCi/L N PV-APP-5-0216  APP-5  02/23/2016 Tritium    < 299 pCi/L N REG PV-APP-5-0216   APP-5 02/23/2016 Cesium-137 < 1.8 pCi/L N REG PV-APP-5-0216  APP-5  02/23/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-5-0216  APP-5 02/23/2016 Cesium-134 < 2.9 pCi/L N REG PV-APP-7-0216  APP-7  02/09/2016 Tritium    < 303 pCi/L N REG PV-APP-7-0216  APP-7  02/09/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-7-0216  APP-7  02/09/2016 Cobalt-60  < 1.5 pCi/L N REG PV-APP-7-0216  APP-7  02/09/2016 Cesium-134 < 1.9 pCi/L N REG PV-APP-9-0216  APP-9  02/04/2016 Tritium    < 303 pCi/L N REG PV-APP-9-0216  APP-9  02/04/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-9-0216   APP-9  02/04/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-9-0216  APP-9  02/04/2016 Cesium-134 < 2.8 pCi/L N REG PV-APP-9-0516  APP-9  05/26/2016 Tritium    < 287 pCi/L N REG PV-APP-9-0516  APP-9  05/26/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-9-0516  APP-9  05/26/2016 Cobalt-60  < 1.4 pCi/L N REG PV-APP-9-0516   APP-9  05/26/2016 Cesium-134 < 2.4 pCi/L N REG PV-APP-9-0916  APP-9  09/21/2016 Tritium    < 288 pCi/L N REG PV-APP-9-0916  APP-9  09/21/2016 Cesium-137 < 1.7 pCi/L N REG PV-APP-9-0916  APP-9  09/21/2016 Cobalt-60  < 0.9 pCi/L N REG PV-APP-9-0916  APP-9  09/21/2016 Cesium-134 < 1.6 pCi/L N REG PV-APP-9-1116  APP-9  11/18/2016 Tritium    < 308 pCi/L N REG PV-APP-9-1116  APP-9 11/18/2016 Cesium-137 < 1.3 pCi/L N REG PV-APP-9-1116  APP-9  11/18/2016 Cobalt-60  < 0.7 pCi/L N REG PV-APP-9-1116  APP-9  11/18/2016 Cesium-134 < 1.7 pCi/L N REG PV-PV-14H-0216  PV-14H 02/01/2016 Tritium    < 242 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cesium-137 < 1.0 pCi/L N REG PV-PV-14H-0216  PV-14H 02/01/2016 Cobalt-60  < 1.4 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cesium-134 < 1.6 pCi/L N REG PV-PV-14H-1016  PV-14H 10/04/2016 Tritium    < 288 pCi/L N PVNGS 2016 ARERR                                                Page 92
____    CALM 0   .76- 1.50      0      0      0      0      0      0      1      0      0      0      0      0      0      0      1      0 2   1.51- 2.50      4      2      0      0      2      1      1      0      0      0      0      1      3     3     2      4 23   2.51- 3.50    21      1      1      3     3     7      4     2      0      0      3     1     0      9      7     8 70  3.51- 4.50    25      9      5      5      0      4     6      0      0      2     3      6      4      6      9    15 99  4.51- 5.50    29    10      2      2      1      4      7     0     0      0      3     1     1      1      4     10 75   5.51- 6.50    11      5     2     0      1     0     2      2      1     1     0      2      0      1     0     4 32   6.51- 8.50      4     2     2      2      1     0     1     1      0      1      0      1      1      0      0      4 20   8.51-11.50      3      1      0     1     0      0      0      0      0      0      0      0      0      0      1      0 6  11.51-14.50      0      0      0      0      0      1      0      0      0      0      0      0      0      0      0      0 1  14.51-20.50      0     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        97    30    12    13      8    17    22      5      1     4      9    12      9    20    24    45 328                                                                                                                               


STABILITY CLASS  ALL SPEED (MPH)        N   NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
PV-PV-14H-1016  PV-14H 10/04/2016 Cesium-137 < 0.8 pCi/L N PV-PV-14H-1016  PV-14H 10/042016 Cobalt-60 < 0.8 pCi/L N PV-PV-14H-1016  PV-14H 10/04/2016 Cesium-134 < 0.8 pCi/L N PV-PV-PV-195A-0216  195A  02/01/2016 Tritium    < 242 pCi/L N REG PV-PV-PV-195A-0216  195A  02/01/2016 Cesium-137 < 2.1 pCi/L N REG PV-PV-PV-195A-0216  195A   02/01/2016 Cobalt-60  < 1.4 pCi/L N REG PV-PV-PV-195A-0216  195A  02/01/2016 Cesium-134 < 1.3 pCi/L N REG PV-PV-PV-195A-1016  195A  10/04/2016 Tritium    < 288 pCi/L N PV-PV-PV-195A-1016  195A  10/04/2016 Cesium-137 < 0.3 pCi/L N PV-PV-PV-195A-1016  195A   10/04/2016 Cobalt-60  < 0.7 pCi/L N PV-PV-PV-195A-1016  195A  10/04/2016 Cesium-134 < 1.0 pCi/L N PV-PV-PV-198AR-0316 198AR  03/16/2016 Tritium    < 287 pCi/L N REG PV-PV-PV-198AR-0316 198AR  03/16/2016 Cesium-137 < 3.1 pCi/L N REG PV-PV-PV-198AR-0316 198AR  03/16/2016 Cobalt-60  < 1.3 pCi/L N REG PV-PV-PV-198AR-0316 198AR  03/16/2016 Cesium-134 < 1.6 pCi/L N REG PV-PV-34H-0216  PV-34H 02/23/2016 Tritium    < 299 pCi/L N REG PV-PV-34H-0216   PV-34H 02/23/2016 Cesium-137 < 1.0 pCi/L N REG PV-PV-34H-0216   PV-34H 02/23/2016 Cobalt-60  < 1.4 pCi/L N REG PV-PV-34H-0216   PV-34H 02/23/2016 Cesium-134 < 1.8 pCi/L N REG PV-PV-PV-R2AR-0216  R2AR   02/03/2016 Tritium    < 303 pCi/L N REG PV-PV-PV-R2AR-0216 R2AR  02/03/2016 Cesium-137 < 1.0 pCi/L N REG PV-PV-PV-R2AR-0216 R2AR  02/03/2016 Cobalt-60  < 1.4 pCi/L N REG PV-PV-PV-R2AR-0216  R2AR  02/03/2016 Cesium-134 < 1.9 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR  10/12/2016 Tritium   < 288 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR  10/12/2016 Cesium-137 < 0.5 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR  10/12/2016 Cobalt-60 < 0.5 pCi/L N REG PV-PV-PV-R2AR-1016  R2AR   10/12/2016 Cesium-134 < 0.5 pCi/L N REG PV-PV-PV-193A-1116  193A  11/08/2016 Tritium    < 289 pCi/L N PVNGS 2016 ARERR                                                Page 93
____    CALM 0   .76- 1.50      1      0      2     2      0      1     2      0      0      1      0      0      0      0      1      0 10   1.51- 2.50      5      3     0     4      4      5      9      1      3     1      3      3    11      7      4      7 70   2.51- 3.50    32    11      5      9    10    12    14      7     5      6    12      5    10     18    18    20 194  3.51- 4.50    30    16     10    12      6     12      9      4    12    18    17    11      8    13    12    19 209   4.51- 5.50    32    20    13      8      7    10    19    12    30    25    27    15      8      8      8    15 257   5.51- 6.50    17    15    17      9      5      5    12    14    46    40    27    27    12      9      4     11 270   6.51- 8.50    11    13    32    24    13    11    14    16    48    53    74    25    23    10      6      8 381   8.51-11.50    10      9    13    16    15    21      8    13    18    58    86    36    28      7      9    13 360 11.51-14.50      6      2    10      3      8      7      8      3    14    38    47      7      5    12    13      7 190 14.51-20.50      2      2      8      5      8      4     2      3      7    23    33      4      4      3      7      4 119    >20.50        0      0      1      0      1      1      0      2      0      3      9     1      0      2      1      0 21 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL      146    91   111    92    77    89    97    75    183    266    335    134    109    89    83    104 2081 TOTAL NUMBER OF OBSERVATIONS: 2088 TOTAL NUMBER OF VALID OBSERVATIONS: 2081 TOTAL NUMBER OF MISSING OBSERVATIONS:    7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.7 %
MEAN WIND SPEED FOR THIS PERIOD:   7.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A        B        C        D        E        F        G 16.00      9.61      7.16    15.19    19.56    16.72    15.76                               
PV-PV-PV-193A-1116 193A  11/08/2016 Cesium-137 < 0.8 pCi/L N PV-PV-PV-193A-1116 193A  11/08/2016 Cobalt-60  < 0.2 pCi/L N PV-PV-PV-193A-1116 193A  11/08/2016 Cesium-134 < 0.9 pCi/L N PV-PV-Q8-1116  PV-Q8 11/08/2016 Tritium    < 289 pCi/L N PV-PV-Q8-1116  PV-Q8 11/08/2016 Cesium-137 < 1.7 pCi/L N PV-PV-Q8-1116  PV-Q8 11/08/2016 Cobalt-60  < 1.9 pCi/L N PV-PV-Q8-1116  PV-Q8 11/08/2016 Cesium-134 < 1.6 pCi/L N PVNGS 2016 ARERR                                          Page 94


DISTRIBUTION OF WIND DIRECTION VS STABILITY N    NNE    NE    ENE      E   ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  CALM 
APPENDIX E 2015 ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT CORRECTION PVNGS 2016 ARERR                                                  Page 95


A        1     3     12    13     17    15    13    20    61    57    69    19    13      8      8      4      0 B        1      3      7      9      9    13      7    13    40    37    31    13      8      6      2      1      0 C        2      1    11      9      9      5      6      8    24     33    15    11      9      4      2      0      0 D        6    15    20    18    12    18    22    16    31    46     50    18    23    11     3      7      0 E      19    16    28    10    17      8    13    11     20    50    95    27    24    18    28    23      0 F      20    23    21    20      5    13    14      2      6    39     66    34    23    22    16    24      0 G      97    30    12    13      8    17    22      5      1      4      9    12      9    20    24    45      0 TOTAL    146    91    111    92    77    89    97    75    183    266    335    134    109    89    83    104      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 REVISION 27 McDowell,          Digitally signed by McDowell, Joshua (Z08270)
Joshua            DN: cn=McDowell, Joshua (Z08270)
Reason: I am the author of this document Originator          (Z08270)          Date: 2016.03.29 13:47:09 -07'00' Digitally signed by Routolo, Robert Routolo, Robert    M(Z99739)
DN: cn=Routolo, Robert M(Z99739)
M(Z99739)
Reason: I have reviewed this document Date: 2016.03.24 10:42:46 -07'00' Technical Reviewer______________________________________
Digitally signed by Moeller, Moeller, Carl     Carl (Z09119)
DN: cn=Moeller, Carl Director, Radiation (Z09119)
(Z09119)
Date: 2016.03.25 06:25:14 Protection                            -07'00' Digitally signed by McGhee, Mark McGhee, Mark DN:  A(Z65028) cn=McGhee, Mark A(Z65028)
A(Z65028)          Reason: PRB Chairman Approval Date: 2016.03.24 11:39:05 -07'00' PRB                ______________________________________
03/25/2016 Effective Date:


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  6/30/2016                                                         
TABLE OF CONTENTS TITLE                                                                                  PAGE


                                                             *** 1ST SEMI ***                                                     
==1.0 INTRODUCTION==
1 1.1  Liquid Effluent Pathways                                                             1 1.2  Gaseous Effluent Pathways                                                            2 1.3  Nuisance Pathways                                                                    2 1.4  Meteorology                                                                          4 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS                                                        5


STABILITY CLASS  A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===2.1 Requirements===
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  4.51- 5.50      0      0      0      1     1      1      2     1     3      0      1      0      0      0      0      0 10  5.51- 6.50      0      1      0      0      2     0      1     6    13      8      4      0      0      0      0      0 35  6.51- 8.50      0      0      1      4      3     4      6    10    27    10    19      7      4      3      1     0 99  8.51-11.50      1      1      0      4     8    10      0      4      8    19    25    10    10      4      5      2 111  11.51-14.50      1      1      5      1     1      1      4      0      7    14    22    10      4      3      6      3 83  14.51-20.50      0      0      5     3     2      2      0      1      5    12      3      2      2      4      0      4 45    >20.50        0     0      1      0      0      0      0      0      0      2      6      1      0      1      1      0 12  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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 (QSITE)                                    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
____    TOTAL        2      3    12    13    17     18    13    22    63    65    80    30    20    15    13      9 395 


STABILITY CLASS  B                                                   
===3.1 Requirements===
Gaseous Effluents                                                      17 3.1.1 Surveillance Requirements                                                      17 3.1.2 Implementation of the Requirements                                            18


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===3.2 Requirements===
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      1      0      1      0      0      0      0      0 2   4.51- 5.50      0      1      1     3     1      1      1      5    12      1      2      1      1      1      1      1 33  5.51- 6.50      1      2      0      2      1      1      2      4    21    10      7      7      2      2      2      0 64  6.51- 8.50      0      2      5      5      3      6      1      5    10    13    14      8      6      2     0      0 80  8.51-11.50      0      1      2     4     3      3      3      2      2    12    12      6      3      1      0      2 56  11.51-14.50      0      1      0      0     1      3      0      1      0      6      9      1      0      2      0      0 24  14.51-20.50      0      0      2      0      1      0      0      0      0      4      4      1      0      0      0      0 12    >20.50        0      0      0      0      0      1      0      0      0      2      0      0      0      1      0      0 4  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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
____    TOTAL        1      7    10    14    10    15      7    17    46    48    49    24    12      9      3      3 275                                                          STABILITY CLASS  C                                                   


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===4.1 Requirements===
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      1      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 1  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      1      0      1      0      0 2  3.51- 4.50      0      0      0      0      0      0      0      0      3      4      2      2      2      0      0      1 14  4.51- 5.50      2      0      3      5      4      1      3      6    17    11      2      1      1      1      1      3 61  5.51- 6.50      2      2      6      2      1     1      1      3    11    19      7      7      3      2      0      2 69  6.51- 8.50      0      4      8      7      7      3      3      1     8      9      5      5      3      2      1      1 67  8.51-11.50      0      0      6      2      3      4     1      2      3      5      2      2      3      0      0      0 33  11.51-14.50      1     0      1      0      3      0      1      0      0      3      7      0      1      0      0      0 17  14.51-20.50      0      0      0      0      0      0      0      0      0      2     5      0      0      1      0      0 8    >20.50        0      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Noble Gases                                                            31 4.1.1 Surveillance Requirements                                                      31 4.1.2 Implementation of the Requirement: Noble Gas                                  32
____    TOTAL        6      6    24    16    18      9      9    12    42    53    31    18    13      7      2      7 273 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  6/30/2016   


                                                          *** 1ST SEMI ***
===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


STABILITY CLASS  D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET
===4.3 Requirements===
Gaseous Radwaste Treatment                                            36 4.3.1 Surveillance Requirements                                                      36 4.3.2 Implementation of the Requirement                                              37


WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===4.4 Requirements===
____    CALM 0    .76- 1.50      1      0      1      0      0      0      1      0      0      1      0      0      0      0      0      0 4  1.51- 2.50      1      1      2      1      0      1      6      3      3      6      5      2      5      1      1      2 40  2.51- 3.50    14      5      4      4      6      4    10    11    20    20    19      9      5      8      2      9 150  3.51- 4.50      7      9    11      7      2      5      5      6    21    24    17      6      7      1      6      4 138  4.51- 5.50      6    15    11      5      3      3      9      8    12    17    16      6      5      4      1      3 124  5.51- 6.50      2      3    11      6      0      4     1      2      8    11      7      7      2      2      3      2 71  6.51- 8.50      5      5      9    12      3      0      1      1      6      6    11      8      5      2      1      1 76  8.51-11.50      0      3      6      3      8      8      2      3      2    11    11    10    11      2      2      1 83  11.51-14.50      0      0      1      3      5      0      0      1      2      9    13      4      4     3      0      2 47  14.51-20.50      1      2      1      1      6      2      2      0      4      8    13      3      4      6      2      0 55    >20.50        0      0      0      0      0      0      0      1      0      4      2      0      0      0      0      0 7  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Liquid Effluents                                                      57 4.4.1 Surveillance Requirements                                                      57 4.4.2 Implementation of the Requirements                                            57 i                                      ODCM Rev. 27
____    TOTAL        37    43    57     42    33    27    37    36    78    117    114    55    48    29    18    24 795 STABILITY CLASS  E SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
____    CALM 0    .76- 1.50      0      0      1      1      1      0      0      0      0      0      1      1      0      0      2      0 7  1.51- 2.50      5      5      0      1      3      2      0      3      1      2      2      5      2      4     2      3 40  2.51- 3.50      7      5      1      2      2      1      2      0      0      5      4     8      8      6    13      3 67  3.51- 4.50      3      2      1     2      3      1      0      1      4     6      7      6      3      4      8      5 56  4.51- 5.50      4      4      2      1      1      0      1      0      8    13      8      3      1      2      4     3 55  5.51- 6.50      4      5      6      0      0      0      2     1      4      6    10      5      3      5      3      3 57   6.51- 8.50      4      6    14      4      2      2      3      3      7    16    28    11    14      5      2      4 125  8.51-11.50      6      6      6      6      0      4      3      2      4    16    40    17    14      6      2      8 140  11.51-14.50      4      1      3      4      4      2      3      1      5    17    22      3      1    17    10      4 101  14.51-20.50      1      0      0      0    18      0      0      2      1      8    20      4      5      6      5      3 73    >20.50        0      0      0      0      2      0      0      1      3      0      2      2      0      0      0      0 10  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        38    34    34    21    36    12    14    14    37    89    144    65    51    55    51    36 731 STABILITY CLASS  F                                                   


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
TABLE OF CONTENTS TITLE                                                                                    PAGE 5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE                                                      58
____    CALM 0    .76- 1.50      0      0      1      1      0      1      0      0      0      0      0      0      0      0      0      0 3  1.51- 2.50      5      2      0      2      0      1      4      1      2      1      5      5      5     6      5      4 48  2.51- 3.50      9      7      2      7      4      3      3      2      1      3      8      4    10      9    17    13 102  3.51- 4.50      7      4      1      4      1      3      0      0      1    11    10      6      5      7    10    12 82  4.51- 5.50      5      5      6      1      1      1      4      0      1      9    12    13      6      5      6      8 83  5.51- 6.50      4      9      8      3      1      1      3      1      1    12    13    11      7      5      4    10 93  6.51- 8.50      6      8      7      4      1      2      1      2      2    20    30    14      6      7      9      8 127  8.51-11.50      3      1      2      2      0      1      0      0      1    18    20      7      4    12      9      9 89  11.51-14.50      0      0      0     0      0      0      0      0      0      1      0      0      1      0      0      2 4  14.51-20.50      0      0      0      1      1      0      0      0      0      0      1      0      0      0      0      0 3    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL       39    36    27    25      9    13    15      6      9    75    99    60    44    51    60    66 634 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO  6/30/2016   


                                                        *** 1ST SEMI ***
===5.1 Requirement===
STABILITY CLASS  G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH 
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


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET
===6.1 Requirement===
REMP                                                                    62 6.1.1 Surveillance Requirements                                                      63 6.1.2 Implementation of the Requirements                                            63


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===6.2 Requirement===
____    CALM 0    .76- 1.50      0      1      0      0      0      0      1      0      0      0      0      0      0      1      2     0 5  1.51- 2.50    15      5      3      1      4      1      1      0      0      2      1      5      9    10    18    22 97  2.51- 3.50    70    12      9      8      5    10      5      4      2      5      6     2      8    28    41    56 271  3.51- 4.50    93    22      8      8      1      5      7      2     1      4      4      8    11    18    35    86 313  4.51- 5.50    95    24      4      4      1      5      7      0      1      1      6      4      3      6    21    48 230  5.51- 6.50    47    24      5      1      1      0      2      2      1      3      1     3      2      6      5    16 119  6.51- 8.50    46    12      3      2      1      0      1      1      1      3      1      2      2     0      1    16 92  8.51-11.50    16    11      1      1      0      0      0      0      0      2      0      0      0      0      1      2 34  11.51-14.50      0      0      0      0      0      1      0      0      0      0      0      0      0      0      0      0 1  14.51-20.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Land Use Census                                                        71 6.2.1 Surveillance Requirements                                                      71 6.2.2 Implementation of the Requirements                                            71
____    TOTAL      382    111    33    25    13    22    24      9      6    20    19    24    35    69    124    246 1162                                                                                                                               


STABILITY CLASS  ALL SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===6.3 Requirement===
____    CALM 0    .76- 1.50      1      1      3     2      1      1      2      0      0      1      1      1      0      1      4      0 19  1.51- 2.50    27    13      5      5      7      5    11      7      6     11    13    17    21    21    26    31 226  2.51- 3.50    100    29    16    21    17    18    20    17    23    33    37    24    31    52    73    81 592  3.51- 4.50    110    37    21    21      7    14    12      9    31    49    41    28    28    30    59    108 605  4.51- 5.50    112    49    27    20    12    12    27    20    54    52    47    28    17    19    34    66 596  5.51- 6.50    60    46    36    14      6      7    12    19    59    69    49    40    19    22    17    33 508  6.51- 8.50    61    37    47    38    20    17    16    23    61    77    108    55    40    21    15    30 666  8.51-11.50    26    23    23    22    22    30      9    13    20    83    110    52    45    25    19    24 546  11.51-14.50      6      3    10      8    14      7      8      3     14    50    73    18    11    25    16    11 277  14.51-20.50      2      2      8      5    28      4      2     3    10    34    46    10    11    17      7     7 196    >20.50        0     0      1      0      2      1      0      2      3      8    11      3      0      2      1      0 34  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Interlaboratory Comparison Program                                      72 6.3.1 Surveillance Requirements                                                      72 6.3.2 Implementation of the Requirements                                            72 7.0 RADIOLOGICAL REPORTS                                                                      83
____    TOTAL      505    240    197    156    136    116    119    116    281    467    536    276    223    235    271    391 4265 


TOTAL NUMBER OF OBSERVATIONS:  4272 TOTAL NUMBER OF VALID OBSERVATIONS:  4265 TOTAL NUMBER OF MISSING OBSERVATIONS:    7 PERCENT DATA RECOVERY FOR THIS PERIOD:  99.8 %
===7.1 Requirement===
MEAN WIND SPEED FOR THIS PERIOD:  6.8 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         
Annual Radioactive Effluent Release Report                              83


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A        B         C        D        E        F        G 9.26      6.45      6.40    18.64    17.14    14.87    27.25                               
===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. 27


DISTRIBUTION OF WIND DIRECTION VS STABILITY N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  CALM  
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 iii                      ODCM Rev. 27


A        2      3    12     13     17    18    13    22    63    65    80    30    20    15    13      9      0 B        1      7    10    14     10    15     7    17     46    48    49    24    12      9      3      3      0 C        6      6    24    16    18      9      9    12    42    53    31    18    13      7      2     7      0 D      37    43    57    42    33    27    37    36    78    117    114    55     48    29    18     24      0 E      38    34    34    21    36    12    14    14    37    89    144    65    51    55    51    36      0 F      39    36    27    25      9    13    15      6      9    75    99    60    44    51    60    66      0 G      382    111    33    25    13    22    24      9      6    20    19    24    35    69    124    246      0 TOTAL    505    240    197    156    136    116    119    116    281    467    536    276    223    235    271    391      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION  
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 l                                      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. 27


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  7/01/2016 TO  9/30/2016                                                         
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 10 - 35 Miles              78 6-3  Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED      79 6-4  Site Exclusion Area Boundary DELETED                                                  80 6-5  Gaseous Effluent Release Points                                                        81 6-6  Low Population Zone DELETED                                                            82 v                                ODCM Rev. 27


                                                            *** 3RD QRTR ***
==1.0    INTRODUCTION==
STABILITY CLASS  A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE   SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      1      0      0      0      0      0      0      0      0      0      0      0      0      0 1  4.51- 5.50      0      0      1      0      0      0      1      1      0      0      0      0      0      0      0      0 3  5.51- 6.50      0      0      0      2      2      4      3      7    14      5      1      2      0      0      0      1 41  6.51- 8.50      1      2      1      2      4    10      9    18    24    18    18    10      5      3      2      1 128  8.51-11.50      0      1      0      0      3    18      1      5    11    15    26    15    11      3      2      2 113  11.51-14.50      0      0      0      0      1      2      0      2      0      3    12      4      1      0      0      0 25  14.51-20.50      0      0      0      1      0      0      0      1      0      2      3      0      0      0      0      0 7    >20.50        1      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        2      3      3      5    10    34    14    34    49    43    60    31    17      6      4      4 319                                                                                                                               


STABILITY CLASS  B SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
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.
____    CALM 0    .76- 1.50     0     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0     0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  4.51- 5.50     1      0      0      0      0      0      2      3      6      2      2      0      1      0      0      1 18  5.51- 6.50      0      2      2      0      1     0      0      3    10     6      7      1     1     1     0      0 34  6.51- 8.50      0      2     1      4      3      5      4      5     8      8    13      7      4      0      0      1 65  8.51-11.50      0      0      2      3      3      6      0      0      4     6    17      9      2      2      0      0 54  11.51-14.50      0      0      1      0      1      1      1      0      4      3     7      1      0      0      0      0 19  14.51-20.50      0      0      0      0      2      0      0      1     0      0      2      0      0      0      0      0 5    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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:
____    TOTAL        1      4      6      7    10    12      7    12    32    25    48    18      8      3      0      2 195                                                          STABILITY CLASS  C                                                   
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.
1                                           ODCM Rev. 27


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
1.2 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:
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      1     0      0      1      1      0      0      0      0      0      1      0      1      0 5  4.51- 5.50     0      1     1      0      1      1      3      2     8      5      3      1      0      0      2     2 30  5.51- 6.50      1      0      0      0      2     0     1      1      8      4      6      4      1      0     0      1 29  6.51- 8.50      0      1      2      2      1      2      2      1      5    12    14      2      3      1      2      0 50   8.51-11.50      0     1      0      1      0      0      0      0      1      5    11      0      1      0      0      0 20  11.51-14.50      1      1      1      0     4      0     0      0      1     0      3     0      0      0      0      0 11  14.51-20.50      1      0      0      0      3      1      0      1      0      1      1      0      0      0      0      0 8    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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.
____    TOTAL        3      4      5      3    11      5      7      5    23    27     38      7      6      1      5      3 153 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  7/01/2016 TO  9/30/2016   
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.
1.3 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. 27


                                                        *** 3RD QRTR ***
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 Outage Support Facility MAR 2016 3      ODCM Rev. 27


STABILITY CLASS  D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET
1.4 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 X/Q and D/Q are utilized for the particular units releases as applicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathways 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 units 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 units releases as applicable for gases other than noble gases at the controlling pathways 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. 27


WIND THRESHOLD  AT:  .75 MPH 
2.0 GASEOUS EFFLUENT MONITOR SETPOINTS


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===2.1 Requirements===
____    CALM 0    .76- 1.50      0     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      2     0      0      3      1      0      0      0      1      0      1     1      1      3      0      1 14  2.51- 3.50      2      1      2      1      1      1      0      3      5      5      1      2      4      2      5      2 37  3.51- 4.50      2     2      2      3      2      2      1     1      8      5      6      2      1      4      0      3 44  4.51- 5.50      2     1     3      2      3      2      0      1     6      7      7      6      2     2     0      3 47  5.51- 6.50      1      2      1      0      0      0      0      2      5      7      9      6      2      1      1     1 38  6.51- 8.50      2      1      2      2      4      4      3      1      9      6    14      3      4      1      2      0 58  8.51-11.50      3      4      2      3      6      4      1      0      4    16    22      7      3      2      1      0 78  11.51-14.50      1      6      4      1    16      4      0      2      1      2    20      4      0      0      0      0 61  14.51-20.50      0      3      0      2    11      1      3      3      1      0    22      2      1      0      1      1 51    >20.50        0      0      0      0      0      1      0      1      0      0      0      0      0      0      0      0 2  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Gaseous Monitors The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2-1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.0 MAR 2016      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.
____    TOTAL        15    20    16    17    44    19      8    14    40    48    102    33    18    15    10    11 430 STABILITY CLASS  E                                                   
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 nonfunctional, or change the setpoint so it is acceptably conservative.
MAR 2016
: b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 2-1. Restore the nonfunctional instrumentation to FUNCTIONAL status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this nonfunctionality was not corrected within MAR 2016          the time specified.
2.1.1 Surveillance Requirements
: a. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE MAR 2016                CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2.
: b. The specified Frequency for each Surveillance Requirement is met if the Surveillance Requirement is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as Prior to each release, the above interval extension does not apply.
For Frequencies specified as Once the above interval extension does not apply.
If a Completion Time requires periodic performance on a once per . . . basis, the above Frequency extension applies to each performance after the initial performance.
MAR 2016 5                                      ODCM Rev. 27


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
TABLE 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT                                FUNCTIONAL     APPLICABILITY   ACTION MAR 2016
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      1      0      0      0      0     0      0      0 1   1.51- 2.50      2      1     1      0      2      1      0      0      2      0      0      1      1      4      2      5 22  2.51- 3.50      7      1      3      2      0      1      0      0      1      0      4      2      2      4     8      3 38  3.51- 4.50      4      4      1      1      2      1      0      0      3      2      4      9      6     2      3      3 45  4.51- 5.50      5      1     4      1     1     2      1      0      2      9    12      6      2      1      2      1 50  5.51- 6.50      6      2      5      2      1     4      0      3      2    14    10      6      3      1      3      1 63  6.51- 8.50      3      5      3      6      7      6      2      6      4    18    36      7      4      2      2      2 113  8.51-11.50      3      2      3    10    14      6      4      4      4    25    62    15      1     4      1      3 161  11.51-14.50      2      0      0      3    21      4      3      1     0      9    33      7      0      1      0      1 85  14.51-20.50      3      2      2      0    18      4      0      0      1     2      9      0      0      0      0      0 41    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
: 1. GASEOUS RADWASTE SYSTEM
____    TOTAL        35    18    22    25    66    29    10    14    20    79    170    53    19    19    21    19 619                                                                                                                               
: a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release #RU-12                    1                #          35
: b. Flow Rate Monitor                                          1               #          36
: 2. NOT USED
: 3. DELETED
: 4. PLANT VENT SYSTEM A. Low Range Monitors 6
: a. Noble Gas Activity Monitor #RU-143                    1
* 37
: b. Iodine Sampler                                        1
* 40
: c. Particulate Sampler                                  1
* 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-144                    1
* 42
: b. Iodine Sampler                                        1
* 42
: c. Particulate Sampler                                  1
* 42
: d. Sampler Flow Rate Measuring Device                    1
* 42 ODCM Rev. 27


STABILITY CLASS   F                                                   
TABLE 2-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT                          FUNCTIONAL        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                ##          40
: d. Flow Rate Monitor                                1                ##          36
: e. Sampler Flow Rate Measuring Device              1                ##          36 B. High Range Monitors 7
: a. Noble Gas Activity Monitor #RU-146              1                ##          42
: b. Iodine Sampler                                  1                ##          42
: c. Particulate Sample                              1                ##          42
: d. Sampler Flow Rate Measuring Device              1                ##          42 ODCM Rev. 27


SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
Table 2-1 (Continued)
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      1      0      0      0      0      0      0      0      0 1   1.51- 2.50      3      1      1      0      1      0      1      0      0      0      3      1      3      3      2      1 20   2.51- 3.50      5      1     2      3      0      0      0      2      0      2     3     4      2      1      4     5 34  3.51- 4.50      6      5      4      0      0      0      0      0      0      3      3      5      7      8      7      5 53  4.51- 5.50     10      6      3      2      0      0      1      1      3      6    15      4     3      3      3      2 62  5.51- 6.50      1      4      1      1      0      0      1      1      1      3      7      2      2      0      2      3 29  6.51- 8.50      6      2     2      1     0      0      2      0      1     8     21      6      3     1     1      0 54  8.51-11.50      1      3     1      0      0      0      0      0      0      2      9      2      0      2      0      0 20  11.51-14.50      0      1      0      0      1      0      1      0      0      0      0      1      0      0      0      1 5  14.51-20.50      2      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 2    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      1      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
TABLE NOTATION
____    TOTAL        34    23    14      7      2      0      6      5      5    24    61    25    20    18    20    17 281 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
* 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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, the contents of the tank(s) may be released to the environment MAR 2016              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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the MAR 2016              flow rate is estimated at least once per 4 hours.
ACTION 37 -     With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the MAR 2016              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 hours, OR obtain gas channel monitor readings locally at least once per 12 hours if the channel is functional locally but nonfunctional due to loss of communication with the minicomputer. The surveillance MAR 2016                  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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via the effected pathway may continue provided MAR 2016              samples are continuously collected with auxiliary sampling equipment as required in Table 3-1 within one hour after the channel has been declared nonfunctional.
ACTION 41 -     With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, comply with Technical Requirements Manual TLCO 3.3.108.
MAR 2016 8                                  ODCM Rev. 27


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  7/01/2016 TO  9/30/2016   
Table 2-1 (Continued)
                                                          *** 3RD QRTR ***
TABLE NOTATION ACTION 42 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement initiate the Preplanned Alternate Sampling Program to monitor MAR 2016          the appropriate parameter(s) within 72 hours, and:
: a. Either restore the nonfunctional channel(s) to FUNCTIONAL status within 7 days of the MAR 2016                event, or
: b. Prepare and submit a Special Report to the Commission within 14 days following the event outlining the action(s) taken, the cause of the nonfunctionality, and the plans and schedule for restoring the system to FUNCTIONAL status.
MAR 2016 9                                       ODCM Rev. 27


STABILITY CLASS  G STABILITY BASED ON: DELTA T     BETWEEN 200.0 AND  35.0 FEET
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(1),(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) 10
: 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.            ##
: c. Particulate Sample                              N.A.        N.A.      N.A.        N.A.            ##
: d. Flow Rate Monitor                                D(6)        N.A.      R            Q              ##
ODCM Rev. 27        e. Sampler Flow Rate Measuring Device              D(6)        N.A.       R            Q              ##


WIND MEASURED AT: 35.0 FEET
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.
(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.
11                                        ODCM Rev. 27


WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
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 Ci/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 (Ci/cc) is derived using actual or fan design flow rates.
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      4      0      0      0      0      0      0      0      0      0      0      1     0      0      5      3 13  2.51- 3.50      5      5      1      1      0      1      0      0      0      0      2      0      1     4      5    10 35  3.51- 4.50    24      5      1      1      0      0      0      0      1      0      0      1      2      0      1      8 44  4.51- 5.50    20    12      2      0      0      0      0      0      1      0      1      2      0      0      4      5 47  5.51- 6.50      7      5      2      0      0      0      0      0      1      0      1      1      0      0      0      2 19  6.51- 8.50    11      6      0      0      0      0      0      0      0      1     2      0      0      0      0      2 22  8.51-11.50      4      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 4  11.51-14.50      1      0      0      1     0      0      0      0      0      0      0      0      0      0      0      0 2  14.51-20.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      1      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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.
____    TOTAL        76    33      6      3      0      1      0      0      3      1      6      5      3     4    16    30 187 STABILITY CLASS  ALL SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
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.
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      1      1      0      0      0      0      0      0      0 2  1.51- 2.50    11      2      2      3      4      1     1      0      3      0      4      4      5    10      9    10 69  2.51- 3.50    19      8      8      7      1      3      0      5      6      7    10      8      9    11    22    20 144  3.51- 4.50    36    16    10      5      4      4      2      1    12    10    13    17    17    14    12    19 192  4.51- 5.50    38    21    14      5      5      5      8      8    26    29    40    19      8      6    11    14 257  5.51- 6.50    16    15    11      5      6      8      5    17    41    39    41    22      9      3      6      9 253  6.51- 8.50    23    19    11    17    19    27    22    31    51    71    118    35    23      8      9      6 490  8.51-11.50    11    11      8    17    26    34      6      9    24    69    147    48    18    13      4      5 450  11.51-14.50      5      8      6      5    44    11      5      5      6    17    75    17      1      1      0      2 208  14.51-20.50      6      5      2      3    34      6      3      6      2      5    37      2      1     0      1      1 114    >20.50        1      0      0      0      0      1      0      1      0      0      0      0      0      0      2      0 5  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
The equations in Section 3.1 of this manual provide the methodology for calculating the gaseous effluent dose rate.
____    TOTAL      166    105    72    67    143    100    52    84    172    247    485    172    91    66    76    86 2184 TOTAL NUMBER OF OBSERVATIONS:  2184 TOTAL NUMBER OF VALID OBSERVATIONS:  2184 TOTAL NUMBER OF MISSING OBSERVATIONS:    0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
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.
MEAN WIND SPEED FOR THIS PERIOD:  7.8 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         
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. 27


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A        B        C        D        E        F        G 14.61     8.93      7.01    19.69    28.34    12.87      8.56                               
2.1.2.1 Equivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows:
K eq =  i[ ( Ki ) ( fi ) ]                                                      (2-1)
Where:
Keq            = the equivalent whole body dose factor weighted by historical radionuclide distribution in releases in mrem/yr per Ci/m3.
Ki              = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per 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 + 1.1M ) eq =     i[ ( Li + 1.1Mi ) ( fi ) ]                                (2-2)
Where:
(L+1.1M)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 Ci/m3.
Li              = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per Ci/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 Ci/m3 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. 27


DISTRIBUTION OF WIND DIRECTION VS STABILITY N    NNE    NE    ENE     E    ESE    SE    SSE     S    SSW    SW    WSW      W    WNW    NW    NNW  CALM 
2.1.2.2 Site Release Rate Limit (QSITE)
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 (QSITE) is the lower of QWB or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded.
The QSITE is established as follows:
( D WB ) ( 0.8 )
Q SITE,WB = ----------------------------------------                                (2-3)
( K eq ) ( X/Q )SITE Where:
QSITE,WB      = the site release rate, in Ci/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 Ci/m3 weighted by the historical radionuclide distribution.
(X/Q)SITE     = 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.
( D SK ) ( 0.8 )
Q SITE,SK = -----------------------------------------------------------              (2-4)
( L + 1.1M ) eq ( X/Q ) SITE Where:
QSITE,SK      = the site release rate limit, in Ci/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+1.1M)eq = equivalent skin dose factor, in mrem/yr per Ci/m3, weighted by the radionuclide distribution.
(X/Q)SITE     = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, 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 QSITE 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. 27


A        2     3     3      5     10    34    14    34    49    43    60    31    17      6      4      4      0 B        1     4     6      7    10    12      7    12    32    25    48    18      8      3      0      2     0 C        3      4      5      3    11      5      7      5    23    27    38      7      6      1     5      3      0 D      15    20    16    17    44    19      8    14    40    48    102    33    18    15    10    11      0 E      35    18    22    25    66    29    10    14    20    79    170    53    19    19    21    19      0 F      34    23    14      7      2     0      6     5      5    24    61    25    20    18    20    17      0 G       76    33      6      3      0      1     0      0      3      1      6      5      3      4    16    30      0 TOTAL    166    105    72    67    143    100    52    84    172    247    485    172    91    66    76    86      0 
2.1.2.3 Unit Release Rate Limits (QUNIT)
Typically QSITE will be divided equally among operating units. If operational history dictates a larger fraction of the QSITE be assigned to a specific unit then a weighted average of each units contribution to the QSITE will be utilized to determine the QUNIT.
QUNIT          = (fUNIT) (QSITE)                                                            (2-5)
Where:
QUNIT          = unit release rate limit, in Ci/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.
QSITE          = the site release rate limit, in Ci/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 (QUNIT) 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            ( Q UNIT ) ( a )
                                                                -                                  (2-6)
Setpoint ( 472 ) ( Flow Rate )
Where:
Monitor Setpoint       = the setpoint for the effluent monitor, in Ci/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.
QUNIT          = unit release rate limit, in Ci/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 QUNIT allocated for a specific release point. The sum of these administrative values shall be less than or equal to one.
15                      ODCM Rev. 27


ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
Monitor RU-12 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:
Monitor [ ( Q UNIT ) ( a ) ( 0.9 ) - ( H ) ( PF ) ( 472 ) ]
                      ----------------------------------------------------------------------------------------        (2-7) setpoint                        ( Flow Rate ) ( 472 )
Where:
Monitor Setpoint      = the setpoint for the monitor, in Ci/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 Ci/sec, 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 Ci/cc.
a            = fraction of QUNIT 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 feet/minute.
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. 27


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016                                                         
3.0    GASEOUS AND LIQUID EFFLUENT DOSE RATES


                                                              *** 4TH QRTR ***                                                     
===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 I-131 and I-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. 27


STABILITY CLASS  A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
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.
____    CALM 0   .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  4.51- 5.50      0      0      0      0      1      0      0      0      0      0      0      0      0      0      0      0 1  5.51- 6.50      0      0      0      1      0      0      2     1      1      0      0      0      0      0      0      0 5  6.51- 8.50      0      0      1      0      2      1      6      4      2      0      2      0      0      0      2      0 20  8.51-11.50      0      0      0      1      0      3     0      0      0      1      0      0      1      2      0      1 9  11.51-14.50      0      0      0      0      0      0      0      0      0      0      1     0      1     1     0      0 3  14.51-20.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
For whole body dose rate:
____    TOTAL        0      0      1      2      3      4      8      5      3      1      3      0      2      3      2      1 38                                                                                                                               
D WB =    i[ ( Ki ) ( X/Q )SITE ( Qi ) ]                                            (3-1)
For skin dose rate:
D SK =   i[ ( Li + 1.1Mi ) ( X/Q )SITE ( 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 Ci/m3 from Table 3-3.
Qi            = the release rate of radionuclide i, in Ci/sec.
(X/Q)SITE    = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, 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 Ci/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 Ci/m3 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. 27


STABILITY CLASS  B                                                   
I-131, I-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 =    i[ ( Pi ) ( X/Q )SITE ( Qi ) ]                                                  (3-3)
Where:
Pi            = the dose factor, in mrem/yr per Ci/m3, for radionuclide i, for the inhalation pathway, from Table 3-4.
(X/Q)SITE      = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, at the Site Boundary, for any of the three units, Qi            = the release rate of radionuclide i, in Ci/sec Do            = the total organ dose rate (mrem/yr).
19                                  ODCM Rev. 27


SPEED (MPH)        N    NNE     NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL  ___________                                                                                                                  _
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) (Ci/ml)a A. Waste Gas Storage         P              P            Principal Gamma            1.0E-04 Each Tank Grab Each Tank     Emittersg Sample B. Containment Purge        P              P            Principal Gamma            1.0E-04 Each Purgeb,c Each Purgeb,c Emittersg Grab Sample H-3                        1.0E-06 C. 1. DELETED                Mb,e          Mb            Principal Gamma            1.0E-04
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      1     0      0      1      0      0      0      0      0      0 2  4.51- 5.50      0      0      0      2      1      1      1      4     5      0      1     0      0      0      1      2 18   5.51- 6.50      0      0      2      2      1     1      3      4      2      2      0      1      0      0      0      0 18  6.51- 8.50      0      0      0      5      5      2      3      6      0      7      2      0      0      0      0      1 31  8.51-11.50      1      0      0      0      5      0      1      0      0      3      3      0      0      0      1     0 14  11.51-14.50      0      0      0      1      3      0      0      1      0      0      1      0      0      0      0      0 6  14.51-20.50      0      0      1      2      0      0      0      0      0      0      0      0      0      0      0      0 3    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
: 2. Plant Vent            Grab Sample                  Emittersg
____    TOTAL        1      0      3    12    15      4      9    15      7    13      7      1      0      0      2      3 92 STABILITY CLASS  C                                                   
: 3. Fuel Bldg. Exhaust H-3                       1.0E-06 Continuousf    4/Md          I-131                      1.0E-12 Charcoal Sample        I-133                      1.0E-10 Continuousf    4/Md          Principal Gamma            1.0E-11 Particulate   Emittersg Sample        (I-131, Others)
Continuousf    M            Gross Alpha                1.0E-11 Composite Particulate Sample Continuousf    Q            Sr-89, Sr-90              1.0E-11 Composite Particulate Sample D. All Radwaste Types as    Continuousf    Noble Gas    Noble Gases Gross Beta    1.0E-06 listed in A., B., and C.,                Monitor      or Gamma above.
20                               ODCM Rev. 27


SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
Table 3-1 (Continued)
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0 1  3.51- 4.50      0      0      0      0      0      2      3      6      6      4      1      0      1      1      1      0 25  4.51- 5.50      1      2     2      5      2      0      1      8    10      3      0      1      1      1      1      0 38  5.51- 6.50      0      1      0      1      0      1      0      3      1      0      1      0      1      0      1      1 11  6.51- 8.50      0      0      2     3      1      0      1      0      2      2      3      1      0      0      1      1 17  8.51-11.50      0      1      4      0      3      2      0      0      0      3      4      0      0      0      0      2 19  11.51-14.50      0      1      0      0      7      0      0      0      0      2      0      1      0      1      0      1 13  14.51-20.50      0      0      0      0      1      0      0      0      0      0      2      0      0      0      0      0 3    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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.
____    TOTAL        1      5      8      9    14      5      5    17    19    14    12      3      3      3      4      5 127 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION
For a particular measurement system (which may include radiochemical separation):
4.66 s b LLD = -------------------------------------------------------------------------------
E
* V
* 2.22E6
* Y
* exp ( - t )
Where:
LLD is the a priori lower limit of detection as defined above (as Ci 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 radiochemical yield (when applicable),
is the radioactive decay constant for the particular radionuclide, and t 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 t 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. 27


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016   
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 nonfunctional, samples must be obtained as MAR 2016 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 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.
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. 27


                                                        *** 4TH QRTR ***
TABLE 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY UNIT 1                      UNIT 2                                      UNIT 3 DISTANCE            X/Q            D/Q      DISTANCE          X/Q            D/Q      DISTANCE          X/Q            D/Q DIRECTION (METERS)          (SEC/m3)        (m-2)      (METERS)        (SEC/m3)        (m-2)      (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.l4E-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 23                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        l607        8.9lE-06      5.73E-09 SW          1487        7.47E-06      5.65E-09        1208        7.72E-06      6.88E-09        l057        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        l045        4.l7E-06      7.98E-09 NNW          1069        3.70E-06      7.26E-09        1342        2.85E-06      4.87E-09        l56l        2.93E-06      4.58E-09


STABILITY CLASS  D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH 
==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.
ODCM Rev. 27


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET
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 mrem-m3        mrem-m3      mrad-m3      mrad-m3 Radionuclide              yr-Ci          yr-Ci        yr-Ci      yr-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        1.01E+04      1.73E+04    1.06E+04 Kr-90                    1.56E+04        7.29E+03      1.63E+04    7.83E+03 Xe-13lm                  9.15E+01        4.76E+02      1.56E+02    1.11E+03 Xe-133m                  2.51E+02        9.94E+02      3.27E+02    1.48E+03 Xe-133                  2.94E+02        3.06E+02      3.53E+02    1.05E+03 Xe-135m                  3.12E+03        7.11E+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      1.51E+03    1.27E+04 Xe-138                  8.83E+03        4.13E+03      9.21E+03    4.75E+03 Ar-41                    8.84E+03        2.69E+03      9.30E+03    3.28E+03


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
==Reference:==
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      1      2      2      1      1      0      1      3      1      0      5      2      0      0      3      2 24   2.51- 3.50    10      2      3      5      2      1      1      4      6      9      7      6    10      8      2      7 83  3.51- 4.50      6      4      7      3      1      2      1      4    13    11      6      1      2      3      5      8 77  4.51- 5.50      1      3      4      3      3      1      4      3      3      4      6      4      3      1      0      4 47  5.51- 6.50      3      1      4      3      0      1      0      0      3      4      4      4      1      1      1      0 30  6.51- 8.50      5      4      1      2      1      3      1      1      2      5    12      4      1      0      3      3 48  8.51-11.50      0      1      6      3      5      1      2      0      0      4      8      3      1      1      1      2 38  11.51-14.50      0      1      0      1    15      3      2      0      0      0      9      3      2      0      0      0 36  14.51-20.50      0      0      1      0    18      0      1      0      1      1      2      1      0      0      0      0 25    >20.50        0      0      0      0      1      0      0      0      0      0      0      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Regulatory Guide 1.109, Table B-1.
____    TOTAL        26    18    28    21    47    12    13    15    29    38    59    28    20    14    15    26 409 STABILITY CLASS  E                                                   
24                               ODCM Rev. 27


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
TABLE 3-4 Pi VALUES FOR THE INHALATION PATHWAY (mrem/yr/Ci/m3)
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      1      0      0      0      0      0      0      0 1   1.51- 2.50      5      4      0      1     0      1     1      1     2      3      7      4      5    11      4      1 50  2.51- 3.50      3      2      0      1     1      3      0      1      4      3      3      3      3      4      2     6 39  3.51- 4.50      8      6      1      2     1      0      0      1      3     3      5      4      2      4      6      3 49   4.51- 5.50      1      6      0      2      0      0      1      3      2      2      8      7      1      0      3     5 41  5.51- 6.50      3      3      3      2      0      0      0      1      2      2      3      4      3      2      1     0 29  6.51- 8.50      4      3      4      2      2      3      1      1      0      5      9     3      3      0      1      1 42  8.51-11.50      1      2     0      3      6      8      1      1      3      3      2      3      0      1      1      2 37  11.51-14.50      0      1      1      0      6     4      1      0      0      1      1      5      1      1      1      0 23  14.51-20.50      0      0      0      0      6      0      0      0      0      1      6      1      0      3      0      1 18    >20.50        0      0      0      0      0      0      0      0      0      0      0      1      1      3      0      0 5  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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 I-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. 27
____    TOTAL        25     27     9    13    22    19      5      9    17    23    44    35    19    29    19    19 334                                                                                                                               


STABILITY CLASS   F                                                   
===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:
5.0E-07 Ci/ml for the principal gamma emitters (except Ce-144) 3.0E-06 Ci/ml for Ce-144 1.0E-06 Ci/ml for I-131 1.0E-03 Ci/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 Ci/ml for Cs-134 2.0E-06 Ci/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. 27


SPEED (MPH)         N    NNE    NE    ENE     E    ESE    SE    SSE     S    SSW     SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release                            Sampling &                      Type Of              (LLD)a Pathway                      Destination     Analysis Frequency Notes      Activity Analysis        (Ci/ml)
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0      0 1  1.51- 2.50      5      3      6      0      1     1      0      3     1     0      1      7      3      8      7      2 48  2.51- 3.50     11      4      4      0      0      0      2      0      0      2      3     2      5     7      5      4 49  3.51- 4.50      8      1     2      4      1      0      0      0      4      1     7      5      7      5    11      8 64  4.51- 5.50      7      1      3      0      1      0      0      0      2      2      9      6      0      2      5      3 41   5.51- 6.50      5      0      0      0      1     0      0      0      0      2      6      3     2      3      2      6 30  6.51- 8.50      4      1      2     5     0      0      1     0      1     4     10      2      1      2      4      5 42  8.51-11.50      1      2     3     4     0      0      1      1      0      0      2      0      1      2      0      3 20  11.51-14.50      0      0      1      1      1      0      0      0      0      0      0      0      0      0      0      1 4  14.51-20.50      0      0      0      1     4      0      0      0      0      0      0      0      0      0      0      0 5    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
: 1. Chemical Waste Neutralizer     Retention Tank      P  Each Batch            Principal Gamma Emittersc     5.0E-07 Tank (CWNT)b                    liquid radwaste          N. A.                 I-131                        1.0E-06 H-3                          1.0E-05
____    TOTAL        41    12    21    15      9      1     4      4      8    12    38    25    19    29    34    32 304 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016   
: 2. Steam Generator Blowdown        circ. water          P   Each Batch      1     Principal Gamma Emittersc    5.0E-07 Low TDS Sumpb                  CWNT                    N. A.                 I-131                        1.0E-06 H-3                           1.0E-05
: 3. Condensate
: a. Condensate Polishing Low     circ. water          P  Each Batch      3     Principal Gamma Emittersc    5.0E-07 b
TDS Sump                    CWNT                    N. A.                 I-131                        1.0E-06 H-3                          1.0E-05 27
: b. Initial Backwash            (low TDS sump) to    P   Each Discharge        Principal Gamma Emittersc    5.0E-07 circ. water                                    I-131                        1.0E-06 (low TDS sump) to        N. A.                  H-3                           1.0E-05 CWNT
: c. Pre-service rinse effluent  Retention Tank      P  Each Discharge 2       Principal Gamma Emittersc    5.0E-07 through SC-N-V069                              I-131                        1.0E-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     5.0E-07 CD-N-V194                                      I-131                        1.0E-06 Retention Tank      P  Each Discharge 2       H-3                           1.0E-05 through SC-N-V079
: 4. Turbine Building Sumpd          Retention Tank      D Grab Sample        3     Principal Gamma Emittersc    5.0E-07 CWNT                  N. A.                   I-131                        1.0E-06 H-3                          1.0E-05 ODCM Rev. 27


                                                        *** 4TH QRTR ***
TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release                              Sampling &                          Type Of                (LLD)a Pathway                        Destination      Analysis Frequency Notes          Activity Analysis        (Ci/ml)
: 5. North & South Condenser Area Retention Tank            D Grab Sample        3        Principal Gamma Emittersc      5.0E-07 Sumpsd                      CWNT                        N. A.                      I-131                          1.0E-06 H-3                            1.0E-05
: 6. Steam Generator Blowdown to      Retention Tank    P      Each Discharge 2          Principal Gamma Emittersc      5.0E-07 Retention Tank                  through SC-N-V064                                  I-131                          1.0E-06 H-3                            1.0E-05
: 7. Retention Tank to Evaporation    evaporation pond      P  Each Batch                Principal Gamma Emittersc      5.0E-07 Pond                                                                                I-131                          1.0E-06 H-3                            1.0E-05 28            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 FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and MAR 2016            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 Tanks 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 ODCM Rev. 27


STABILITY CLASS  G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT: 35.0 FEET
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 s b LLD = -------------------------------------------------------------------------------
E
* V
* 2.22E6
* Y
* exp ( - t )
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, is the radioactive decay constant for the particular radionuclide, and t is the elapsed time between midpoint of sample collection and time of counting.
Typical values of E, V, Y, and t should be used in the calculation.
It should be recognized that the LLD is defined as an a 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.
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 3.0E-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. 27


WIND THRESHOLD  AT:   .75 MPH 
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 nonfunctional MAR 2016 Obtain grab sample at least once per 12 hours and analyze in accordance Pre-service rinse to Retention Tanks      At All Times  with section 3.2 Obtain grab sample at least once per 12 hours and analyses in accordance Condensate overboard to Retention Tanks          1-4      with section 3.2 Modes 1-4: Suspend the release Steam Generator Blowdown/Drain to Retention                    Modes 5,6 & defueled: Obtain grab At All Times Tanks                                      sample at least once per 12 hours and analyze in accordance with sec-tion 3.2 30                                    ODCM Rev. 27


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
4.0 GASEOUS & LIQUID EFFLUENTS - DOSE
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      2      0      0      2 4   1.51- 2.50    20    12      3      2      1      1      1      1      2      2      2      4      8    15    16    20 110  2.51- 3.50    56    17      3      4      0      0      0     3      1      1      5      4      6    22    36    53 211  3.51- 4.50    79    37      5      6      2      1      0      1      2      1      3      0    10      7    20    52 226  4.51- 5.50    45    30      4      1      0      0      0      0      0      0      1      0      1      1      3    24 110  5.51- 6.50    23    14      7      2      0      0      0      0      0      1      0      1      0      0      4    10 62  6.51- 8.50    26    19      2      2      0      0      0      0      0      0      0      0      0      0      1    13 63  8.51-11.50      5      8      5      1      0      0      0      0      0      0      0      0      0      0      0      2 21  11.51-14.50      0      0      0      1      0      0      0      0      0      0      0      0      0      0      0      0 1  14.51-20.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL      254    137    29    19      3      2      1      5      5      5    11      9    27    45    80    176 808                                                                                                                               


STABILITY CLASS  ALL SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===4.1 Requirements===
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      1      1      0      0      2      0      0      2 6   1.51- 2.50    31    21    11      4     3      3      3      8      6     5     15    17    16    34    30    25 232  2.51- 3.50    80    25    10     10      3      4      3      8    11    15    19    15    24    41    45    70 383  3.51- 4.50    101    48    15    15      5      5      5    12    28    21    22    10     22    20     43    71 443  4.51- 5.50    55    42    13    13      8      2      7    18    22    11    25    18      6      5    13    38 296  5.51- 6.50    34    19    16    11      2      3      5      9      9    11    14    13      7      6      9    17 185  6.51- 8.50    39    27    12    19    11      9    13    12      7    23    38    10      5      2    12    24 263  8.51-11.50      8    14    18    12    19    14      5      2      3    14    19      6      3      6      3    12 158  11.51-14.50      0      3      2      4    32      7      3      1      0      3    12      9      4      3      1     2 86  14.51-20.50      0      0      2     3    29      0      1      0      1      2    10      2      0      3      0      1 54    >20.50        0      0      0      0      1      0      0      0      0      0      0      1      1      3      0      0 6  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Noble Gases The air dose due to noble gases released in gaseous effluents, 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:
____    TOTAL      348    199    99    91    113    47    45    70    88    106    174    101    90    123    156    262 2112 TOTAL NUMBER OF OBSERVATIONS:  2112 TOTAL NUMBER OF VALID OBSERVATIONS:  2112 TOTAL NUMBER OF MISSING OBSERVATIONS:    0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
: 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,
MEAN WIND SPEED FOR THIS PERIOD:  5.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         
: 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. 27


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A        B        C        D         E        F        G 1.80      4.36      6.01     19.37    15.81    14.39    38.26                               
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 u          = (3.17E-08) i [(Mi) (X/Q)UNIT(Qi)]                                          (4-1)
For beta radiation:
D u          = (3.17E-08) i [(Ni) (X/Q)UNIT(Qi)]                                          (4-2)
Where:
Mi            = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per Ci/m3 from Table 3-3.
Ni            = the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per Ci/m3 from Table 3-3.
(X/Q)UNIT     = the highest calculated annual average dispersion parameter, in sec/m3, 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 l
                        =7.90E-06 from Unit 2
                        =8.91E-06 from Unit 3 D u          = 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 u          = 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 Ci, 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. 27


DISTRIBUTION OF WIND DIRECTION VS STABILITY N    NNE     NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  CALM 
===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 mrems to any organ and,
: b. During any calendar year: Less than or equal to 15 mrems to any organ.
Applicability:     At all times.
Action:
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. 27


A        0      0      1      2     3     4     8      5      3     1      3     0      2      3      2      1     0 B        1      0      3    12    15      4     9    15     7     13      7     1     0      0      2     3     0 C        1      5      8      9    14      5      5    17     19    14    12      3      3      3      4     5      0 D      26    18     28    21    47    12    13    15    29    38    59    28    20    14    15    26      0 E      25    27      9    13    22    19      5      9    17    23    44    35    19    29    19    19      0 F      41    12    21    15      9      1     4      4      8    12    38    25    19    29    34    32      0 G      254    137    29    19      3     2     1     5      5      5    11      9    27    45    80    176      0 TOTAL    348    199    99    91    113    47    45    70    88    106    174    101    90    123    156    262      0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  7/01/2016 TO 12/31/2016                                                         
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) i [k (Rik Wk) (Qi)]                                              (4-3)
Where:
Dou          = 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 Ci, 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 mrem/yr per Ci/m3 and for the food and ground plane pathways in m2 - mrem/yr per Ci/sec, except H-3, which has units of mrem/yr per Ci/m3) at the controlling location. The Riks 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)UNIT, 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 1
                        =7.90E-06 from Unit 2
                        =8.91E-06 from Unit 3
                  = (X/Q)UNIT, 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)UNIT, 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. 27


                                                            *** 2ND SEMI ***
              = (D/Q)UNIT, 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.
STABILITY CLASS  A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
                =3.25E-09 from Unit 1
____    CALM 0    .76- 1.50      0     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      1     0      0      0      0      0      0      0      0      0      0      0      0      0 1  4.51- 5.50      0      0      1      0      1      0      1      1      0      0      0      0      0      0      0      0 4   5.51- 6.50      0      0      0      3     2      4      5      8    15      5      1      2      0     0      0      1 46  6.51- 8.50      1     2      2      2      6    11    15    22    26    18    20    10      5      3     4     1 148  8.51-11.50      0      1      0      1      3    21      1      5    11    16    26    15    12      5      2      3 122  11.51-14.50      0      0      0      0      1     2      0      2      0      3     13      4     2     1     0      0 28  14.51-20.50      0      0      0      1      0      0      0      1      0      2     3      0      0      0      0      0 7    >20.50        1      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
                =3.88E-10 from Unit 2
____    TOTAL        2      3     4      7    13    38    22    39    52    44    63    31    19      9      6     5 357                                                                                                                               
                =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 Ri values were calculated in accordance with the methodologies in NUREG-0133. The following site specific information was used to calculate Ri:
Value The length of the grazing season for milk animals (fs).
Ref. ER-OL, Section 2.1.3.4.3                                                      0.75 The length of the grazing season for meat animals (fs).
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. 27


STABILITY CLASS  B                                                   
===4.3 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 nonfunctional equipment or subsystems and the reason for nonfunctionality,
: b. Action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status, and MAR 2016
: c. Summary description of action(s) taken to prevent a recurrence.
4.3.1 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. 27


SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
4.3.2 Implementation of the Requirement Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      1     0      0      1      0      0      0      0      0      0 2  4.51- 5.50      1      0      0      2     1      1      3      7    11      2      3      0      1      0      1      3 36  5.51- 6.50      0      2      4     2      2      1      3      7    12      8      7      2      1      1      0      0 52  6.51- 8.50      0      2      1      9      8      7      7    11      8    15    15      7      4     0      0      2 96  8.51-11.50      1      0      2      3      8      6      1      0      4      9    20      9      2      2      1      0 68  11.51-14.50      0      0      1      1      4      1      1      1      4      3      8      1      0      0      0      0 25  14.51-20.50      0      0      1      2      2      0      0      1      0      0      2      0      0      0      0      0 8    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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:
____    TOTAL        2      4      9    19    25    16    16    27     39    38    55    19      8      3      2      5 287 
For gamma radiation:
31 day      = D + CD                                                                  (4-4)
For beta radiation:
31 day      = D + CD                                                                  (4-5)
Where:
D            = 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.
CD          = 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 .
CD          = 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 .
When performing the 31 day dose projection using the Gaseous Radioactive Effluent Tracking System (GRETS), D and D 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. 27


STABILITY CLASS  C                                                   
Dose Projection - I-131, I-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:
31dayo        = Do + CDo                                                                    (4-6)
Where:
Do            = the total organ dose due to I-131, I-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 dayo.
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. 27


SPEED (MPH)        N    NNE    NE    ENE     E   ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
TABLE 4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY NUCLIDE     T. BODY      SKIN H-3      0.00E+00   0.00E+00 CR-51      4.66E+06   5.51E+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      0.00E+00    0.00E+00 ZR-95      2.45E+08    2.84E+08 SB-124     5.98E+08    6.90E+08 I-131     1.72E+07    2.09E+07 I-133     2.45E+06    2.98E+06 CS-134     6.86E+09    8.00E+09 CS-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. 27
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0     0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0 1  3.51- 4.50      0      0      1      0      0      3      4      6      6      4      1      0      2     1      2     0 30  4.51- 5.50      1      3      3      5      3      1      4    10    18      8     3      2     1      1      3      2 68  5.51- 6.50      1      1      0     1      2     1      1      4      9      4      7      4      2      0     1     2 40  6.51- 8.50      0      1      4      5     2     2      3      1      7    14    17      3      3      1      3      1 67  8.51-11.50      0      2      4     1     3      2      0      0      1     8    15      0      1      0      0      2 39  11.51-14.50      1     2     1      0    11      0      0      0      1      2     3     1     0      1      0      1 24  14.51-20.50     1      0      0      0      4      1      0      1      0      1      3      0      0      0      0      0 11    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        4      9    13    12    25    10    12    22    42    41    50    10      9      4      9      8 280  ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016   
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  0.00E+00  2.87E+03  2.87E+03    2.87E+03 2.87E+03 2.87E+03  2.87E+03 CR-51  0.00E+00  0.00E+00  4.00E+04    2.39E+04 8.82E+03 5.31E+04  1.01E+07 MN-54  0.00E+00  2.97E+08  5.66E+07    0.00E+00 8.83E+07 0.00E+00  9.09E+08 FE-59 1.14E+08  2.68E+08  1.03E+08    0.00E+00 0.00E+00 7.49E+07  8.93E+08 CO-58  0.00E+00  2.84E+07  6.38E+07    0.00E+00 0.00E+00 0.00E+00  5.76E+08 CO-60  0.00E+00  1.59E+08  3.51E+08    0.00E+00 0.00E+00 0.00E+00  2.99E+09 ZN-65  3.00E+08  9.56E+08  4.32E+08    0.00E+00 6.39E+08 0.00E+00  6.02E+08 SR-89  9.08E+09  0.00E+00  2.61E+08    0.00E+00 0.00E+00 0.00E+00  1.46E+09 SR-90  5.76E+11  0.00E+00  1.41E+11    0.00E+00 0.00E+00 0.00E+00  1.67E+10 ZR-95  1.08E+06  3.47E+05  2.35E+05    0.00E+00 5.45E+05 0.00E+00  1.10E+09 SB-124 9.53E+07  1.80E+06  3.78E+07    2.31E+05 0.00E+00 7.42E+07  2.71E+09 I-131 5.49E+07  7.85E+07  4.50E+07    2.57E+10 1.35E+08 0.00E+00  2.07E+07 I-133 1.39E+06  2.42E+06  7.38E+05    3.56E+08 4.22E+06 0.00E+00  2.17E+06 CS-134 4.44E+09  1.06E+10  8.64E+09    0.00E+00 3.42E+09 1.13E+09  1.85E+08 CS-137 6.06E+09  8.29E+09  5.43E+09    0.00E+00 2.81E+09 9.36E+08  1.60E+08 BA-140 9.43E+07  1.19E+05  6.18E+06    0.00E+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 0.00E+00  4.48E+08 CE-144 3.12E+07  1.30E+07  1.67E+06    0.00E+00 7.73E+06 0.00E+00  1.05E+10 40                          ODCM Rev. 27
                                                          *** 2ND SEMI ***


STABILITY CLASS   D STABILITY BASED ON: DELTA T     BETWEEN 200.0 AND 35.0 FEET
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  0.00E+00  3.36E+03  3.36E+03    3.36E+03 3.36E+03 3.36E+03  3.36E+03 CR-51  0.00E+00  0.00E+00  5.60E+04    3.11E+04 1.23E+04 7.99E+04  9.41E+06 MN-54  0.00E+00  4.41E+08  8.74E+07    0.00E+00 1.31E+08 0.00E+00  9.04E+08 FE-59 1.69E+08  3.94E+08  1.52E+08    0.00E+00 0.00E+00 1.24E+08  9.31E+08 CO-58  0.00E+00  4.16E+07  9.59E+07    0.00E+00 0.00E+00 0.00E+00  5.74E+08 CO-60  0.00E+00  2.42E+08  5.45E+08    0.00E+00 0.00E+00 0.00E+00  3.15E+09 ZN-65  4.11E+08  1.43E+09  6.65E+08    0.00E+00 9.12E+08 0.00E+00  6.04E+08 SR-89  1.43E+10  0.00E+00  4.10E+08    0.00E+00 0.00E+00 0.00E+00  1.70E+09 SR-90  7.30E+11  0.00E+00  1.80E+11    0.00E+00 0.00E+00 0.00E+00  2.05E+10 ZR-95  1.64E+06  5.17E+05  3.56E+05    0.00E+00 7.60E+05 0.00E+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 0.00E+00  1.47E+07 I-133 1.29E+06  2.19E+06  6.68E+05    3.06E+08 3.84E+06 0.00E+00  1.66E+06 CS-134 6.90E+09  1.62E+10  7.53E+09    0.00E+00 5.16E+09 1.97E+09  2.02E+08 CS-137 9.86E+09  1.31E+10  4.57E+09    0.00E+00 4.46E+09 1.73E+09  1.87E+08 BA-140 1.07E+08  1.31E+05  6.88E+06    0.00E+00 4.44E+04 8.80E+04  1.65E+08 CE-141 2.61E+05  1.74E+05  2.00E+04    0.00E+00 8.19E+04 0.00E+00  4.98E+08 CE-144 5.11E+07  2.12E+07  2.75E+06    0.00E+00 1.26E+07 0.00E+00  1.29E+10 41                          ODCM Rev. 27


WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT:   .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET
TABLE 4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR NUCLIDES BONE      LIVER    T.BODY      THYROID  KIDNEY    LUNG      GI-LLI H-3  0.00E+00  5.23E+03  5.23E+03    5.23E+03 5.23E+03 5.23E+03  5.23E+03 CR-51  0.00E+00  0.00E+00  1.08E+05    6.02E+04 1.64E+04 1.10E+05  5.75E+06 MN-54  0.00E+00  6.49E+08  1.73E+08    0.00E+00 1.82E+08 0.00E+00  5.45E+08 FE-59  3.79E+08  6.13E+08  3.05E+08    0.00E+00 0.00E+00 1.78E+08  6.38E+08 CO-58  0.00E+00  6.21E+07  1.90E+08    0.00E+00 0.00E+00 0.00E+00  3.62E+08 CO-60  0.00E+00  3.70E+08  1.09E+09    0.00E+00 0.00E+00 0.00E+00  2.05E+09 ZN-65  7.93E+08  2.11E+09  1.31E+09    0.00E+00 1.33E+09 0.00E+00  3.71E+08 SR-89  3.44E+10  0.00E+00  9.83E+08    0.00E+00 0.00E+00 0.00E+00  1.33E+09 SR-90  1.22E+12  0.00E+00  3.09E+11    0.00E+00 0.00E+00 0.00E+00  1.64E+10 ZR-95  3.72E+06  8.17E+05  7.27E+05    0.00E+00 1.17E+06 0.00E+00  8.52E+08 SB-124  3.38E+08  4.39E+06  1.19E+08    7.47E+05 0.00E+00 1.88E+08  2.12E+09 I-131  9.95E+07  1.00E+08  5.68E+07    3.31E+10 1.64E+08 0.00E+00  8.90E+06 I-133  2.36E+06  2.91E+06  1.10E+06    5.41E+08 4.85E+06 0.00E+00  1.17E+06 CS-134  1.57E+10  2.57E+10  5.43E+09    0.00E+00 7.98E+09 2.86E+09 1.39E+08 CS-137 2.34E+10  2.24E+10  3.31E+09    0.00E+00 7.31E+09 2.63E+09 1.40E+08 BA-140  2.20E+08   1.93E+05  1.28E+07    0.00E+00 6.27E+04 1.15E+05  1.11E+08 CE-141  6.15E+05  3.07E+05  4.55E+04    0.00E+00 1.34E+05 0.00E+00  3.83E+08 CE-144  1.24E+08  3.89E+07  6.62E+06    0.00E+00 2.15E+07 0.00E+00  1.01E+10 42                          ODCM Rev. 27


SPEED (MPH)        N   NNE     NE   ENE     E   ESE    SE   SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
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  0.00E+00  4.33E+02  4.33E+02   4.33E+02 4.33E+02 4.33E+02  4.33E+02 CR-51  0.00E+00  0.00E+00  3.44E+02   2.06E+02 7.58E+01 4.57E+02 8.65E+04 MN-54 0.00E+00  2.71E+06  5.18E+05   0.00E+00 8.08E+05 0.00E+00  8.31E+06 FE-59 2.60E+07  6.11E+07  2.34E+07    0.00E+00 0.00E+00 1.71E+07  2.04E+08 CO-58  0.00E+00  2.84E+06  6.36E+06    0.00E+00 0.00E+00 0.00E+00  5.75E+07 CO-60  0.00E+00  2.61E+07  5.76E+07    0.00E+00 0.00E+00 0.00E+00  4.90E+08 ZN-65  9.97E+07  3.17E+08  1.43E+08    0.00E+00 2.12E+08 0.00E+00  2.00E+08 SR-89  3.41E+07  0.00E+00  9.79E+05    0.00E+00 0.00E+00 0.00E+00  5.47E+06 SR-90  4.43E+09  0.00E+00  1.09E+09    0.00E+00 0.00E+00 0.00E+00  1.28E+08 ZR-95  2.68E+05  8.58E+04  5.81E+04    0.00E+00 1.35E+05 0.00E+00  2.72E+08 SB-124 2.67E+06  5.05E+04  1.06E+06    6.48E+03 0.00E+00 2.08E+06  7.59E+07 I-131 1.36E+05   1.94E+05  1.11E+05    6.37E+07 3.33E+05 0.00E+00  5.13E+04 I-133 4.56E-03  7.94E-03  2.42E-03    1.17E+00 1.39E-02 0.00E+00  7.14E-03 CS-134 2.17E+08  5.17E+08  4.23E+08    0.00E+00 1.67E+08 5.56E+07  9.05E+06 CS-137 3.11E+08   4.25E+08  2.78E+08    0.00E+00 1.44E+08 4.79E+07  8.22E+06 BA-140 4.35E+05  5.46E+02  2.85E+04    0.00E+00 1.86E+02 3.13E+02  8.95E+05 CE-141 8.87E+02  6.00E+02 6.80E+01    0.00E+00 2.79E+02 0.00E+00 2.29E+06 CE-144 4.23E+05  1.77E+05  2.27E+04    0.00E+00 1.05E+05 0.00E+00  1.43E+08 43                          ODCM Rev. 27
____    CALM 0    .76- 1.50      0     0     0     0     0     0     0     0     0     0     0     0     0     0     0     0 0   1.51- 2.50      3      2      2      4      2      0     1     3      2      0     6      3      1      3      3      3 38  2.51- 3.50    12      3      5     6     3      2     1     7    11    14      8      8    14    10      7      9 120   3.51- 4.50      8      6      9      6      3      4      2     5    21    16    12      3      3      7     5    11 121  4.51- 5.50      3      4     7      5     6      3      4      4      9     11    13    10      5      3     0      7 94   5.51- 6.50      4      3      5      3      0     1     0      2      8     11    13    10      3      2      2      1 68  6.51- 8.50      7      5     3      4      5      7      4      2     11    11    26      7      5      1     5      3 106  8.51-11.50      3      5      8      6     11      5      3      0      4    20    30    10      4      3      2      2 116 11.51-14.50      1      7      4      2     31      7      2      2      1      2    29      7      2      0     0      0 97 14.51-20.50      0      3      1     2     29      1      4      3      2      1    24      3      1      0     1     1 76    >20.50        0     0      0      0      1     1      0      1      0      0      0      0      0      0      0      0 3  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        41    38    44    38    91    31    21    29    69    86    161    61    38    29    25    37 839 


STABILITY CLASS   E                                                   
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  0.00E+00  2.58E+02  2.58E+02    2.58E+02 2.58E+02 2.58E+02  2.58E+02 CR-51  0.00E+00  0.00E+00  2.75E+02    1.53E+02 6.03E+01 3.93E+02  4.62E+04 MN-54  0.00E+00  2.07E+06  4.11E+05    0.00E+00 6.18E+05 0.00E+00  4.25E+06 FE-59 2.08E+07  4.85E+07  1.87E+07    0.00E+00 0.00E+00 1.53E+07  1.15E+08 CO-58  0.00E+00  2.19E+06  5.04E+06    0.00E+00 0.00E+00 0.00E+00  3.02E+07 CO-60  0.00E+00  2.03E+07  4.56E+07    0.00E+00 0.00E+00 0.00E+00  2.64E+08 ZN-65  7.01E+07  2.43E+08  1.14E+08    0.00E+00 1.56E+08 0.00E+00  1.03E+08 SR-89  2.88E+07  0.00E+00  8.24E+05    0.00E+00 0.00E+00 0.00E+00  3.43E+06 SR-90  2.87E+09  0.00E+00  7.08E+08    0.00E+00 0.00E+00 0.00E+00  8.05E+07 ZR-95  2.14E+05  6.76E+04  4.65E+04    0.00E+00 9.93E+04 0.00E+00  1.56E+08 SB-124 2.18E+06  4.02E+04  8.52E+05    4.95E+03 0.00E+00 1.91E+06  4.40E+07 I-131 1.13E+05  1.58E+05  8.49E+04    4.61E+07 2.72E+05 0.00E+00  3.13E+04 I-133 3.82E-03  6.48E-03  1.98E-03    9.04E-01 1.14E-02 0.00E+00  4.90E-03 CS-134 1.73E+08  4.07E+08  1.89E+08    0.00E+00 1.29E+08 4.94E+07  5.06E+06 CS-137 2.58E+08  3.43E+08  1.20E+08    0.00E+00 1.17E+08 4.54E+07  4.88E+06 BA-140 3.59E+05  4.40E+02  2.31E+04    0.00E+00 1.49E+02 2.96E+02  5.54E+05 CE-141 7.45E+02  4.97E+02  5.71E+01    0.00E+00 2.34E+02 0.00E+00  1.42E+06 CE-144 3.56E+05  1.47E+05  1.91E+04    0.00E+00 8.80E+04 0.00E+00  8.96E+07 44                          ODCM Rev. 27


SPEED (MPH)        N    NNE    NE    ENE     E   ESE     SE   SSE     S   SSW    SW    WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
TABLE 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILD RECEPTOR NUCLIDES  BONE     LIVER   T.BODY     THYROID  KIDNEY   LUNG     GI-LLI H-3  0.00E+00  3.12E+02  3.12E+02   3.12E+02 3.12E+02 3.12E+02  3.12E+02 CR-51 0.00E+00 0.00E+00  4.29E+02   2.38E+02 6.51E+01 4.35E+02  2.28E+04 MN-54  0.00E+00  2.37E+06  6.31E+05    0.00E+00 6.64E+05 0.00E+00  1.99E+06 FE-59  3.68E+07  5.96E+07  2.97E+07    0.00E+00 0.00E+00 1.73E+07  6.20E+07 CO-58  0.00E+00  2.55E+06  7.82E+06    0.00E+00 0.00E+00 0.00E+00  1.49E+07 CO-60  0.00E+00  2.40E+07  7.09E+07    0.00E+00 0.00E+00 0.00E+00  1.33E+08 ZN-65  1.05E+08  2.80E+08  1.74E+08    0.00E+00 1.77E+08 0.00E+00  4.92E+07 SR-89  5.45E+07  0.00E+00  1.56E+06    0.00E+00 0.00E+00 0.00E+00  2.11E+06 SR-90  3.70E+09  0.00E+00  9.39E+08    0.00E+00 0.00E+00 0.00E+00  4.99E+07 ZR-95  3.81E+05  8.36E+04  7.45E+04    0.00E+00 1.20E+05 0.00E+00  8.73E+07 SB-124  3.95E+06  5.12E+04  1.38E+06    8.72E+03 0.00E+00 2.19E+06  2.47E+07 I-131  2.09E+05  2.11E+05  1.20E+05    6.96E+07 3.46E+05 0.00E+00  1.87E+04 I-133  7.09E-03  8.77E-03  3.32E-03    1.63E+00 1.46E-02 0.00E+00  3.53E-03 CS-134  3.05E+08  5.00E+08  1.06E+08    0.00E+00 1.55E+08 5.56E+07  2.70E+06 CS-137  4.75E+08  4.55E+08  6.71E+07    0.00E+00 1.48E+08 5.33E+07  2.85E+06 BA-140 6.63E+05  5.81E+02  3.87E+04    0.00E+00 1.89E+02 3.46E+02  3.36E+05 CE-141  1.40E+03  6.99E+02  1.04E+02    0.00E+00 3.07E+02 0.00E+00  8.72E+05 CE-144  6.72E+05  2.11E+05  3.58E+04    0.00E+00 1.17E+05 0.00E+00  5.49E+07 45                           ODCM Rev. 27
____    CALM 0    .76- 1.50      0     0     0     0     0     0      0      0      2     0     0     0     0     0     0     0 2  1.51- 2.50      7      5      1     1     2      2      1      1      4     3      7      5     6    15      6      6 72  2.51- 3.50    10      3      3      3      1      4      0     1      5      3      7      5      5      8    10      9 77  3.51- 4.50    12    10      2      3     3      1     0     1      6      5      9    13      8     6      9      6 94  4.51- 5.50      6      7      4      3      1     2     2     3      4    11    20    13      3      1      5      6 91  5.51- 6.50      9      5      8      4      1     4      0      4      4    16    13    10      6     3     4      1 92  6.51- 8.50      7      8      7      8      9      9      3     7      4    23    45    10      7      2      3     3 155  8.51-11.50      4      4      3    13    20    14      5     5      7    28    64    18      1     5     2     5 198  11.51-14.50      2      1      1      3    27      8      4     1      0     10    34    12      1     2     1      1 108 14.51-20.50      3     2      2      0     24      4      0      0      1     3     15      1     0     3     0     1 59    >20.50        0     0      0      0      0      0      0      0      0      0      0      1     1      3      0      0 5 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        60    45     31    38    88    48    15    23    37    102    214    88    38    48    40    38 953                                                                                                                               


STABILITY CLASS   F                                                   
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  0.00E+00  1.02E+03  1.02E+03    1.02E+03 1.02E+03 1.02E+03  1.02E+03 CR-51  0.00E+00  0.00E+00  8.28E+03    4.95E+03 1.82E+03 1.10E+04  2.08E+06 MN-54  0.00E+00  3.99E+06  7.61E+05    0.00E+00 1.19E+06 0.00E+00  1.22E+07 FE-59 9.69E+06  2.28E+07  8.73E+06    0.00E+00 0.00E+00 6.36E+06  7.59E+07 CO-58  0.00E+00  1.74E+06  3.90E+06    0.00E+00 0.00E+00 0.00E+00  3.53E+07 CO-60  0.00E+00  8.41E+06  1.85E+07    0.00E+00 0.00E+00 0.00E+00  1.58E+08 ZN-65  6.34E+08  2.02E+09  9.12E+08    0.00E+00 1.35E+09 0.00E+00  1.27E+09 SR-89  4.90E+08  0.00E+00  1.41E+07    0.00E+00 0.00E+00 0.00E+00  7.86E+07 SR-90  2.43E+10  0.00E+00  5.96E+09    0.00E+00 0.00E+00 0.00E+00  7.02E+08 ZR-95  3.39E+02  1.09E+02  7.37E+01    0.00E+00 1.71E+02 0.00E+00  3.45E+05 SB-124 9.11E+06  1.72E+05  3.61E+06    2.21E+04 0.00E+00 7.09E+06  2.59E+08 I-131 7.77E+07  1.11E+08  6.37E+07    3.64E+10 1.91E+08 0.00E+00  2.93E+07 I-133 1.02E+06  1.77E+06  5.39E+05    2.60E+08 3.08E+06 0.00E+00  1.59E+06 CS-134 2.83E+09  6.73E+09  5.50E+09    0.00E+00 2.18E+09 7.23E+08  1.18E+08 CS-137 3.83E+09  5.24E+09  3.43E+09    0.00E+00 1.78E+09 5.91E+08  1.01E+08 BA-140 7.11E+06  8.93E+03  4.66E+05    0.00E+00 3.04E+03 5.11E+03  1.46E+07 CE-141 8.73E+03  5.90E+03  6.70E+02    0.00E+00 2.74E+03 0.00E+00  2.26E+07 CE-144 1.01E+06  4.21E+05  5.41E+04    0.00E+00 2.50E+05 0.00E+00  3.41E+08 46                          ODCM Rev. 27


SPEED (MPH)        N    NNE     NE    ENE      E    ESE     SE   SSE     S   SSW    SW   WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
TABLE 4-9 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEEN RECEPTOR NUCLIDE  BONE      LIVER     T.BODY     THYROID  KIDNEY   LUNG     GI-LLI H-3  0.00E+00  1.33E+03  1.33E+03   1.33E+03 1.33E+03 1.33E+03  1.33E+03 CR-51  0.00E+00  0.00E+00  1.45E+04   8.03E+03 3.17E+03 2.06E+04 2.43E+06 MN-54 0.00E+00  6.64E+06  1.32E+06   0.00E+00 1.98E+06 0.00E+00  1.36E+07 FE-59 1.69E+07  3.95E+07  1.52E+07    0.00E+00 0.00E+00 1.24E+07  9.33E+07 CO-58  0.00E+00  2.93E+06  6.76E+06    0.00E+00 0.00E+00 0.00E+00  4.04E+07 CO-60  0.00E+00  1.42E+07  3.21E+07    0.00E+00 0.00E+00 0.00E+00  1.86E+08 ZN-65  9.74E+08  3.38E+09   1.58E+09    0.00E+00 2.17E+09 0.00E+00  1.43E+09 SR-89  9.03E+08  0.00E+00  2.59E+07    0.00E+00 0.00E+00 0.00E+00  1.08E+08 SR-90  3.43E+10  0.00E+00  8.48E+09    0.00E+00 0.00E+00 0.00E+00  9.64E+08 ZR-95  5.94E+02  1.87E+02  1.29E+02    0.00E+00 2.75E+02 0.00E+00  4.32E+05 SB-124 1.62E+07  2.99E+05  6.34E+06    3.69E+04 0.00E+00 1.42E+07  3.27E+08 I-131 1.41E+08  1.98E+08  1.06E+08    5.76E+10 3.40E+08 0.00E+00  3.91E+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   1.16E+10  5.36E+09    0.00E+00 3.67E+09 1.40E+09  1.44E+08 CS-137 6.95E+09  9.24E+09  3.22E+09    0.00E+00 3.15E+09 1.22E+09 1.32E+08 BA-140 1.28E+07  1.57E+04  8.27E+05    0.00E+00 5.33E+03 1.06E+04  1.98E+07 CE-141 1.60E+04  1.07E+04  1.23E+03    0.00E+00 5.03E+03 0.00E+00  3.06E+07 CE-144 1.86E+06  7.68E+05  9.97E+04    0.00E+00 4.59E+05 0.00E+00 4.67E+08 47                           ODCM Rev. 27
____    CALM 0    .76- 1.50      0     0     0     0     0     0     0     1     0     1      0     0     0      0      0      0 2   1.51- 2.50      8      4      7      0     2      1     1      3      1      0     4      8      6    11      9      3 68   2.51- 3.50    16      5      6      3      0     0     2      2      0     4      6      6      7      8      9     9 83  3.51- 4.50    14      6      6      4      1     0     0     0      4      4    10    10    14    13    18    13 117  4.51- 5.50    17      7      6     2      1      0     1     1      5      8    24    10      3     5      8      5 103  5.51- 6.50      6      4      1     1     1      0     1      1      1      5    13      5      4      3     4      9 59  6.51- 8.50    10      3     4     6      0     0      3      0      2     12    31      8      4     3      5      5 96   8.51-11.50      2      5      4      4      0     0      1     1     0     2    11      2      1     4      0      3 40 11.51-14.50      0     1     1     1     2      0      1     0      0      0      0      1     0     0     0      2 9 14.51-20.50      2      0     0      1      4     0      0      0      0      0      0      0      0      0     0      0 7    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      1      0 1 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        75    35    35    22    11      1    10      9    13    36    99    50    39    47     54    49 585 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION


JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016      
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  0.00E+00  2.09E+03  2.09E+03    2.09E+03 2.09E+03 2.09E+03  2.09E+03 CR-51  0.00E+00  0.00E+00  2.95E+04    1.64E+04 4.47E+03 2.99E+04  1.56E+06 MN-54  0.00E+00  9.94E+06  2.65E+06    0.00E+00 2.79E+06 0.00E+00  8.34E+06 FE-59  3.92E+07  6.35E+07  3.16E+07    0.00E+00 0.00E+00 1.84E+07  6.61E+07 CO-58  0.00E+00  4.48E+06  1.37E+07    0.00E+00 0.00E+00 0.00E+00  2.61E+07 CO-60  0.00E+00  2.21E+07  6.52E+07    0.00E+00 0.00E+00 0.00E+00  1.23E+08 ZN-65  1.91E+09  5.09E+09  3.17E+09    0.00E+00 3.21E+09 0.00E+00  8.95E+08 SR-89  2.23E+09  0.00E+00  6.38E+07    0.00E+00 0.00E+00 0.00E+00  8.65E+07 SR-90  5.80E+10  0.00E+00  1.47E+10    0.00E+00 0.00E+00 0.00E+00 7.81E+08 ZR-95  1.38E+03  3.03E+02  2.70E+02    0.00E+00 4.34E+02 0.00E+00  3.16E+05 SB-124  3.84E+07  4.99E+05  1.35E+07    8.49E+04 0.00E+00 2.13E+07  2.41E+08 I-131  3.42E+08  3.44E+08  1.96E+08    1.14E+11 5.65E+08 0.00E+00  3.06E+07 I-133  4.51E+06  5.57E+06  2.11E+06    1.04E+09 9.29E+06 0.00E+00  2.25E+06 CS-134  1.13E+10  1.86E+10  3.92E+09    0.00E+00 5.76E+09 2.07E+09  1.00E+08 CS-137  1.67E+10  1.60E+10  2.36E+09    0.00E+00 5.22E+09 1.88E+09  1.00E+08 BA-140  3.10E+07  2.71E+04  1.81E+06    0.00E+00 8.83E+03 1.62E+04  1.57E+07 CE-141  3.94E+04  1.97E+04  2.92E+03     0.00E+00 8.62E+03 0.00E+00  2.45E+07 CE-144  4.57E+06  1.43E+06  2.44E+05    0.00E+00 7.94E+05 0.00E+00  3.74E+08 48                          ODCM Rev. 27
                                                          *** 2ND SEMI ***


STABILITY CLASS   G STABILITY BASED ON: DELTA T     BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET
TABLE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR NUCLIDE  BONE      LIVER    T.BODY    THYROID   KIDNEY    LUNG     GI-LLI H-3  0.00E+00  3.18E+03  3.18E+03    3.18E+03 3.18E+03 3.18E+03  3.18E+03 CR-51  0.00E+00  0.00E+00  4.67E+04    3.05E+04 6.66E+03 5.93E+04  1.36E+06 MN-54  0.00E+00  1.85E+07  4.19E+06    0.00E+00 4.10E+06 0.00E+00  6.79E+06 FE-59 7.32E+07  1.28E+08  5.04E+07    0.00E+00 0.00E+00 3.78E+07  6.11E+07 CO-58  0.00E+00  8.96E+06  2.23E+07    0.00E+00 0.00E+00 0.00E+00  2.23E+07 CO-60  0.00E+00  4.52E+07  1.07E+08    0.00E+00 0.00E+00 0.00E+00  1.07E+08 ZN-65  2.57E+09  8.81E+09  4.06E+09    0.00E+00 4.27E+09 0.00E+00  7.44E+09 SR-89  4.25E+09  0.00E+00  1.22E+08    0.00E+00 0.00E+00 0.00E+00  8.74E+07 SR-90  6.31E+10  0.00E+00  1.61E+10    0.00E+00 0.00E+00 0.00E+00  7.88E+08 ZR-95  2.45E+03  5.97E+02  4.23E+02    0.00E+00 6.43E+02 0.00E+00  2.97E+05 SB-124 7.41E+07  1.09E+06 2.30E+07    1.97E+05 0.00E+00 4.64E+07  2.29E+08 I-131 7.14E+08  8.42E+08 3.70E+08    2.77E+11 9.83E+08 0.00E+00 3.00E+07 I-133 9.52E+06  1.39E+07 4.06E+06    2.52E+09 1.63E+07 0.00E+00  2.35E+06 CS-134 1.82E+10  3.40E+10  3.44E+09    0.00E+00 8.76E+09 3.59E+09  9.24E+07 CS-137 2.67E+10  3.13E+10  2.22E+09    0.00E+00 8.39E+09 3.40E+09  9.78E+07 BA-140 6.37E+07  6.37E+04  3.28E+06    0.00E+00 1.51E+04 3.91E+04  1.57E+07 CE-141 7.81E+04  4.77E+04  5.61E+03    0.00E+00 1.47E+04 0.00E+00  2.46E+07 CE-144 6.55E+06  2.68E+06  3.67E+05    0.00E+00 1.08E+06 0.00E+00  3.76E+08 49                          ODCM Rev. 27


WIND THRESHOLD AT:   .75 MPH  
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  0.00E+00  1.26E+03  1.26E+03    1.26E+03 1.26E+03 1.26E+03  1.26E+03 CR-51  0.00E+00  0.00E+00  1.00E+02    5.95E+01 2.28E+01 1.44E+04  3.32E+03 MN-54  0.00E+00  3.96E+04  6.30E+03    0.00E+00 9.84E+03 1.40E+06  7.74E+04 FE-59 1.18E+04  2.78E+04  1.06E+04    0.00E+00 0.00E+00 1.02E+06  1.88E+05 CO-58  0.00E+00   1.58E+03 2.07E+03    0.00E+00 0.00E+00 9.28E+05  1.06E+05 CO-60  0.00E+00  1.15E+04  1.48E+04    0.00E+00 0.00E+00 5.97E+06  2.85E+05 ZN-65  3.24E+04  1.03E+05  4.66E+04    0.00E+00 6.90E+04 8.64E+05  5.34E+04 SR-89  3.04E+05  0.00E+00  8.72E+03    0.00E+00 0.00E+00 1.40E+06  3.50E+05 SR-90  9.92E+07  0.00E+00  6.10E+06    0.00E+00 0.00E+00 9.60E+06  7.22E+05 ZR-95  1.07E+05  3.44E+04  2.33E+04    0.00E+00 5.42E+04 1.77E+06  1.50E+05 SB-124 3.12E+04  5.89E+02  1.24E+04    7.55E+01 0.00E+00 2.48E+06  4.06E+05 I-131 2.52E+04  3.58E+04  2.05E+04    1.19E+07 6.13E+04 0.00E+00  6.28E+03 I-133 8.64E+03  1.48E+04  4.52E+03    2.15E+06 2.58E+04 0.00E+00  8.88E+03 CS-134 3.73E+05  8.48E+05  7.28E+05    0.00E+00 2.87E+05 9.76E+04  1.04E+04 CS-137 4.78E+05  6.21E+05  4.28E+05    0.00E+00 2.22E+05 7.52E+04  8.40E+03 BA-140 3.90E+04  4.90E+01  2.57E+03    0.00E+00 1.67E+01 1.27E+06  2.18E+05 CE-141 1.99E+04  1.35E+04  1.53E+03    0.00E+00 6.26E+03 3.62E+05  1.20E+05 CE-144 3.43E+06  1.43E+06  1.84E+05    0.00E+00 8.48E+05 7.78E+06  8.16E+05 50                          ODCM Rev. 27


JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE     NE   ENE     E   ESE    SE   SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
TABLE 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - TEEN RECEPTOR NUCLIDE  BONE      LIVER    T.BODY     THYROID  KIDNEY   LUNG     GI-LLI H-3  0.00E+00  1.27E+03  1.27E+03   1.27E+03 1.27E+03 1.27E+03  1.27E+03 CR-51  0.00E+00  0.00E+00  1.35E+02   7.50E+01 3.07E+01 2.10E+04 3.00E+03 MN-54 0.00E+00  5.11E+04  8.40E+03   0.00E+00 1.27E+04 1.98E+06  6.68E+04 FE-59 1.59E+04  3.70E+04  1.43E+04    0.00E+00 0.00E+00 1.53E+06  1.78E+05 CO-58  0.00E+00  2.07E+03  2.78E+03    0.00E+00 0.00E+00 1.34E+06  9.52E+04 CO-60  0.00E+00  1.51E+04  1.98E+04    0.00E+00 0.00E+00 8.72E+06  2.59E+05 ZN-65  3.86E+04  1.34E+05  6.24E+04    0.00E+00 8.64E+04 1.24E+06  4.66E+04 SR-89  4.34E+05  0.00E+00  1.25E+04    0.00E+00 0.00E+00 2.42E+06  3.71E+05 SR-90  1.08E+08  0.00E+00  6.68E+06    0.00E+00 0.00E+00 1.65E+07  7.65E+05 ZR-95  1.46E+05  4.58E+04  3.15E+04    0.00E+00 6.74E+04 2.69E+06  1.49E+05 SB-124 4.30E+04  7.94E+02  1.68E+04    9.76E+01 0.00E+00 3.85E+06  3.98E+05 I-131 3.54E+04   4.91E+04  2.64E+04    1.46E+07 8.40E+04 0.00E+00  6.49E+03 I-133 1.22E+04  2.05E+04  6.22E+03    2.92E+06 3.59E+04 0.00E+00  1.03E+04 CS-134 5.02E+05  1.13E+06   5.49E+05    0.00E+00 3.75E+05 1.46E+05  9.76E+03 CS-137 6.70E+05   8.48E+05  3.11E+05    0.00E+00 3.04E+05 1.21E+05  8.48E+03 BA-140 5.47E+04  6.70E+01  3.52E+03    0.00E+00 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04  1.90E+04  2.17E+03    0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06  2.02E+06  2.62E+05    0.00E+00 1.21E+06 1.34E+07 8.64E+05 51                          ODCM Rev. 27
____    CALM 0    .76- 1.50      0     0     0     0      0      0      0      0      0      0      0      0      2     0     0     2 4  1.51- 2.50    24    12      3      2      1     1     1      1      2      2      2      5      8     15    21    23 123  2.51- 3.50    61    22      4     5      0     1     0     3     1     1     7     4     7    26    41    63 246   3.51- 4.50    103    42      6      7     2      1     0     1      3     1      3     1    12      7    21    60 270   4.51- 5.50    65    42      6      1     0     0      0      0      1     0      2     2     1     1     7    29 157   5.51- 6.50    30    19      9      2      0      0      0      0      1      1      1      2      0      0      4    12 81   6.51- 8.50    37    25      2      2      0     0      0      0      0      1     2      0      0      0      1    15 85  8.51-11.50      9      8      5      1      0     0      0      0      0      0      0      0      0      0      0      2 25 11.51-14.50      1     0      0      2     0     0      0      0      0      0      0      0      0      0      0      0 3 14.51-20.50      0      0      0      0      0      0      0      0     0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      1     0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL      330    170    35    22      3      3      1      5      8     6    17    14    30    49    96    206 995 STABILITY CLASS  ALL                                                 


SPEED (MPH)        N   NNE     NE   ENE     E   ESE    SE   SSE      S    SSW    SW    WSW      W    WNW    NW    NNW T OTAL ___________                                                                                                                  _
TABLE 4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILD RECEPTOR NUCLIDE  BONE      LIVER   T.BODY     THYROID  KIDNEY   LUNG     GI-LLI H-3  0.00E+00  1.12E+03  1.12E+03   1.12E+03 1.12E+03 1.12E+03  1.12E+03 CR-51  0.00E+00  0.00E+00  1.54E+02   8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 0.00E+00  4.29E+04  9.51E+03   0.00E+00 1.00E+04 1.58E+06  2.29E+04 FE-59 2.07E+04  3.34E+04  1.67E+04    0.00E+00 0.00E+00 1.27E+06  7.07E+04 CO-58  0.00E+00  1.77E+03  3.16E+03    0.00E+00 0.00E+00 1.11E+06  3.44E+04 CO-60  0.00E+00  1.31E+04  2.26E+04    0.00E+00 0.00E+00 7.07E+06  9.62E+04 ZN-65  4.26E+04   1.13E+05  7.03E+04    0.00E+00 7.14E+04 9.95E+05  1.63E+04 SR-89  5.99E+05  0.00E+00  1.72E+04    0.00E+00 0.00E+00 2.16E+06  1.67E+05 SR-90  1.01E+08   0.00E+00  6.44E+06    0.00E+00 0.00E+00 1.48E+07  3.43E+05 ZR-95  1.90E+05   4.18E+04  3.70E+04    0.00E+00 5.96E+04 2.23E+06  6.11E+04 SB-124 5.74E+04   7.40E+02  2.00E+04   1.26E+02 0.00E+00 3.24E+06 1.64E+05 I-131 4.81E+04  4.81E+04  2.73E+04    1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-133 1.66E+04  2.03E+04  7.70E+03    3.85E+06 3.38E+04 0.00E+00  5.48E+03 CS-134 6.51E+05  1.01E+06  2.25E+05    0.00E+00 3.30E+05 1.21E+05  3.85E+03 CS-137 9.07E+05  8.25E+05  1.28E+05    0.00E+00 2.82E+05 1.04E+05  3.62E+03 BA-140 7.40E+04  6.48E+01  4.33E+03    0.00E+00 2.11E+01 1.74E+06  1.02E+05 CE-141 3.92E+04  1.95E+04  2.90E+03    0.00E+00 8.55E+03 5.44E+05  5.66E+04 CE-144 6.77E+06  2.12E+06 3.61E+05   0.00E+00 1.17E+06 1.20E+07 3.89E+05 52                          ODCM Rev. 27
____    CALM 0    .76- 1.50      0     0     0     0     0     0     0      1     2     1      0     0     2      0      0      2 8   1.51- 2.50    42    23    13      7     7      4      4      8      9     5     19    21    21    44    39    35 301   2.51- 3.50    99    33    18    17      4      7      3    13    17    22    29    23    33    52    67    90 527   3.51- 4.50    137    64    25    20      9      9      7    13    40    31    35    27    39    34    55    90 635   4.51- 5.50    93    63    27    18    13      7    15    26    48    40    65    37    14    11    24    52 553  5.51- 6.50    50    34    27    16      8    11    10    26    50    50    55    35    16      9    15    26 438  6.51- 8.50    62    46    23    36    30    36    35    43    58    94    156    45    28    10    21    30 753   8.51-11.50    19    25    26    29    45    48    11    11    27    83   166    54    21    19      7    17 608 11.51-14.50      5    11      8      9    76    18      8      6      6    20    87    26      5      4     1     4 294 14.51-20.50      6      5     4      6     63      6      4      6      3      7    47      4      1     3      1      2 168    >20.50        1      0     0      0      1     1     0     1     0     0      0      1     1     3     2     0 11 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL      514   304    171    158    256    147    97    154    260    353    659    273    181    189    232    348 4296 TOTAL NUMBER OF OBSERVATIONS: 4296 TOTAL NUMBER OF VALID OBSERVATIONS:  4296 TOTAL NUMBER OF MISSING OBSERVATIONS:    0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %
MEAN WIND SPEED FOR THIS PERIOD:  6.7 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A        B        C        D        E        F        G 8.31      6.68      6.52    19.53    22.18    13.62    23.16                               
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  0.00E+00  6.47E+02  6.47E+02    6.47E+02 6.47E+02 6.47E+02  6.47E+02 CR-51  0.00E+00  0.00E+00  8.95E+01    5.75E+01 1.32E+01 1.28E+04  3.57E+02 MN-54  0.00E+00  2.53E+04  4.98E+03    0.00E+00 4.98E+03 1.00E+06  7.06E+03 FE-59 1.36E+04  2.35E+04  9.48E+03    0.00E+00 0.00E+00 1.02E+06  2.48E+04 CO-58  0.00E+00  1.22E+03  1.82E+03    0.00E+00 0.00E+00 7.77E+05  1.11E+04 CO-60  0.00E+00  8.02E+03  1.18E+04    0.00E+00 0.00E+00 4.51E+06  3.19E+04 ZN-65  1.93E+04  6.26E+04  3.11E+04    0.00E+00 3.25E+04 6.47E+05  5.14E+04 SR-89  3.98E+05  0.00E+00  1.14E+04    0.00E+00 0.00E+00 2.03E+06  6.40E+04 SR-90  4.09E+07  0.00E+00  2.59E+06    0.00E+00 0.00E+00 1.12E+07  1.31E+05 ZR-95  1.15E+05  2.79E+04  2.03E+04    0.00E+00 3.11E+04 1.75E+06  2.17E+04 SB-124 3.79E+04  5.56E+02  1.20E+04    1.01E+02 0.00E+00 2.65E+06  5.91E+04 I-131 3.79E+04  4.44E+04  1.96E+04    1.48E+07 5.18E+04 0.00E+00  1.06E+03 I-133 1.32E+04  1.92E+04  5.60E+03    3.56E+06 2.24E+04 0.00E+00  2.16E+03 CS-134 3.96E+05  7.03E+05  7.45E+04    0.00E+00 1.90E+05 7.97E+04  1.33E+03 CS-137 5.49E+05  6.12E+05  4.55E+04    0.00E+00 1.72E+05 7.13E+04  1.33E+03 BA-140 5.60E+04  5.60E+01  2.90E+03    0.00E+00 1.34E+01 1.60E+06  3.84E+04 CE-141 2.77E+04  1.67E+04  1.99E+03    0.00E+00 5.25E+03 5.17E+05  2.16E+04 CE-144 3.19E+06  1.21E+06  1.76E+05    0.00E+00 5.38E+05 9.84E+06  1.48E+05 53                          ODCM Rev. 27


DISTRIBUTION OF WIND DIRECTION VS STABILITY N   NNE     NE   ENE      E   ESE     SE   SSE      S   SSW     SW   WSW      W   WNW     NW   NNW  CALM 
TABLE 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT l X/Q        RESIDENCE(b)            D/Q          X/Q      GARDEN(b)        D/Q        X/Q      MILK(b)            D/Q DIRECTION         (Sec/m3)      Dist. Miles          (m-2)      (Sec/m3)    Dist. Miles    (m-2)    (Sec/m3)  Dist. Miles      (m-2)
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 54                    SSE         1.27E-06            4.7          2.61E-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 (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.
ODCM Rev. 27    


A        2      3      4      7    13    38    22    39    52    44    63    31    19      9      6      5      0 B        2      4      9    19    25    16    16    27    39    38    55    19      8      3      2      5      0 C        4      9    13    12    25    10    12    22    42    41    50    10      9      4      9      8      0 D      41    38    44    38    91    31    21    29    69    86    161    61    38    29    25    37      0 E      60    45    31    38    88    48    15    23    37    102    214    88    38    48    40    38      0 F      75    35    35    22    11      1    10      9    13    36    99    50    39    47    54    49      0 G      330    170    35    22      3      3      1      5      8      6    17    14    30    49    96    206      0 TOTAL    514    304    171    158    256    147    97    154    260    353    659    273    181    189    232    348      0 
==References:==
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.


ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO 12/31/2016                                                         
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          X/Q      GARDEN(b)        D/Q        X/Q      MILK(b)            D/Q DIRECTION        (Sec/m3)      Dist. Miles          (m-2)      (Sec/m3)    Dist. Miles    (m-2)    (Sec/m3)  Dist. Miles      (m-2)
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        1.51E-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 55                    SSE        1.34E-06            4.5          2.81E-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)      3.56E-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 (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.
ODCM Rev. 27 


                                                              ***  ANNUAL  ***
==References:==
STABILITY CLASS  A STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      1      0      0      0      0      0      0      0      0      0      0      0      0      0 1  4.51- 5.50      0      0      1      1      2      1      3      2      3      0      1      0      0      0      0      0 14  5.51- 6.50      0      1      0      3      4      4      6    14    28    13      5      2      0      0      0      1 81  6.51- 8.50      1      2      3      6      9    15    21    32    53    28    39    17      9      6      5      1 247  8.51-11.50      1      2      0      5    11    31      1      9    19    35    51    25    22      9      7      5 233  11.51-14.50      1      1      5      1      2      3      4      2      7    17    35    14      6      4      6      3 111  14.51-20.50      0      0      5      4      2      2      0      2      5    14      6      2      2      4      0      4 52    >20.50        1      0      1      0      0      0      0      0      0      2      6      1      0      1      1      0 13  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL        4      6    16    20    30    56    35    61    115    109    143    61    39    24    19    14 752 


STABILITY CLASS  B SPEED (MPH)        N    NNE     NE   ENE      E    ESE     SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
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/m3)      Dist. Miles          (m-2)      (Sec/m3)     Dist. Miles   (m-2)     (Sec/m3)  Dist. Miles      (m-2)
____    CALM 0    .76- 1.50     0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50      0      0      0      0      0      0      0      0      0      0      0      0      0     0      0      0 0  2.51- 3.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  3.51- 4.50      0      0      0      0      0      0      1     0     1     1      1      0      0      0      0      0 4   4.51- 5.50      1     1      1      5      2     2     4    12    23      3     5     1     2     1     2     4 69   5.51- 6.50      1      4      4      4      3     2     5    11    33    18    14      9      3     3      2     0 116  6.51- 8.50      0      4     6     14    11    13     8    16    18    28    29    15    10      2      0      2 176   8.51-11.50      1     1      4      7    11      9      4      2      6    21    32    15     5     3     1     2 124  11.51-14.50      0      1     1      1      5      4      1     2     4     9    17      2     0     2     0      0 49  14.51-20.50      0      0      3     2     3      0      0      1      0     4     6      1      0      0      0      0 20    >20.50       0      0      0      0      0      1      0      0      0      2      0      0      0      1      0      0 4 ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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           3.00E-09     1.48E-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 56                    SSE        1.36E-06            4.4          2.88E-10     1.09E-06          (a)     2.15E-10  1.09E-06      (a)      2.15E-10 S          2.65E-06            4.2           5.25E-10     2.25E-06          4.9     4.06E-10  2.31E-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          1.11E-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 (a) 5-mile value used since there is no pathway located within the sector up to five miles.
____    TOTAL        3     11    19    33    35    31    23    44    85    86    104    43    20    12      5      8 562 STABILITY CLASS  C SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
(b) Controlling locations are discussed in Appendix A.
____    CALM 0    .76- 1.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0  1.51- 2.50     1      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 1   2.51- 3.50      0      0      0      0      0      0      0      0      0      0      1      1      0      1      0      0 3  3.51- 4.50      0      0      1      0      0      3      4      6      9     8      3     2      4      1      2      1 44   4.51- 5.50      3      3      6    10     7     2     7     16    35    19      5      3      2      2     4     5 129   5.51- 6.50      3      3      6      3     3      2      2      7    20    23    14    11      5      2      1      4 109   6.51- 8.50      0      5    12    12      9      5      6     2    15    23    22      8     6     3      4     2 134   8.51-11.50      0      2    10     3      6      6      1     2      4    13    17      2      4      0      0      2 72  11.51-14.50      2      2      2     0    14      0      1      0      1      5     10      1      1      1      0      1 41  14.51-20.50      1      0      0      0      4      1      0      1      0      3     8      0      0      1      0      0 19    >20.50        0      0      0      0      0      0      0      0      0      0      1      0      0      0      0      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
ODCM Rev. 27 
____    TOTAL        10     15    37    28    43    19    21    34    84    94    81    28    22    11    11    15 553 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO 12/31/2016   


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


STABILITY CLASS  D STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET WIND  MEASURED  AT: 35.0 FEET
===4.4 Requirements===
Liquid Effluents 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. 27


WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
5.0    TOTAL DOSE AND DOSE TO PUBLIC ONSITE
____    CALM 0    .76- 1.50      1      0      1      0      0      0      1      0      0      1      0      0      0      0      0      0 4  1.51- 2.50      4      3      4      5      2      1      7      6      5      6    11      5      6      4      4      5 78  2.51- 3.50    26      8      9    10      9      6    11    18    31    34    27    17    19    18      9    18 270  3.51- 4.50    15    15    20    13      5      9      7    11    42    40    29      9    10      8    11    15 259  4.51- 5.50      9    19    18    10      9      6    13    12    21    28    29    16    10      7      1    10 218  5.51- 6.50      6      6    16      9      0      5      1      4    16    22    20    17      5      4      5      3 139  6.51- 8.50    12    10    12    16      8      7      5      3    17    17    37    15    10      3      6      4 182  8.51-11.50      3      8    14      9    19    13      5      3      6    31    41    20    15      5      4      3 199  11.51-14.50      1      7      5      5    36      7      2      3      3    11    42    11      6      3      0      2 144  14.51-20.50      1      5      2      3    35      3      6      3      6      9    37      6      5      6      3      1 131    >20.50        0      0      0      0      1      1      0      2      0      4      2      0      0      0      0      0 10  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
____    TOTAL       78    81    101    80    124    58    58    65    147    203    275    116    86    58    43    61 1634 STABILITY CLASS  E                                                   


SPEED (MPH)         N    NNE     NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===5.1 Requirement===
____    CALM 0    .76- 1.50      0      0      1      1      1      0      0      0      2      0      1      1      0      0      2      0 9  1.51- 2.50    12    10      1      2      5      4     1      4     5      5      9    10      8    19      8      9 112  2.51- 3.50    17      8      4      5     3      5      2      1     5      8    11    13    13    14    23    12 144  3.51- 4.50    15    12      3      5      6      2      0      2    10     11    16    19    11    10    17    11 150  4.51- 5.50    10    11      6      4     2      2      3      3    12    24    28    16      4     3      9      9 146  5.51- 6.50    13    10    14      4      1     4     2     5     8    22    23    15      9      8      7      4 149  6.51- 8.50    11    14    21    12    11    11      6    10    11    39    73    21    21      7      5      7 280  8.51-11.50    10    10      9    19    20    18      8      7    11    44    104    35    15    11      4    13 338  11.51-14.50      6      2     4      7    31    10      7      2      5     27    56    15      2    19    11      5 209  14.51-20.50      4      2      2      0    42      4      0      2     2    11    35      5      5      9      5      4 132    >20.50        0      0      0      0      2      0      0      1      3      0      2      3      1      3      0      0 15  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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.
____    TOTAL        98    79    65    59    124    60    29    37    74    191    358    153    89    103    91    74 1684                                                                                                                               
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. 27


STABILITY CLASS  F                                                   
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, 4.1b, 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) i [(Ki) (X/Q)UNIT (Qi)]                                        (5-1)
Where:
Ki            = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per Ci/m3 from Table 3-3.
Qi            = the integrated release of radionuclide i, in Ci for the previous calendar year.
(X/Q)UNIT      = 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. 27


SPEED (MPH)         N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-131, 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:
____    CALM 0    .76- 1.50      0      0      1      1      0      1      0      1      0      1      0      0      0      0      0      0 5  1.51- 2.50    13      6      7      2      2      2      5      4     3      1     9    13    11    17    14      7 116  2.51- 3.50    25    12      8    10      4     3      5      4     1      7    14    10    17     17    26    22 185  3.51- 4.50    21    10      7      8      2     3      0      0      5    15    20    16    19    20    28    25 199  4.51- 5.50    22    12    12      3      2     1      5      1      6    17    36    23      9    10    14    13 186  5.51- 6.50    10    13      9      4      2     1      4     2      2    17    26    16    11      8      8    19 152  6.51- 8.50    16     11    11    10      1      2      4     2      4     32    61    22    10    10    14    13 223  8.51-11.50      5      6      6      6      0      1     1      1      1    20    31      9      5    16      9    12 129  11.51-14.50      0      1      1      1      2     0      1      0      0      1      0      1      1      0      0      4 13  14.51-20.50     2      0      0      2      5      0      0      0      0      0      1      0      0      0      0      0 10    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      1      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
Do          = (3.17E-08) i [k(RikWk) (Qi)]                                              (5-2)
____    TOTAL      114    71    62    47    20    14    25    15    22    111    198    110    83    98    114    115 1219 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD  1/01/2016 TO 12/31/2016   
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 Ci, 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 Ci/m3 and for the food and ground plane pathways in m2-mrem/yr per Ci/sec) at the controlling location. The Riks 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)UNIT, 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 1
                  =2.19E-06 from Unit 2
                  =2.31E-06 from Unit 3
              = (D/Q)UNIT, 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 1
                  =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. 27


                                                        ***  ANNUAL  ***
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.
STABILITY CLASS  G STABILITY BASED ON: DELTA T      BETWEEN 200.0 AND  35.0 FEET
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.
61                                        ODCM Rev. 27


WIND  MEASURED  AT:  35.0 FEET WIND THRESHOLD  AT:  .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET
6.0   RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)


SPEED (MPH)        N   NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
===6.1 Requirement===
____    CALM 0    .76- 1.50      0      1      0      0      0      0      1      0      0      0      0      0      2     1      2     2 9  1.51- 2.50    39    17      6     3      5      2     2      1     2     4      3    10    17    25    39    45 220  2.51- 3.50    131    34    13    13      5    11      5      7      3      6    13      6    15    54    82    119 517  3.51- 4.50    196    64    14    15      3      6      7      3      4      5      7      9    23    25    56    146 583  4.51- 5.50    160    66    10      5      1     5      7      0     2     1      8      6     4      7    28    77 387  5.51- 6.50    77    43    14      3      1      0      2     2      2      4     2      5      2      6      9    28 200  6.51- 8.50    83    37      5      4      1     0      1      1      1      4     3      2     2      0      2    31 177  8.51-11.50    25    19      6     2      0      0      0      0      0      2      0      0      0      0      1      4 59  11.51-14.50      1      0      0      2      0      1     0      0      0      0      0      0      0      0      0      0 4  14.51-20.50      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0      0 0    >20.50        0      0      0      0      0      0      0      0      0      0      0      0      0      0      1      0 1  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
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.
____    TOTAL      712    281    68    47    16    25    25    14    14    26    36    38    65    118    220    452 2157                                                                                                                               
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)
                          ------------------------------------------------- + ---------------------------------------------- + . . . 1.0 reporting level (1) 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. 27


STABILITY CLASS  ALL SPEED (MPH)        N    NNE    NE    ENE      E    ESE    SE    SSE      S    SSW    SW    WSW      W    WNW    NW    NNW  T OTAL  ___________                                                                                                                  _
6.1.1 Surveillance Requirements
____    CALM 0    .76- 1.50      1      1      3      2      1      1      2      1      2      2      1      1      2      1      4      2 27  1.51- 2.50    69    36    18    12    14      9    15    15    15    16    32    38    42    65    65    66 527  2.51- 3.50    199    62    34    38    21    25    23    30    40    55    66    47    64    104    140    171 1119  3.51- 4.50    247    101    46    41    16    23    19    22    71    80    76    55    67    64    114    198 1240  4.51- 5.50    205    112    54    38    25    19    42    46    102    92    112    65    31    30    58    118 1149  5.51- 6.50    110    80    63    30    14    18    22    45    109    119    104    75    35    31    32    59 946  6.51- 8.50    123    83    70    74    50    53    51    66    119    171    264    100    68    31    36    60 1419  8.51-11.50    45    48    49    51    67    78    20    24    47    166    276    106    66    44    26    41 1154  11.51-14.50    11    14    18    17    90    25    16      9    20    70    160    44    16    29    17    15 571  14.51-20.50      8      7    12    11    91    10      6      9    13    41    93    14    12    20      8      9 364    >20.50        1      0      1      0      3      2      0      3      3      8    11      4      1      5      3      0 45  ___________ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ ______ __
: 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 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.
____    TOTAL      1019    544    368    314    392    263    216    270    541    820  1195    549    404    424    503    739 8561 
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.
63                                      ODCM Rev. 27


TOTAL NUMBER OF OBSERVATIONS:  8568 TOTAL NUMBER OF VALID OBSERVATIONS:  8561 TOTAL NUMBER OF MISSING OBSERVATIONS:    7 PERCENT DATA RECOVERY FOR THIS PERIOD:  99.9 %
TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples                  Sampling and      Type and Frequency and/or Sample              and Sample Locationsa            Collection Frequencya      of Analysisd Airborne              Samples from 5 locations: 4 samples    Continuous sampling    Gross beta weeklyc, at or near the SITE BOUNDARIES          collected weekly, or  I-131 weekly; gamma Radioiodine and      (#14A, 15, 29, 40) including 3          more frequently if     isotopic analysis of particulates          different sectors of the highest        required by dust      composite (by calculated annual average ground        loading.              location) quarterly.
MEAN WIND SPEED FOR THIS PERIOD:   6.7 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA:    0                                                                         
level D/Q.*
1 sample (#40) from areas of special interest, which is from the vicinity of a community having the highest calculated annual average D/Q.
1 sample (#6A) from a control location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.e 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. 27


PERCENTAGE OCCURRENCE OF STABILITY CLASSES A        B        C        D        E        F        G 8.78     6.56     6.46    19.09    19.67    14.24    25.20                               
TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples            Sampling and        Type and Frequency and/or Sample          and Sample Locationsa          Collection Frequency  a of Analysisd Waterborne Surface          85 acre Water storagereservoir (#60) Quarterlyh grab sample    Tritium and gamma MAR 2016                  45 acre Water storage reservoir (#61)                          isotopic analysis Evaporation pond #1 (#59)                                      quarterly.
Evaporation pond #2 (#63)
Evaporation pond #3 (#64)
Ground            2 onsite wellsf (#57, #58)            Quarterly grab sample    Tritium and gamma isotopic analysis quarterly.
Drinking (well)  3 wells from surrounding residences    Composite sample of      I-131 analysis on each
(#46, #48, #49) that would be          weekly grab samples      composite when the affected by its discharge.             over 2-week period      dose calculated for when I-131 analysis is  the consumption of performed, monthly      the water is greater composite of weekly     than 1 mrem per grab samples otherwise  year.g Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.
Ingestion        Samples from milking animals in        Semimonthly for          Gamma isotopic and 3 locations within 5 km (3 mi) distant animals on pasture;     I-131 analysis Milk              having the highest dose potential. If otherwise, monthly.       semimonthly when 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.g 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.e 65                                    ODCM Rev. 27


DISTRIBUTION OF WIND DIRECTION VS STABILITY N    NNE    NE    ENE      E    ESE    SE    SSE     S   SSW    SW   WSW      W    WNW    NW    NNW  CALM 
TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples                Sampling and        Type and Frequency and/or Sample            and Sample Locationsa            Collection Frequency  a of Analysisd Food Products
* 2 samples (#47, #51) of 3 types of     Monthly during          Gamma isotopic MAR 2016                      broad leaf vegetation (as available)   growing season.          analysis.
from locations identified per the criteria of Section 6.2b. of this manual.
1 control sample (#62) of 3 types of Monthly during              Gamma isotopic broad leaf vegetation (as available)   growing season.          analysis.
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. 27


A        4     6     16    20    30    56    35    61    115    109    143    61    39    24     19    14      0 B        3    11    19    33    35    31    23    44    85    86    104    43    20    12      5      8      0 C      10     15    37    28    43    19    21    34    84    94    81    28    22    11    11    15      0 D      78    81    101    80    124    58    58    65    147    203    275    116    86    58    43    61      0 E      98    79    65    59    124    60    29    37    74    191    358    153    89    103    91    74      0 F      114    71    62    47    20    14    25    15    22    111    198    110    83    98    114    115      0 G      712    281    68    47    16    25    25    14    14    26    36    38    65    118    220    452      0 TOTAL  1019    544    368    314    392    263    216    270    541    820  1195    549    404    424    503    739      0 
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 6-1or 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 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. 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.
h Quarterly grab samples are not required from the onsite evaporation pond if the evaporation pond has not received any influent since the last sample was taken.
MAR 2016 67                                      ODCM Rev. 27


APPENDIX C DOSE CALCULATIONS 
TABLE 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate        Fresh Milk      Food Products Analysis        Water (pCi/l)          or Gas (pCi/m3)              (pCi/l)        (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/l may be used.
** If no drinking water pathway exists, a reporting level of 20 pCi/l may be used.
68                                    ODCM Rev. 27


GASEOUS EFFLUENT DOSE CALCULATIONS Doses to the maximum individual and the surrounding population resulting from the release of radioactive material in gaseous effluents from the Palo Verde Nuclear Generating Station were calculated using the GASPAR computer program. The radionuclides considered in the dose calculations were tritium, iodine-131, iodine-132, iodine-133, iodine-135, all noble gases, and particulates having a half-life greater than eight days and for which dose factors are contained in NUREG-0172. Locations selected for individual dose calculations included for each sector, the site boundary, and within five miles, if present, the nearest residence, the nearest garden, and the nearest milk animal. GASPAR implements the radiological dose models of Regulatory Guide 1.109 to determine the radiation exposure to man from four principal atmospheric exposure pathways:
TABLE 6-3 a
plume, ground deposition, inhalation, and ingestion. Doses to the maximum individual and the population were calculated as a function of age group and pathway for significant body organs.
DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS Lower Limit of Detection (LLD)b Airborne Particulate          Fresh Milk          Food Products Analysis          Water (pCi/l)        or Gas (pCi/m3)              (pCi/l)          (pCi/kg, wet)
Table 43 presents the doses on a quarterly, semiannual and annual basis for the Energy Information Center. An occupancy factor of 1.0 (implying continuous occupancy over the entire
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/l may be used.
**    If no drinking water pathway exists, a value of 15 pCi/l may be used.
69                                        ODCM Rev. 27


year) was considered for the Energy Information Center and the exposure pathways considered to calculate its doses were plume, ground deposition, and inhalation. Dose to the special location for 2016 was 1.65 millirem. This is well within the 25 mrem/yr limit of 40 CFR 190.
Table 6-3 (Continued)
Table 44 presents the population dose.
TABLE NOTATION a Guidance for detection capabilities for thermoluminescent dosimeters used for environmental measurements is given in Regulatory Guide 4.13.
Table 45 summarizes the individual doses and compares the result to PVNGS ODCM Requirement limits. The site boundary and residence locations for which data are presented represent the highest annual doses.
b Table 6-3 indicates acceptable detection capabilities for radioactive materials in environmental samples.
Based on results obtained by placing TLDs on the site boundary in each sector, the net dose for this reporting period, from direct-radiation, (plume and ground deposition) from all three units was indistinguishable from preoperational values of 8 - 14
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.
&#xb5;R/hr (17 - 30 mR/Std Qtr).
For a particular measurement system (which may include radiochemical separation):
There were no liquid effluents associated with the operation of this facility.
4.66s b LLD = ------------------------------------------------------------------------
Dose Calculation Models The GASPAR computer code was used to evaluate the radiological consequences of the routine release of gaseous effluents. GASPAR implements the dose calculational methodologies of Regu-latory Guide 1.109, Revision 1.
E
Source terms for each quarter are combined with station-specific demographic data and each quarter's atmospheric diffusion estimates for gaseous dose calculations.
* V
Atmospheric diffusion estimates are generated by the XOQDOQ computer code using onsite meteorological data as input. Additional input to GASPAR includes the following site-specific data:
* 2.22
0 to 5 mile nearest residence, milk animal and garden in each of the 16 compass sectors, based on the 2016 Land Use Census.
* Y
0 to 10 mile population from the PVNGS Emergency Plan, Rev 47.
* exp ( - t )
The 10 to 50 mile population distribution from the PVNGS UFSAR, Figure 2.1-12.
Where:
The population distribution of metropolitan Phoenix greater than 50 miles from PVNGS, based on the 1980 federal census results, is conservatively included in the 40 to 50 mile sectors (NE=123; ENE=140,097; E=621,130; ESE=8,392). Absolute humidity of 6.0 g/m 3 from the PVNGS UFSAR, Table 2.3-16. The fraction of the year that vegetables are grown (0.667) from the PVNGS ER-OL, Section 2.1.3.4, Table 2.1-8.
LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume),
The fraction of daily feed derived from pasture while on pasture (0.35) and length of grazing season for milk animals beyond 5 miles (0.75) from the PVNGS ER-OL, Section 2.1.3.4.3.
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),
The fraction of daily feed derived from pasture while on pasture (0.05) and length of grazing season for meat animals (0.25) from the PVNGS ER-OL, Section 2.1.3.4.4.
E is the counting efficiency (as counts per disintegration),
There were three (3) sectors containing milk animal (goat or cow) locations within five (5) miles. For calculation purposes these milk animals are assumed to be fed 100% on pasture grass during the year.
V is the sample size (in units of mass or volume),
Other values used for input to GASPAR are default values from Regulatory Guide 1.109, Rev. 1. 
2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
is the radioactive decay constant for the particular radionuclide, and t 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 t 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. 27


Table 43: Doses To Special Locations For 2016 ENERGY INFORMATION CENTER LOCATED ONSITE 0.45 MILE S FROM UNIT 1, 0.29 MILE SSE FROM UNIT 2 AND 0.20 MILE ESE FROM UNIT 3.
===6.2 Requirement===
(MREM) T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN 1ST QUARTER ADULT 6.71E-01 6.71E-01 1.22E-036.71E-016.71E-016.71E-01 6.71E-016.71E-01TEEN 6.75E-01 6.75E-01 1.22E-036.75E-016.75E-016.75E-01 6.75E-016.76E-01 CHILD 5.97E-01 5.97E-01 1.22E-035.97E-015.97E-015.97E-01 5.97E-015.98E-01 INFANT 3.44E-01 3.44E-01 1.22E-033.44E-013.44E-013.44E-01 3.44E-013.44E-012ND QUARTER ADULT 1.95E-01 1.95E-01 9.72E-031.95E-011.95E-011.95E-01 1.97E-011.97E-01TEEN 1.97E-01 1.97E-01 9.72E-031.97E-011.97E-011.97E-01 2.01E-011.99E-01 CHILD 1.75E-01 1.75E-01 9.72E-031.75E-011.75E-011.75E-01 1.78E-011.77E-01 INFANT 1.05E-01 1.05E-01 9.72E-031.05E-011.05E-011.05E-01 1.07E-011.07E-011ST SEMI-ANNUAL ADULT 8.66E-01 8.66E-01 1.09E-028.66E-018.66E-018.66E-01 8.68E-018.69E-01TEEN 8.72E-01 8.72E-01 1.09E-028.72E-018.72E-018.72E-01 8.76E-018.75E-01 CHILD 7.72E-01 7.72E-01 1.09E-027.72E-017.72E-017.72E-01 7.75E-017.75E-01 INFANT 4.49E-01 4.49E-01 1.09E-024.49E-014.49E-014.49E-01 4.50E-014.51E-013RD QUARTER ADULT 2.30E-01 2.30E-01 3.39E-042.30E-012.30E-012.30E-01 2.30E-012.31E-01TEEN 2.32E-01 2.32E-01 3.39E-042.32E-012.32E-012.32E-01 2.32E-012.32E-01 CHILD 2.05E-01 2.05E-01 3.39E-042.05E-012.05E-012.05E-01 2.05E-012.05E-01 INFANT 1.18E-01 1.18E-01 3.39E-041.18E-011.18E-011.18E-01 1.18E-011.18E-014TH QUARTER ADULT 5.56E-01 5.56E-01 2.08E-035.56E-015.56E-015.56E-01 5.56E-015.56E-01TEEN 5.60E-01 5.60E-01 2.08E-035.60E-015.60E-015.60E-01 5.60E-015.60E-01 CHILD 4.95E-01 4.95E-01 2.08E-034.95E-014.95E-014.96E-01 4.96E-014.95E-01 INFANT 2.86E-01 2.86E-01 2.08E-032.86E-012.86E-012.86E-01 2.86E-011.29E-012ND SEMI-ANNUAL ADULT 7.86E-01 7.86E-01 2.42E-037.86E-017.86E-017.86E-01 7.86E-017.86E-01TEEN 7.92E-01 7.92E-01 2.42E-037.92E-017.92E-017.92E-01 7.92E-017.92E-01 CHILD 7.00E-01 7.00E-01 2.42E-037.00E-017.00E-017.01E-01 7.01E-016.99E-01 INFANT 4.04E-01 4.04E-01 2.42E-034.04E-014.04E-014.04E-01 4.04E-012.47E-01ANNUAL ADULT 1.65E+00 1.65E+00 1.34E-021.65E+001.65E+001.65E+00 1.65E+001.65E+00TEEN 1.66E+00 1.66E+00 1.34E-021.66E+001.66E+001.66E+00 1.67E+001.67E+00 CHILD 1.47E+00 1.47E+00 1.34E-021.47E+001.47E+001.47E+00 1.48E+001.47E+00 INFANT 8.52E-01 8.52E-01 1.34E-028.52E-018.52E-018.52E-01 8.54E-016.98E-01
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. 27


Table 44: Integrated Population Dose for 2016 January through March PLUME 1.20E-04 1.20E-04 1.20E-041.20E-041.20E-041.20E-04 1.20E-042.23E-04 0.00% 0.00% 90.84%0.00%0.00%0.00% 0.00%0.00%GROUND 1.21E-05 1.21E-05 1.21E-051.21E-051.21E-051.21E-05 1.21E-051.42E-05 0.00% 0.00% 9.16%0.00%0.00%0.00% 0.00%0.00%INHAL 2.15E+00 2.15E+00 < LLD2.15E+002.15E+002.15E+00 2.15E+002.15E+00 25.83% 25.83% 0.00%25.83%25.83%25.83% 25.83%25.83%
===6.3 Requirement===
VEGET 5.33E+00 5.33E+00 < LLD5.33E+005.33E+005.33E+00 5.33E+005.33E+00 64.04% 64.04% 0.00%64.04%64.04%64.04% 64.04%64.04%
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.
COW MILK 5.79E-01 5.79E-01 < LLD5.79E-015.79E-015.79E-01 5.79E-015.79E-01 6.96% 6.96% 0.00%6.96%6.96%6.96% 6.96%6.96%MEAT 2.64E-01 2.64E-01 < LLD2.64E-012.64E-012.64E-01 2.64E-012.64E-01 3.17% 3.17% 0.00%3.17%3.17%3.17% 3.17%3.17%*TOTAL* 8.33E+00 8.33E+00 1.32E-048.33E+008.33E+008.33E+00 8.33E+008.33E+00 PER CAPITA DOSE (REM) 4.25E-06 4.25E-06 6.74E-114.25E-064.25E-064.25E-06 4.25E-064.25E-06 April through June PLUME 1.87E-04 1.87E-04 1.87E-041.87E-041.87E-041.87E-04 1.87E-044.23E-04 0.01% 0.01% 2.48%0.01%0.01%0.01% 0.01%0.02%GROUND 7.29E-03 7.29E-03 7.29E-037.29E-037.29E-037.29E-03 7.29E-038.57E-03 0.26% 0.26% 96.94%0.26%0.26%0.26% 0.26%0.31%INHAL 8.24E-01 8.24E-01 2.14E-058.24E-018.24E-018.24E-01 8.30E-018.24E-01 29.90% 29.89% 0.28%29.90%29.90%29.90% 30.05%29.88%
Applicability:  At all times.
VEGET 1.65E+00 1.66E+00 2.11E-051.65E+001.65E+001.65E+00 1.65E+001.65E+00 60.04% 60.05% 0.28%60.04%60.04%60.04% 59.91%60.01%
Action:
COW 2.08E-01 2.08E-01 5.34E-072.08E-012.08E-012.08E-01 2.08E-012.08E-01 7.56% 7.56% 0.01%7.56%7.56%7.56% 7.55%7.56%MEAT 6.14E-02 6.14E-02 3.47E-076.14E-026.14E-026.14E-02 6.14E-026.14E-02 2.23% 2.23% 0.00%2.23%2.23%2.23% 2.22%2.23%*TOTAL* 2.76E+00 2.76E+00 7.52E-032.76E+002.75E+002.76E+00 2.76E+002.76E+00 PER CAPITA DOSE (REM) 1.41E-06 1.41E-06 3.84E-091.41E-061.40E-061.41E-06 1.41E-061.41E-06
: 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.
6.3.1 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.
6.3.2 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. 27


Table 44: (conti nued) Integrated Population Dose for 2016 January through June PLUME 3.07E-04 3.07E-04 3.07E-043.07E-043.07E-043.07E-04 3.07E-046.45E-04 0.00% 0.00% 4.01%0.00%0.00%0.00% 0.00%0.01%GROUND 7.30E-03 7.30E-03 7.30E-037.30E-037.30E-037.30E-03 7.30E-038.59E-03 0.07% 0.07% 95.42%0.07%0.07%0.07% 0.07%0.08%INHAL 2.97E+00 2.98E+00 2.14E-052.97E+002.97E+002.98E+00 2.98E+002.97E+00 26.84% 26.84% 0.28%26.84%26.84%26.84% 26.88%26.84%
TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE                  NOTE  DESIGNATION SITE    SAMPLE 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 5      TLD (b)      SP      ESE11    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.
VEGET 6.99E+00 6.99E+00 2.11E-056.99E+006.99E+006.99E+00 6.99E+006.99E+00 63.04% 63.05% 0.28%63.04%63.04%63.04% 63.01%63.03%
7A          Air        SUP      ESE3    Arlington School 8      TLD (b)      OR        SSE4    Southern Pacific Pipeline Rd.
COW 7.88E-01 7.88E-01 5.34E-077.88E-017.88E-017.88E-01 7.88E-017.88E-01 7.11% 7.10% 0.01%7.11%7.11%7.11% 7.10%7.10%MEAT 3.26E-01 3.26E-01 3.47E-073.26E-013.26E-013.26E-01 3.26E-013.26E-01 2.94% 2.94% 0.00%2.94%2.94%2.94% 2.94%2.94%*TOTAL* 1.11E+01 1.11E+01 7.65E-031.11E+011.11E+011.11E+01 1.11E+011.11E+01 PER CAPITA DOSE (REM) 5.67E-06 5.67E-06 3.91E-095.67E-065.67E-065.67E-06 5.67E-065.67E-06 July through September PLUME 6.45E-05 6.45E-05 6.45E-056.45E-056.45E-056.45E-05 6.45E-051.19E-04 0.00% 0.00% 99.59%0.00%0.00%0.00% 0.00%0.00%GROUND 2.66E-07 2.66E-07 2.66E-072.66E-072.66E-072.66E-07 2.66E-073.11E-07 0.00% 0.00% 0.41%0.00%0.00%0.00% 0.00%0.00%INHAL 8.81E-01 8.81E-01 < LLD8.81E-018.81E-018.81E-01 8.81E-018.81E-01 29.86% 29.86% 0.00%29.86%29.86%29.86% 29.86%29.86%
9      TLD (b)      OR          S5  Southern Pacific Pipeline Rd.
VEGET 1.78E+00 1.78E+00 < LLD1.78E+001.78E+001.78E+00 1.78E+001.78E+00 60.44% 60.44% 0.00%60.44%60.44%60.44% 60.44%60.44%
10       TLD (b)      OR        SE5    355th Ave. and Elliot Rd.
COW 2.14E-01 2.14E-01 < LLD2.14E-012.14E-012.14E-01 2.14E-012.14E-01 7.27% 7.27% 0.00%7.27%7.27%7.27% 7.27%7.27%MEAT 7.19E-02 7.19E-02 < LLD7.19E-027.19E-027.19E-02 7.19E-027.19E-02 2.44% 2.44% 0.00%2.44%2.44%2.44% 2.44%2.44%*TOTAL* 2.95E+00 2.95E+00 6.47E-052.95E+002.95E+002.95E+00 2.95E+002.95E+00 PER CAPITA DOSE (REM) 1.51E-06 1.51E-06 3.30E-111.51E-061.51E-061.51E-06 1.51E-061.51E-06
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)      IR        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. 27


Table 44: (continued)
TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE                  NOTE  DESIGNATION SITE  SAMPLE 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.
Integrated Population Dose for 2016 October through December PLUME 1.11E-04 1.11E-04 1.11E-041.11E-041.11E-041.11E-04 1.11E-042.49E-04 0.00% 0.00% 31.22%0.00%0.00%0.00% 0.00%0.00%GROUND 2.35E-04 2.35E-04 2.35E-042.35E-042.35E-042.35E-04 2.35E-042.77E-04 0.00% 0.00% 66.34%0.00%0.00%0.00% 0.00%0.00%INHAL 2.41E+00 2.41E+00 6.97E-062.41E+002.41E+002.42E+00 2.41E+002.41E+00 27.37% 27.37% 1.97%27.37%27.37%27.37% 27.37%27.37%
25      TLD (b)      OR      WSW5    N of Elliot Rd.
VEGET 5.48E+00 5.48E+00 1.50E-065.48E+005.48E+005.48E+00 5.48E+005.48E+00 62.11% 62.11% 0.42%62.11%62.11%62.10% 62.10%62.11%
26      TLD (b)      OR      SSW4    Duke Property 27      TLD (b)      IR      SW1    SW site boundary 28      TLD (b)      IR    WSW1    WSW site boundary 29      TLD (b)      IR      W1    W site boundary 29        Air (b)              W1    Same as TLD 30      TLD (b)      IR    WNW1    WNW site boundary 31       TLD (b)      IR      NW1    NW site boundary 32      TLD (b)      IR    NNW1    NNW site boundary 33      TLD (b)      OR      NW4    S of Buckeye Rd.
COW MILK 6.71E-01 6.71E-01 1.59E-076.71E-016.71E-016.71E-01 6.71E-016.71E-01 7.61% 7.61% 0.04%7.61%7.61%7.61% 7.61%7.61%MEAT 2.57E-01 2.57E-01 2.06E-092.57E-012.57E-012.57E-01 2.57E-012.57E-01 2.92% 2.92% 0.00%2.92%2.92%2.92% 2.92%2.92%*TOTAL* 8.82E+00 8.82E+00 3.54E-048.82E+008.82E+008.82E+00 8.82E+008.82E+00 PER CAPITA DOSE (REM) 4.50E-06 4.50E-06 1.81E-104.50E-064.50E-064.50E-06 4.50E-064.50E-06 July through December PLUME  0.00% 0.00% 41.78%0.00%0.00%0.00% 0.00%0.00%GROUND 2.35E-04 2.35E-04 2.35E-042.35E-042.35E-042.35E-04 2.35E-042.77E-04 0.00% 0.00% 56.16%0.00%0.00%0.00% 0.00%0.00%INHAL 3.30E+00 3.30E+00 6.97E-063.30E+003.30E+003.30E+00 3.30E+003.30E+00 27.99% 27.99% 1.66%27.99%27.99%27.99% 27.99%27.99%
34       TLD (b)      OR      NNW5    395th Ave. and Van Buren St.
VEGET  COW  MEAT  *TOTAL* PER CAPITA DOSE (REM)     
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 43        TLD        SUP      NE5    Winters Well School 74                              ODCM Rev. 27


Table 44: (continued)
TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE                    NOTE    DESIGNATION SITE  SAMPLE TYPE        (d)        (a)          LOCATION DESCRIPTION (c) 44       TLD (b)       Control    ENE35    El Mirage SUP Transit 45         TLD        Control    ONSITE  Central lab, lead pig 46        TLD (b)        SP      ENE30    Litchfield Park School 46        Water (b)      WD        NNW8    Local residence 47          TLD          SUP        E35    Littleton School 47    Vegetation (b)                N3    Local residence 48          TLD          SUP        E24    Jackrabbit Trail 48        Water (b)      WD        SW1    Local residence 49          TLD          SUP      ENE11    Palo Verde Rd.
Integrated Population Dose for 2016 January through December PLUME 4.82E-04 4.82E-04 4.82E-044.82E-044.82E-044.82E-04 4.82E-041.01E-03 0.00% 0.00% 5.97%0.00%0.00%0.00% 0.00%0.00%GROUND 7.54E-03 7.54E-03 7.54E-037.54E-037.54E-037.54E-03 7.54E-038.86E-03 0.03% 0.03% 93.39%0.03%0.03%0.03% 0.03%0.04%INHAL 6.27E+0 0 6.27E+00 2.84E-056.27E+00 6.27E+0 0 6.27E+00 6.28E+00 6.27E+0 0  27.43% 27.43% 0.35%27.43%27.43%27.44% 27.45%27.43%
49        Water (b)      WD          N2    Local residence 50        TLD (b)        OR        WNW5    S of Buckeye-Salome Rd.
VEGET 1.43E+0 1 1.43E+01 2.26E-051.43E+01 1.43E+0 1 1.43E+01 1.43E+01 1.43E+0 1  62.35% 62.35% 0.28%62.35%62.35%62.34% 62.33%62.34%
51        Milk (b)                  ENE5    Local residence (goats) 51    Vegetation (b)              ENE5    Local residence MAR 2016 53        Milk (b)    Control    NE30    Local residence (goats) 54        Milk (b)                NNE4    Local residence (goats)
COW 1.67E+0 0 1.67E+00 6.93E-071.67E+00 1.67E+0 0 1.67E+00 1.67E+00 1.67E+0 0 7.32% 7.32% 0.01%7.32%7.32%7.32% 7.32%7.32%MEAT 6.55E-01 6.55E-01 3.49E-076.55E-016.55E-016.55E-01 6.55E-016.55E-01 2.87% 2.87% 0.00%2.87%2.87%2.87% 2.86%2.87%*TOTAL* 2.29E+0 1 2.29E+01 8.07E-032.29E+01 2.29E+0 1 2.29E+01 2.29E+01 2.29E+0 1 PER CAPITA DOSE (REM) 1.17E-05 1.17E-05 4.12E-091.17E-051.17E-051.17E-05 1.17E-051.17E-05
WD 55          Water        SUP        SW3    Local residence 57    Ground Water (b)  WG        onsite  Well 27ddc 58    Ground Water (b)  WG        onsite  Well 34abb 59    Surface Water (b)  WS        onsite  Evaporation Pond #1 60    Surface Water (b)  WS        onsite  85 acre Water storage reservoir 61    Surface Water (b)  WS        onsite 45 acre Water storage reservoir 62     Vegetation (b)  Control    ENE26    Commercial produce company 63    Surface Water (b)  WS        onsite Evaporation Pond #2 64    Surface Water (b) WS        onsite  Evaporation Pond #3 75                                ODCM Rev. 27


Table 45: Summary of Individual Doses for 2016 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Ai r Dose mrad 5.07E-04 3.29E-04 1.23E-04 3.72E-04 1.17E-03 ODCM Req. 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 % ODCM Limit
NOTES: (a) Distance and direction are relative to the Unit 2 containment, rounded to the nearest mile.
% 1.01E-02 6.58E-03 2.46E-03 7.44E-03 1.17E-02 Beta Ai r Dose mrad 1.82E-04 1.41E-04 4.46E-05 1.49E-04 4.53E-04 ODCM Req. 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 % ODCM Limit
(b) These samples fulfill the requirements of the ODCM, Table 6-1.
% 1.82E-03 1.41E-03 4.46E-04 1.49E-03 2.27E-03 Maximum Individual Total Body mrem 3.37E-04 2.18E-04 8.14E-05 2.47E-04 7.78E-04 Skin mrem 5.41E-04 3.57E-04 1.31E-04 3.99E-04 1.26E-03 Site Boundary Location Unit 1 miles 1.70 SSE 0.78  NW 1.40 SSW 1.70 SSE 1.70 SSE Unit 2 miles 1.88 SSE 0.74  NW 1.14 SSW 1.88 SSE 1.88 SSE Unit 3 miles 1.73 SSE 0.65  NW 1.00 SSW 1.73 SSE 1.73 SSE Maximum Organ Dose (excluding skin)
(c) Refer to Figure 6-1 and Figure 6-2 for relative locations of sample sites.
Age Infant Infant Infant Teen Teen Organ Bone Bone Bone Thyroid (2) Lung mrem 1.85E-01 1.01E-01 7.94E-02 1.90E-01 4.86E-01 ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 % ODCM Limit (1) % 2.47E+00 1.35E+00 1.06E+00 2.53E+00 3.24E+00 Location  Unit 1 miles 2.84 NNE 2.84 NNE 2.84 NNE 2.74  S 2.74  S Unit 2 miles 3.05 NNE 3.05 NNE 3.05 NNE 2.56  S 2.56  S Unit 3 miles 3.28 NNE 3.28 NNE 3.28 NNE 2.35  S 2.35  S Maximum Organ Dose excluding C-14 (3) (excluding skin)
(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. 27
Age Teen Infant Teen Teen Teen Organ Thyroid (2)Thyroid Thyroid (2)Thyroid (2) Lung mrem 1.74E-01 4.88E-02 7.41E-02 1.90E-01 4.86E-01 ODCM Req. 4.2 Limit 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 % ODCM Limit (1)  2.32E+00 6.51E-01 9.88E-01 2.53E+00 3.24E+00 Organ dose from tritium only for Unit 2 location above  mrem 1.74E-01 4.72E-02 7.41E-02 1.90E-01 4.84E-01 Fraction of organ dose from tritium only for Unit 2 location above (2,3) %  100.00%  96.72%  100.00%  100.00%  99.59% X/Q for Unit 2 location above sec/m 3 8.75E-07 4.73E-07 3.76E-07 7.96E-06 5.16E-06 D/Q for Unit 2 location above m-2 1.31E-09 1.82E-09 1.61E-09 2.58E-09 1.86E-09 Note 1: ODCM Requirement 5.1 has higher limits than ODCM Requirement 4.2, therefore the percent of limits are more conservative based on ODCM Requirement 4.2 than on ODCM Requirement 5.1. Note 2: All organs except bone Note 3  Refer to discussion in section 10.4 


APPENDIX D NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING 
Figure 6-1 Radiological Environmental Monitoring Program Sample Sites 0 - 10 miles 77                      ODCM Rev. 27


Field Sample ID Location ID Sample Date Parameter Name  Report Result Repo rt Units Det ected Sample Purpose PV-APP-10-0216 APP-10 02/04/2016 Tritium <303 pCi/L N REG PV-APP-10-0216 APP-10 02/04/2016 Cesium-137
78 Figure 6-2 Radiological Environmental Monitoring Program Sample Sites ODCM Rev. 27            10 - 35 Miles
<1.0 pCi/L N REG PV-APP-10-0216 APP-10 02/04/2016 Cobalt-60
<2.0 pCi/L N REG PV-APP-10-0216 APP-10 02/04/2016 Cesium-134
<2.1 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Tritium <287 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Cesium-137
<2.1 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Cesium-134
<1.7 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Tritium <288 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Cesium-137
<1.5 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Cobalt-60
<0.5 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Cesium-134
<1.3 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Tritium <308 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Cesium-137
<1.5 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Cobalt-60
<0.7 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Cesium-134
<1.0 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Tritium <303 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Cesium-134
<1.6 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Tritium <287 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Cesium-134
<1.5 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Tritium <288 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Cesium-137
<0.8 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Cobalt-60
<0.5 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Cesium-134
<1.1 pCi/L N REG PV-APP-12-1116 APP-12 11/08/2016 Tritium <289 pCi/L N PV-APP-12-1116 APP-12 11/08/2016 Cesium-137
<1.0 pCi/L N PV-APP-12-1116 APP-12 11/08/2016 Cobalt-60
<1.2 pCi/L N PV-APP-12-1116 APP-12 11/08/2016 Cesium-134
<10.0 pCi/L N PV-APP-15-0216 APP-15 02/01/2016 Tritium <242 pCi/L N REG PV-APP-15-0216 APP-15 02/01/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-15-0216 APP-15 02/01/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-15-0216 APP-15 02/01/2016 Cesium-134
<1.4 pCi/L N REG PV-APP-15-1016 APP-15 10/04/2016 Tritium <288.0 pCi/L N PV-APP-15-1016 APP-15 10/04/2016 Cesium-137
<1.4 pCi/L N PV-APP-15-1016 APP-15 10/04/2016 Cobalt-60
<1.1 pCi/L N PV-APP-15-1016 APP-15 10/04/2016 Cesium-134
<1.0 pCi/L N PV-APP-18-0316 APP-18 03/16/2016 Tritium <287 pCi/L N REG 


PV-APP-18-0316 APP-18 03/16/2016 Cesium-137
Figure 6-3 Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED 79                    ODCM Rev. 27
<3.4 pCi/L N REG PV-APP-18-0316 APP-18 03/16/2016 Cobalt-60
<1.3 pCi/L N REG PV-APP-18-0316 APP-18 03/16/2016 Cesium-134
<2.8 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Tritium <285 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Cesium-137
<0.9 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Cobalt-60
<0.3 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Cesium-134
<1.0 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Tritium <303 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Cesium-137
<1.1 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Cesium-134
<2.1 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Tritium <308 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Cesium-137
<0.5 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Cobalt-60
<0.8 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Cesium-134
<1.0 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Tritium <303 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Cesium-137
<1.4 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Cesium-134
<1.7 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Tritium <285 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Cesium-137
<1.1 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Cobalt-60
<1.0 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Cesium-134
<0.8 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Tritium <303 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Cesium-137
<1.2 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Cobalt-60
<1.5 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Cesium-134
<1.2 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Tritium <285 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Cesium-137
<0.9 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Cobalt-60
<1.0 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Cesium-134
<0.9 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Tritium <299 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Cesium-137
<1.2 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Cesium-134
<1.7 pCi/L N REG PV-APP-22-1016 APP-22 10/04/2016 Tritium <288 pCi/L N PV-APP-22-1016 APP-22 10/04/2016 Cesium-137
<1.4 pCi/L N PV-APP-22-1016 APP-22 10/04/2016 Cobalt-60
<0.8 pCi/L N PV-APP-22-1016 APP-22 10/04/2016 Cesium-134
<1.0 pCi/L N PV-APP-23-0216 APP-23 02/10/2016 Tritium <303 pCi/L N REG PV-APP-23-0216 APP-23 02/10/2016 Cesium-137
<1.3 pCi/L N REG PV-APP-23-0216 APP-23 02/10/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-23-0216 APP-23 02/10/2016 Cesium-134
<1.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Tritium <288 pCi/L N REG 


PV-APP-23-1016 APP-23 10/12/2016 Cesium-137
Figure 6-4 Site Exclusion Area Boundary DELETED Refer to UFSAR Figure 2.1-4 80            ODCM Rev. 27
<0.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Cobalt-60
<0.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Cesium-134
<0.7 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Tritium <303 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Cesium-134
<1.7 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Tritium <303 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Cesium-137
<1.1 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Cesium-134
<2.7 pCi/L N REG PV-APP-4R-1116 APP-4R 11/01/2016 Tritium <285 pCi/L N PV-APP-4R-1116 APP-4R 11/01/2016 Cesium-137
<1.7 pCi/L N PV-APP-4R-1116 APP-4R 11/01/2016 Cobalt-60
<0.3 pCi/L N PV-APP-4R-1116 APP-4R 11/01/2016 Cesium-134
<1.4 pCi/L N PV-APP-5-0216 APP-5 02/23/2016 Tritium <299 pCi/L N REG PV-APP-5-0216 APP-5 02/23/2016 Cesium-137
<1.8 pCi/L N REG PV-APP-5-0216 APP-5 02/23/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-5-0216 APP-5 02/23/2016 Cesium-134
<2.9 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Tritium <303 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Cobalt-60
<1.5 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Cesium-134
<1.9 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Tritium <303 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Cesium-134
<2.8 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Tritium <287 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Cesium-137
<1.0 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Cobalt-60
<1.4 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Cesium-134
<2.4 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Tritium <288 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Cesium-137
<1.7 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Cobalt-60
<0.9 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Cesium-134
<1.6 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Tritium <308 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Cesium-137
<1.3 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Cobalt-60
<0.7 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Cesium-134
<1.7 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Tritium <242 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cesium-137
<1.0 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cobalt-60
<1.4 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cesium-134
<1.6 pCi/L N REG PV-PV-14H-1016 PV-14H 10/04/2016 Tritium <288 pCi/L N 


PV-PV-14H-1016 PV-14H 10/04/2016 Cesium-137
81 Figure 6-5 Gaseous Effluent Release Points ODCM Rev. 27
<0.8 pCi/L N PV-PV-14H-1016 PV-14H 10/042016 Cobalt-60
<0.8 pCi/L N PV-PV-14H-1016 PV-14H 10/04/2016 Cesium-134
<0.8 pCi/L N PV-PV-195A-0216 PV-195A 02/01/2016 Tritium <242 pCi/L N REG PV-PV-195A-0216 PV-195A 02/01/2016 Cesium-137
<2.1 pCi/L N REG PV-PV-195A-0216 PV-195A 02/01/2016 Cobalt-60
<1.4 pCi/L N REG PV-PV-195A-0216 PV-195A 02/01/2016 Cesium-134
<1.3 pCi/L N REG PV-PV-195A-1016 PV-195A 10/04/2016 Tritium <288 pCi/L N PV-PV-195A-1016 PV-195A 10/04/2016 Cesium-137
<0.3 pCi/L N PV-PV-195A-1016 PV-195A 10/04/2016 Cobalt-60
<0.7 pCi/L N PV-PV-195A-1016 PV-195A 10/04/2016 Cesium-134
<1.0 pCi/L N PV-PV-198AR-0316 PV-198AR 03/16/2016 Tritium <287 pCi/L N REG PV-PV-198AR-0316 PV-198AR 03/16/2016 Cesium-137
<3.1 pCi/L N REG PV-PV-198AR-0316 PV-198AR 03/16/2016 Cobalt-60
<1.3 pCi/L N REG PV-PV-198AR-0316 PV-198AR 03/16/2016 Cesium-134
<1.6 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Tritium <299 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Cesium-137
<1.0 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Cobalt-60
<1.4 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Cesium-134
<1.8 pCi/L N REG PV-PV-R2AR-0216 PV-R2AR 02/03/2016 Tritium <303 pCi/L N REG PV-PV-R2AR-0216 PV-R2AR 02/03/2016 Cesium-137
<1.0 pCi/L N REG PV-PV-R2AR-0216 PV-R2AR 02/03/2016 Cobalt-60
<1.4 pCi/L N REG PV-PV-R2AR-0216 PV-R2AR 02/03/2016 Cesium-134
<1.9 pCi/L N REG PV-PV-R2AR-1016 PV-R2AR 10/12/2016 Tritium <288 pCi/L N REG PV-PV-R2AR-1016 PV-R2AR 10/12/2016 Cesium-137
<0.5 pCi/L N REG PV-PV-R2AR-1016 PV-R2AR 10/12/2016 Cobalt-60
<0.5 pCi/L N REG PV-PV-R2AR-1016 PV-R2AR 10/12/2016 Cesium-134
<0.5 pCi/L N REG PV-PV-193A-1116 PV-193A 11/08/2016 Tritium <289 pCi/L N 


PV-PV-193A-1116 PV-193A 11/08/2016 Cesium-137
Figure 6-6 Low Population Zone DELETED Refer to UFSAR Figure 2.1-15 82            ODCM Rev. 27
<0.8 pCi/L N PV-PV-193A-1116 PV-193A 11/08/2016 Cobalt-60
<0.2 pCi/L N PV-PV-193A-1116 PV-193A 11/08/2016 Cesium-134
<0.9 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Tritium <289 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Cesium-137
<1.7 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Cobalt-60
<1.9 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Cesium-134
<1.6 pCi/L N   


APPENDIX E 2015 ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT CORRECTION
7.0    RADIOLOGICAL REPORTS


OFFSITE DOSE CALCULATION MANUALPALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 REVISION 27Originator______________________________________Technical Reviewer______________________________________
===7.1 Requirement===
Director, RadiationProtection______________________________________PRB______________________________________
Annual Radioactive Effluent Release Report
Effective Date:
* 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.
McDowell, Joshua (Z08270)Digitally signed by McDowell, Joshua (Z08270)DN: cn=McDowell, Joshua (Z08270)
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.
Reason: I am the author of this document Date: 2016.03.29 13:47:09 -07'00' Routolo, Robert
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. 27


M(Z99739)Digitally signed by Routolo, Robert
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. 27


M(Z99739)DN: cn=Routolo, Robert M(Z99739)
===7.2 Requirement===
Reason: I have reviewed this document Date: 2016.03.24 10:42:46 -07'00' Moeller, Carl (Z09119)Digitally signed by Moeller, Carl (Z09119)
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 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. 27


DN: cn=Moeller, Carl (Z09119)
APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses.
Date: 2016.03.25 06:25:14
The determination of a controlling location for implementation of 10CFR50 for radioiodines and particulates is known to be a function of:
(1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptors 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. 27


-07'00'McGhee, Mark A (Z65028)Digitally signed by McGhee, Mark A (Z65028)DN: cn=McGhee, Mark A(Z65028)
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 10 CFR 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.
Reason: PRB Chairman Approval Date: 2016.03.24 11:39:05 -07'00' 03/25/2016 ODCM Rev. 27TABLE OF CONTENTS TITLEPAGE
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 II.A and II.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 mrems/year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year. This 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. 27


==1.0INTRODUCTION==
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.
11.1Liquid Effluent Pathways11.2Gaseous Effluent Pathways21.3Nuisance Pathways2 1.4Meteorology42.0GASEOUS EFFLUENT MONITOR SETPOINTS52.1Requirements: Gaseous Monitors52.1.1Surveillance Requirements5 2.1.2Implementation of the Requirements122.1.2.1Equivalent Dose Factor Determination132.1.2.2Site Release Rate Limit (QSITE)142.1.2.3Unit Release Rate Limits (QUNIT)152.1.2.4Setpoint Determination152.1.2.5Monitor Calibration163.0GASEOUS AND LIQUID EFFLUENT DOSE RATES173.1Requirements: Gaseous Effluents173.1.1Surveillance Requirements173.1.2Implementation of the Requirements183.2Requirements:  Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System-Concentration263.2.1Surveillance Requirements26 3.2.2Implementation of the Requirements264.0GASEOUS & LIQUID EFFLUENTS - DOSE314.1Requirements: Noble Gases314.1.1Surveillance Requirements31 4.1.2Implementation of the Requirement: Noble Gas324.2Requirement: Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate FormWithHalf-Lives Greater Than 8Days33 4.2.1Surveillance Requirements334.2.2Implementation of the Requirement344.3Requirements: Gaseous Radwaste Treatment364.3.1Surveillance Requirements364.3.2Implementation of the Requirement374.4Requirements: Liquid Effluents574.4.1Surveillance Requirements574.4.2Implementation of the Requirements57 i
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 ponds 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.
ODCM Rev. 27TABLE OF CONTENTS TITLEPAGE5.0TOTAL DOSE AND DOSE TO PUBLIC ONSITE585.1Requirement: Total Dose585.1.1Surveillance Requirements585.1.2Implementation of the Requirement586.0RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)626.1Requirement: REMP626.1.1Surveillance Requirements636.1.2Implementation of the Requirements636.2Requirement: Land Use Census716.2.1Surveillance Requirements716.2.2Implementation of the Requirements716.3Requirement: Interlaboratory Comparison Program726.3.1Surveillance Requirements726.3.2Implementation of the Requirements727.0RADIOLOGICAL REPORTS837.1Requirement: Annual Radioactive Effluent Release Report837.2Requirement: Annual Radiological Environmental Operating Report85APPENDIX ADETERMINATION OF CONTROLLING LOCATION86 APPENDIX BBASES FOR REQUIREMENTS872.1RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION873.1GASEOUS EFFLUENT - DOSE RATE873.2SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITEEVAPORATION PONDS - CONCENTRATION884.1GASEOUS EFFLUENT - DOSE, Noble Gases884.2GASEOUS EFFLUENT - DOSE - Iodine-131, Iodine-133, Tritium, andAllRadionuclidesin Particulate Form With Half-Lives Greater Than8Days894.3GASEOUS RADWASTE TREATMENT894.4SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITEEVAPORATION PONDS - DOSE905.1TOTAL DOSE AND DOSE TO PUBLIC ONSITE906.1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)916.2LAND USE CENSUS916.3INTERLABORATORY COMPARISON PROGRAM91APPENDIX CDEFINITIONS92APPENDIX DREFERENCES96 ii ODCM Rev. 27LIST OF TABLESTABLEPAGE TITLE1-1NUISANCE PATHWAYS32-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION6 2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS103-1RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM20 3-2DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES ATTHESITE BOUNDARY233-3DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS24 3-4P i VALUES FOR THE INHALATION PATHWAY253-5RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM27 3-6RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION30 3-7RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS304-1Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY39 4-2Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - ADULT RECEPTOR 404-3Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - TEEN RECEPTOR 414-4Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR 424-5Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - ADULTRECEPTOR434-6Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - TEENRECEPTOR444-7Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILDRECEPTOR454-8Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - ADULTRECEPTOR464-9Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEENRECEPTOR474-10Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - CHILDRECEPTOR48iii ODCM Rev. 27LIST OF TABLESTABLEPAGE TITLE4-11Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR 494-12Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - ADULTRECEPTOR504-13Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - TEENRECEPTOR514-14Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILDRECEPTOR524-15Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTOR 534-16PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT l544-17PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2554-18PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3566-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM64 6-2REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES686-3DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS696-4RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS73C-1FREQUENCY NOTATION95 iv ODCM Rev. 27LIST OF FIGURESFIGUREPAGE TITLE6-1Radiological Environmental Monitoring Program Sample Sites 0 - 10 miles776-2Radiological Environmental Monitoring Program Sample Sites 10 - 35 Miles786-3Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED796-4Site Exclusion Area Boundary DELETED806-5Gaseous Effluent Release Points816-6Low Population Zone DELETED82 v
This requirement applies to the secondary system liquid waste discharges of radioactive materials from all reactor units to the onsite evaporation ponds.
1ODCM Rev. 2
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 II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section II.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. 27


==71.0INTRODUCTION==
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 II.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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 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.
The Offsite Dose Calculation Manual (ODCM) implements the program elements which are requiredby the Administrative Controls section of the Technical Specifications. The ODCM contains theoperational requirements, the surveillance requirements, and actions required if the operationalrequirements are not met for the Radioactive Effluent Controls Program and the RadiologicalEnvironmental Monitoring Program to assure compliance with 10CFR20.1302, 40CFR Part190,10CFR50.36a, and AppendixI to 10CFR Part50. The Technical Specifications, Section3.0, alsoapply to the ODCM. Substitute the word Requirements for Limiting Condition for Operation. Itshould be noted that the hot and cold shutdown and operability requirements in Technical Specification3.0.3 and 3.0.4 do not apply to any of the requirements contained in this ODCM. TheODCM also contains descriptions of the information that should be included in the AnnualRadiological 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 resultingfrom radioactive effluents, in the calculation of gaseous effluent monitor Alarm/Trip Setpoints, and inthe 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 assurecompliance with the regulatory requirements detailed in the ODCM. Methods are included forperforming dose projections to assure compliance with the gaseous treatment system operability sections of the ODCM. The ODCM utilizes information from NRC Regulatory Guide1.109,Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose ofEvaluating Compliance with 10CFR Part50, AppendixI, October1977, and NRC NUREG0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,October1978. NUREG0133 utilizes some of the key information in Regulatory Guide1.109 toprovide methods which were used in the preparation of the radiological effluent TechnicalSpecifications and which have now been transferred to the ODCM in accordance with NRC GenericLetter89-01, Implementation of Programmatic Controls for Radiological Effluent TechnicalSpecifications in the Administrative Controls Section of the Technical Specifications and theRelocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the ProcessControl Program, January31,1989, and NUREG1301, Offsite Dose Calculation Manual Guidance:Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter89-01,Supplement No.1, April1991. Further guidance for the implementation of the new 10CFR Part20,effective January1,1994, was obtained from the Federal Register, Vol.58, December23,1993. It isrecognized that this is only draft guidance, however, it is the only guidance for referencing the new 10CFR20 in the ODCM. 1.1Liquid Effluent PathwaysDose calculation methodology for radioactive liquid effluents is not included in this manual due tothe desert location of the plant, the hydrology of the area, and the fact that there are no liquid releasesto areas at or beyond the SITE BOUNDARY during normal operation. All liquid discharges to theonsite evaporation ponds are controlled by Section 3.2. The impact of postulated accidental seepageson the groundwater system, and in particular on the existing wells located in the 5-mile zone aroundthe site area has been calculated and analyzed in Section2.4.13.3 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.
This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.
2ODCM Rev. 271.2Gaseous Effluent PathwaysAll gaseous effluents are treated as ground level releases and are considered to be long-term asdiscussed in NUREG-0133, Preparation of Radiological Effluent Technical Specifications forNuclear Power Plants. This includes the containment purge and Waste Gas Decay Tank releases aswell as the normal ventilation system and condenser vacuum exhaust releases. All releases are eithergreater than 500hours in duration or are made at random, not depending upon atmosphericconditions or time of day. The releases are lumped together and calculated as an entity. Historicalannual average X/Q values are used throughout this manual for all gaseous effluent setpoint and dosecalculations. Airborne releases are further subdivided into two subclasses:1.2.1Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form with Half-livesGreater than Eight DaysIn this model, a controlling location is identified for assessing the maximum exposure to aMEMBER OF THE PUBLIC for the various pathways and to critical organs. Infant exposureoccurs through inhalation and any actual milk pathway. Child, teenager and adult exposure derives from inhalation, consumed vegetation pathways, and any actual milk and meatpathways. Dose to each of the seven organs listed in Regulatory Guide1.109 (bone, liver, totalbody, thyroid, kidney, lung and GI-LLI) are computed from individual nuclide contributions ineach sector. The largest of the organ doses in any sector is compared to 10CFR50, AppendixIdesign objectives. The release rates of these nuclides will be converted to instantaneous doserates for comparison to the limits of 10CFR20.1.2.2Noble GasesThe air dose from both the beta and gamma radiation component of the noble gases will beassessed and compared to the 10CFR50, AppendixI design objectives. The noble gas releaserate will be converted to instantaneous dose rates for comparison to the limits of 10CFR20.Section2.0 of this manual discusses the methodology to be used in determining effluentmonitor alarm/trip setpoints to assure compliance with the 10CFR Part20 limits asimplemented in Section3.0. Section4.0 discusses the methods to assure releases are As LowAs Reasonably Achievable (ALARA) in accordance with AppendixI to 10CFR Part50.Methods are described in Section5.0 for determining the annual cumulative dose to a MEMBER OF THE PUBLIC from gaseous effluents and direct radiation to assure compliancewith 40CFR Part190.The requirements for the Annual Radiological Effluent Release Report and the RadiologicalEnvironmental Monitoring Program, including the Annual Land Use Census and the Interlaboratory Comparison Program, and the Annual Environmental Report are described inSections6.0 and 7.0 of this manual.1.3Nuisance PathwaysThis section addresses the potential release pathways which should not contribute more than 10% ofthe doses evaluated in this manual. Table1-1 lists examples of potential release pathways. TheODCM methodology for calculation of doses will be applied to an applicable release pathway if alikely potential arises for contributing more than 10% of the doses evaluated in this manual.
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 II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
3ODCM Rev. 27TABLE 1-1NUISANCE PATHWAYS(EXAMPLES)Evaporation PondCooling 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 Outage Support Facility MAR 2016 4ODCM Rev. 271.4MeteorologyHistorical annual average atmospheric dispersion (X/Q) and deposition (D/Q) data, based on nineyears of meteorological data, and given in Table 3-2 for each of the three nuclear generating units areused to demonstrate compliance with the ODCM Requirements. These Requirements include:Section2.0 Gaseous Effluent Monitor Setpoints;Section3.0Gaseous and Liquid Effluent - Dose RateSection4.0Gaseous and Liquid Effluent - Dose Section5.0Total Dose and Dose to Public Onsite Sections2.0 and 3.0 specify utilizing the highest X/Q or D/Q meteorological dispersion parameter atthe Site Boundary for any of the three units as applicable. Using the highest dispersion parameter forany of the units provides a conservative assumption to assure compliance with the higher 10CFRPart20 limits.Section4.0 specifies utilizing the highest X/Q at the Site Boundary for the particular unit, fromTable3-2 for noble gases. The highest X/Q and D/Q are utilized for the particular units releases asapplicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathways location (site boundary using Table3-2 or other controlling locations using Table4-16,4-17, or 4-18).Section5.0 specifies utilizing the highest X/Q for the particular units releases at the controllinglocation from Table4-16, 4-17, or 4-18, for noble gases. The highest X/Q and D/Q are utilized for theparticular units releases as applicable for gases other than noble gases at the controlling pathwayslocation using Table4-16, 4-17, or 4-18.Section7.0 requires that the meteorological conditions concurrent with the time of release ofradioactive materials in gaseous effluents, as determined by sampling frequency and measurement,shall be used for determining the gaseous pathway doses.
This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.
5ODCM Rev. 272.0GASEOUS EFFLUENT MONITOR SETPOINTS2.1Requirements: Gaseous MonitorsThe radioactive gaseous effluent monitoring instrumentation channels shown in Table2-1 shall beFUNCTIONAL with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.0are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted inaccordance with the methodology and parameters in Section2.1.2.Applicability:As shown in Table 2-1.Action: a.With the low range radioactive gaseous effluent monitoring instrumentation channel alarm/tripsetpoint less conservative than required by the above Requirement, immediately suspend therelease of radioactive gaseous effluents monitored by the affected channel, or declare the channelnonfunctional, or change the setpoint so it is acceptably conservative.
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.
b.With less than the minimum number of radioactive gaseous effluent monitoring instrumentationchannels FUNCTIONAL, take the ACTION shown in Table2-1. Restore the nonfunctional instrumentation to FUNCTIONAL status within 30days or, if unsuccessful, explain in the nextAnnual Radioactive Effluent Release Report why this nonfunctionality was not corrected withinthe time specified.2.1.1Surveillance Requirementsa.Each radioactive gaseous effluent monitoring instrumentation channel shall bedemonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operationsat the frequencies shown in Table 2-2.b.The specified Frequency for each Surveillance Requirement is met if the SurveillanceRequirement is performed within 1.25 times the interval specified in the Frequency, asmeasured from the previous performance or as measured from the time a specifiedcondition of the Frequency is met.For Frequencies specified as Prior to each release, the above interval extension does notapply.For Frequencies specified as Once the above interval extension does not apply.If a Completion Time requires periodic performance on a once per . . . basis, the aboveFrequency extension applies to each performance after the initial performance.MAR 2016 MAR 2016MAR 2016MAR 2016MAR 2016 6ODCM Rev. 27TABLE 2-1RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONINSTRUMENT MINIMUM CHANNELS FUNCTIONALAPPLICABILITYACTION1.GASEOUS RADWASTE SYSTEMa.Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release #RU-121#35b.Flow Rate Monitor1#362.NOT USED 3.DELETED 4.PLANT VENT SYSTEMA.Low Range Monitorsa.Noble Gas Activity Monitor #RU-1431*37b.Iodine Sampler1*40c.Particulate Sampler1*40d.Flow Rate Monitor1*36e.Sampler Flow Rate Measuring Device1*36B.High Range Monitorsa.Noble Gas Activity Monitor #RU-1441*42b.Iodine Sampler1*42c.Particulate Sampler1*42d.Sampler Flow Rate Measuring Device1*42 MAR 2016 7ODCM Rev. 275.FUEL BUILDING VENTILATION SYSTEMA.Low Range Monitorsa.Noble Gas Activity Monitor #RU-1451##37, 41b.Iodine Sampler1##40c.Particulate Sample1##40d.Flow Rate Monitor1##36e.Sampler Flow Rate Measuring Device1##36B.High Range Monitorsa.Noble Gas Activity Monitor #RU-1461##42b.Iodine Sampler1##42c.Particulate Sample1##42 d.Sampler Flow Rate Measuring Device1##42TABLE 2-1 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONINSTRUMENTMINIMUM CHANNELS FUNCTIONALAPPLICABILITYACTION 8ODCM Rev. 27Table 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 beingsupplied 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 FUNCTIONAL less than required by the Minimum ChannelsFUNCTIONAL requirement, the contents of the tank(s) may be released to the environmentprovided that prior to initiating the release:a.At least two independent samples of the tanks contents are analyzed, andb.At least two technically qualified members of the facility staff independently verify therelease rate calculations and discharge valve lineup;Otherwise, suspend release of radioactive effluents via this pathway.ACTION 36 -With the number of channels FUNCTIONAL less than required by the Minimum ChannelsFUNCTIONAL 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 FUNCTIONAL less than required by the Minimum ChannelsFUNCTIONAL requirement, effluent releases via this pathway may continue provided theactions of (a) or (b) or (c) are performed:a.Initiate the Preplanned Alternate Sampling Program to monitor the appropriateparameter(s).b.Place moveable air monitors in-line.
89                                        ODCM Rev. 27
c.Either take grab samples at least once per 12hours, OR obtain gas channel monitorreadings locally at least once per 12hours if the channel is functional locally butnonfunctional due to loss of communication with the minicomputer. The surveillance requirements of Section2.1.1 must be performed at the required frequencies for thechannel to be functional locally.ACTION 38 -NOT USED ACTION 39 -NOT USEDACTION 40 -With the number of channels FUNCTIONAL less than required by the Minimum ChannelsFUNCTIONAL requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table3-1within one hour after the channel has been declared nonfunctional.ACTION 41 -With the number of channels FUNCTIONAL less than required by the Minimum ChannelsFUNCTIONAL requirements, comply with Technical Requirements Manual TLCO 3.3.108.MAR 2016MAR 2016MAR 2016MAR 2016MAR 2016MAR 2016 9ODCM Rev. 27 Table 2-1 (Continued)TABLE NOTATIONACTION 42 -With the number of channels FUNCTIONAL less than required by the Minimum ChannelsFUNCTIONAL requirement initiate the Preplanned Alternate Sampling Program to monitorthe appropriate parameter(s) within 72 hours, and:a.Either restore the nonfunctional channel(s) to FUNCTIONAL status within 7 days of theevent, orb.Prepare and submit a Special Report to the Commission within 14 days following theevent outlining the action(s) taken, the cause of the nonfunctionality, and the plans andschedule for restoring the system to FUNCTIONAL status.MAR 2016 MAR 2016MAR 2016 10ODCM Rev. 27TABLE 2-2RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSINSTRUMENTCHANNEL CHECKSOURCE CHECKCHANNEL CALIBRATION CHANNELFUNCTIONAL TESTMODE IN WHICH SURVEILLANCE IS REQUIRED1.GASEOUS RADWASTE SYSTEMa.Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release RU-12PP(7)R(3)Q(1),(2),P####b.Flow Rate MonitorPN.A.RQ,P####2.DELETED3.DELETED4.PLANT VENT SYSTEM(RU-143 and RU-144)a.Noble Gas Activity MonitorD(5)M(7)R(3)Q(2)*b.Iodine SamplerN.A.N.A.N.A.N.A.*
c.Particulate SamplerN.A.N.A.N.A.N.A.*d.Flow Rate MonitorD(6)N.A.RQ*e.Sampler Flow Rate Measuring DeviceD(6)N.A.RQ*5.FUEL BUILDING VENTILATION SYSTEM(RU-145 and RU-146)a.Noble Gas Activity MonitorD(5)M(7)R(3)Q(2)##b.Iodine SamplerN.A.N.A.N.A.N.A.##c.Particulate SampleN.A.N.A.N.A.N.A.##d.Flow Rate MonitorD(6)N.A.RQ##e.Sampler Flow Rate Measuring DeviceD(6)N.A.RQ##
11ODCM Rev. 27 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 beingsupplied 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 theinsertion of a simulated alarm condition.(1)The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathwayoccurs if the instrument indicates measured levels above the alarm/trip setpoint.(2)The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciationoccurs 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 standardscertified by the National Institute of Standards and Technology (NIST) or using standards that have beenobtained from suppliers that participate in measurement assurance activities with NIST. These standardsshall permit calibrating the system over its intended range of energy and measurement range. Forsubsequent 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-lineand 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.
12ODCM Rev. 272.1.2Implementation of the RequirementsThe general methodology for establishing low range gaseous effluent monitor setpoints isbased upon a site release rate limit in
&#xb5;Ci/sec derived from site specific meteorologicaldispersion 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 individualvent will result in exceeding the limits in Section3.1. 80% of Section3.1 limits is consideredto be the site release rate limit. The site release rate limit will be allocated among the licensedunits release points. The unit release rate limit will then be utilized for the determination ofgaseous effluent monitor setpoints. A fraction of the unit release rate limit is then allotted toeach release point and its monitor alert setpoint (&#xb5;Ci/cc) is derived using actual or fan designflow rates.Administrative values are used to reduce each setpoint to account for the potential activity inother releases. These administrative values shall be reviewed based on actual release data. For the purpose of implementation of Section2.1, the alarm setpoint levels for low rangeeffluent noble gas monitors are established to ensure that personnel are alerted when the noblegas releases are at a rate such that if the releases would continue for the year they wouldapproach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose in Section 3.1.
The equations in Section3.1 of this manual provide the methodology for calculating thegaseous effluent dose rate.The evaluation of doses due to releases of radioactive material can be simplified by the use ofequivalent dose factors as defined in Section2.1.2.1.The equivalent dose factors will be evaluated periodically to assure that the best informationon isotopic distribution is being used for the dose equivalent value.
13ODCM Rev. 272.1.2.1Equivalent Dose Factor DeterminationThe equivalent whole body dose factor is calculated as follows:(2-1)Where: K eq=the equivalent whole body dose factor weighted by historicalradionuclide distribution in releases in mrem/yr per
&#xb5;Ci/m 3.K i=the whole body dose factor due to gamma emissions for eachidentified noble gas radionuclide i, in mrem/yr per
&#xb5;Ci/m 3 fromTable3-3.f i=the fraction of noble gas radionuclide i in the total noble gasradionuclide mix.The equivalent skin dose factor is calculated as follows:(2-2)Where:(L+1.1M)eq=the equivalent skin dose factor due to beta and gamma emissions fromall noble gases released, weighted by the historical radionuclidedistribution in releases in mrem/yr per
&#xb5;Ci/m 3.L i=the skin dose factor due to the beta emissions for each identified noblegas radionuclide i, in mrem/yr per
&#xb5;Ci/m 3 from Table3-3.
M i=the air dose factor due to gamma emissions for each identified noblegas radionuclide i, in mrad/yr per
&#xb5;Ci/m 3 from Table3-3.
f i=the fraction of noble gas radionuclide i in the total noble gasradionuclide mix.1.1 =unit conversion constant of 1.1mrem/mrad converts air dose to skindose.K eq K i ()f i ()[]i=L1.1M+()eq L i1.1M i+()f i ()[]i=
14ODCM Rev. 272.1.2.2Site Release Rate Limit (QSITE)The release rates corresponding to 80% of the whole body (Q WB) and skin (Q SK) doserate limits are calculated using the equivalent dose factors defined in Section2.1.2.1.The site release rate limit (QSITE) is the lower of Q WB or Q SK, thus assuring that themore restrictive dose rate limit will not be exceeded.
The Q SITE is established as follows:(2-3)Where: Q SITE,WB=the site release rate, in
&#xb5;Ci/sec, that would deliver a dose rate 80% ofthe whole body dose rate limit, D WB.D WB=whole body dose rate limit of 500mrem/yr.
K eq=equivalent whole body dose factor, in mrem/yr per
&#xb5;Ci/m 3 weightedby the historical radionuclide distribution.(X/Q)SITE=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 inthe radionuclide mix and to ensure that Site Boundary dose rate limitswill not be exceeded.(2-4)Where: QSITE,SK=the site release rate limit, in
&#xb5;Ci/sec, that would deliver a dose rate80% of the skin dose rate limit, D SK.D SK=skin dose rate limit of 3000mrem/yr.(L+1.1M)eq=equivalent skin dose factor, in mrem/yr per
&#xb5;Ci/m 3, weighted by theradionuclide distribution.(X/Q)SITE=8.91E-06, the highest calculated annual average dispersion parameter,in sec/m 3, at the Site Boundary for any of the three units, fromTable3-2.0.8=administrative factor to compensate for any unexpected variability inthe radionuclide mix and to ensure that Site Boundary dose rate limitswill not be exceeded.After determination of the QSITE whole body and skin dose rates (equations2-3 and2-4, respectively), the most conservative result will be used as QSITE, the site releaserate limit.
QSITE,WB D WB ()0.8 ()K eq ()X/Q ()SITE----------------------------------------
=QSITE,SK D SK ()0.8 ()L1.1M+()eqX/Q ()SITE-----------------------------------------------------------
=
15ODCM Rev. 272.1.2.3Unit Release Rate Limits (QUNIT)Typically QSITE will be divided equally among operating units. If operational historydictates a larger fraction of the Q SITE be assigned to a specific unit then a weightedaverage of each units contribution to the Q SITE will be utilized to determine the QUNIT.QUNIT=(fUNIT) (Q SITE)(2-5)Where: QUNIT=unit release rate limit, in
&#xb5;Ci/sec.fUNIT=the fraction (< 1) of noble gas historically released from a specificoperating unit to the total of all noble gas released from the site.
Q SITE=the site release rate limit, in
&#xb5;Ci/sec determined in Section2.1.2.2.2.1.2.4Setpoint DeterminationTo comply with the requirements in Section2.1, the alarm/trip setpoints can now beestablished using the unit release rate limit (Q UNIT) to ensure that the noble gas releasesdo not exceed the dose rate limits.To allow for multiple sources of releases from different or common release points, theeffluent 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 alsobe adjusted in accordance with Nuclear Administrative and Technical Manualprocedures to account for monitor-specific characteristics.Monitors RU-143 and RU-145The alarm/trip setpoint for Monitors RU-143 and RU-145 is calculated as follows:(2-6)Where: MonitorSetpoint=the setpoint for the effluent monitor, in
&#xb5;Ci/cc, which provides a safemargin of assurance that the allowable dose rate limits will not be exceeded.QUNIT=unit release rate limit, in
&#xb5;Ci/sec, as determined in Section2.1.2.3.Flow Rate=the flow rate, in cfm, from flow rate monitors or the fan design flowrate for the release source under consideration.472=conversion factor, cubic centimeter/second per cubic feet/minute.
a=fraction of QUNIT allocated for a specific release point. The sum ofthese administrative values shall be less than or equal to one.Monitor Setpoint QUNIT ()a ()472 ()FlowRate ()--------------------------------------------
-
16ODCM Rev. 27Monitor RU-12The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, iscalculated as follows:(2-7)Where: Monitor Setpoint=the setpoint for the monitor, in
&#xb5;Ci/cc at STP, which provides a safemargin of assurance that the allowable dose rate limits will not beexceeded.QUNIT=unit release rate limit, in
&#xb5;Ci/sec, as determined in Section2.1.2.3.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
&#xb5;Ci/cc.a=fraction of QUNIT allocated for a specific release point. Thisadministrative value should be equal to or less than the administrativevalue used for the Plant Vent.0.9=an administrative value to account for potential increases in activityfrom other contributors to the same release point.472=conversion factor, cubic centimeter/second per cubic feet/minute.
If there is no release associated with this monitor, the monitor setpoint should beestablished as close as practical to background to prevent spurious alarms, and yetassure an alarm should an inadvertent release occur.2.1.2.5Monitor CalibrationThe Radiation Level Conversion Factor (RLF) for each monitor is entered into theRadiation Monitoring System Database and may change whenever the monitor iscalibrated. Calibration is performed in accordance with Nuclear Administrative andTechnical Manual procedures.Monitor setpoint Q UNIT ()a ()0.9 ()H ()PF ()472 ()-[]FlowRate ()472 ()----------------------------------------------------------------------------------------
17ODCM Rev. 273.0GASEOUS AND LIQUID EFFLUENT DOSE RATES3.1Requirements: Gaseous EffluentsThe dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 6-4and Figure 6-5) shall be limited to the following:
a.For noble gases: Less than or equal to 500mrems/yr to the total body and less than or equal to3000mrems/yr to the skin, and b.For I-131 and I-133, for tritium, and for all radionuclides in particulate form with half-livesgreater 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).3.1.1Surveillance Requirementsa.The dose rate due to noble gases in gaseous effluents shall be determined to be within theabove limits in accordance with the methods contained in Section3.1.2.b.The dose rate due to I-131, I-133, tritium and all radionuclides in particulate form withhalf-lives greater than 8days in gaseous effluents shall be determined to be within theabove limits in accordance with the methods contained in Section3.1.2 by obtainingrepresentative samples and performing analyses in accordance with the sampling andanalysis program specified in Table3-1.
18ODCM Rev. 273.1.2Implementation of the RequirementsNoble GasesNoble gas activity monitor setpoints are established at release rates which permit correctiveaction to be taken before exceeding the 10CFR20 annual dose limits as described inSection2.0. The requirements for sampling and analysis of continuous and batch effluentreleases are given in Table3-1. The methods for sampling and analysis of continuous andbatch effluent releases are given in the Nuclear Administrative and Technical Manual procedures. The dose rate in unrestricted areas shall be determined using the followingequations.For whole body dose rate:(3-1)For skin dose rate:(3-2)Where: K i=the whole body dose factor due to gamma emissions for each identified noblegas radionuclide i, in mrem/yr per
&#xb5;Ci/m 3 from Table3-3.
Q i=the release rate of radionuclide i, in
&#xb5;Ci/sec.(X/Q)SITE=8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3, for any of the three units, from Table3-2.
D WB=the annual whole body dose rate (mrem/yr.).
L i=the skin dose factor due to the beta emissions for each identified noble gasradionuclide i, in mrem/yr per
&#xb5;Ci/m 3 from Table3-3.
M i=the air dose factor due to gamma emissions for each identified noble gasradionuclide i, in mrad/yr per
&#xb5;Ci/m 3 from Table3-3.
D SK=the annual skin dose rate (mrem/yr).1.1=unit conversion constant of 1.1mrem/mrad converts air dose to skin dose.
D WB K i ()X/Q ()SITE Q i ()[]i=D SK L i1.1M i+()X/Q ()SITE Q i ()[]i=
19ODCM Rev. 27I-131, I-133, tritium and radionuclides in particulate form with half-lives greater than 8 daysThe 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 8days, are given inthe applicable Nuclear Administrative and Technical Manual procedures. Additional monthly and quarterly analyses shall be performed in accordance with Table3-1. The total organ doserate in unrestricted areas shall be determined by the following equation:(3-3)Where: P i=the dose factor, in mrem/yr per
&#xb5;Ci/m 3, for radionuclide i, for the inhalationpathway, from Table 3-4.(X/Q)SITE=8.91E-06, the highest calculated annual average dispersion parameter, in sec/m 3, at the Site Boundary, for any of the three units, Q i=the release rate of radionuclide i, in
&#xb5;Ci/sec D o=the total organ dose rate (mrem/yr).
D o P i ()X/Q ()SITE Q i ()[]i=
20ODCM Rev. 27TABLE 3-1RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMGASEOUS RELEASE TYPESAMPLING FREQUENCY MINIMUM ANALYSIS FREQUENCYTYPE OFACTIVITY ANALYSISLOWER LIMIT OF DETECTION (LLD) (&#xb5;Ci/ml)aA.Waste Gas Storage PEach Tank Grab Sample PEach TankPrincipal Gamma Emitters g1.0E-04B.Containment Purge PEach Purge b,cGrab Sample PEach Purgeb,cPrincipal Gamma Emitters g1.0E-04H-31.0E-06C.1.DELETED2.Plant Vent3.Fuel Bldg. Exhaust M b,eGrab Sample M bPrincipal Gamma Emitters g1.0E-04H-31.0E-06Continuous f 4/M dCharcoal SampleI-1311.0E-12I-1331.0E-10Continuous f 4/M dParticulate SamplePrincipal Gamma Emitters g(I-131, Others)1.0E-11Continuous f MComposite Particulate SampleGross Alpha1.0E-11Continuous f QComposite Particulate


SampleSr-89, Sr-901.0E-11D.All Radwaste Types as listed in A., B., and C., above.Continuous f Noble Gas MonitorNoble Gases Gross Beta or Gamma1.0E-06 21ODCM Rev. 27 Table 3-1 (Continued)TABLE NOTATIONaThe 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 offalsely concluding that a blank observation represents a real signal.For a particular measurement system (which may include radiochemical separation):Where:LLD is the a priori lower limit of detection as defined above (as
B-4.4 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 II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to 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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 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.
&#xb5;Ci per unit mass or volume). Currentliterature defines the LLD as the detection capability for the instrumentation only and the MDCminimum detectable concentration, as the detection capability for a given instrument, procedure and typeof sample.
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.
s b is the standard deviation of the background counting rate or of the counting rate of a blank sample asappropriate (as counts per minute),E is the counting efficiency (as counts per transformation),
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.)
V is the sample size (in units of mass or volume),
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.
2.22E6 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), is the radioactive decay constant for the particular radionuclide, andt is the elapsed time between the midpoint of sample collection and time of counting (for planteffluents, not environmental samples).The value of s b used in the calculation of the LLD for a detection system shall be based on the actualobserved variance of the background counting rate or of the counting rate of the blank samples (asappropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for aradionuclide determined by gamma-ray spectrometry the background should include the typicalcontributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and tshould be used in the calculation.It should be recognized that the LLD is defined as an a priori (before the fact) limit representing thecapability of a measurement system and not as an a posteriori (after the fact) limit for a particularmeasurement.
90                                          ODCM Rev. 27
LLD4.66s bE*V*2.22E6*Y*expt-()-------------------------------------------------------------------------------
-=
22ODCM Rev. 27 Table 3-1 (Continued)TABLE NOTATIONbAnalyses shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER changeexceeding 15% of the RATED THERMAL POWER within a 1-hour period if 1) analysis shows that theDOSE 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 morethan a factor of 3. If the associated noble gas vent monitor is nonfunctional, samples must be obtained assoon as possible. Analyses shall be performed within a four-hour period. This requirement does notapply to the Fuel Building Exhaust.cSampling and analyses shall also be performed at least once per 31days when purging time exceeds30days continuous.dSamples shall be changed at least 4 times a month and analyses shall be completed within 48 hours afterchanging (or after removal from sampler). When samples collected for 24hours are analyzed, thecorresponding LLDs may be increased by a factor of 10.eTritium grab samples shall be taken at least monthly from the ventilation exhaust from the spent fuel poolarea, whenever spent fuel is in the spent fuel pool.fThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time periodcovered by each dose or dose rate calculation made in accordance with Requirements 3.1, 4.1 and 4.2 ofthe ODCM.gThe principal gamma emitters for which the LLD specification applies include the followingradionuclides: 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 aremeasurable and identifiable, together with the above nuclides shall also be identified and reported in theAnnual Radioactive Effluent Release Report.MAR 2016 23ODCM Rev. 27


==Reference:==
B-6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculationby NUS Corporation based on 9years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.TABLE 3-2DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES ATTHESITE BOUNDARY DIRECTIONDISTANCE (METERS)UNIT 1 X/Q(SEC/m 3)D/Q (m-2)UNIT 2 DISTANCE (METERS)X/Q(SEC/m 3)D/Q (m-2)UNIT 3 DISTANCE (METERS)X/Q(SEC/m 3)D/Q (m-2)N10374.93E-069.24E-0913183.85E-066.17E-0916613.54E-064.86E-09NNE10574.14E-061.19E-0813423.18E-067.93E-0916932.86E-066.23E-09NE22062.84E-066.84E-0925452.42E-065.34E-0927562.21E-064.65E-09ENE19672.51E-064.43E-0922062.22E-063.64E-0923372.08E-063.30E-09E19272.56E-063.24E-0921632.27E-062.66E-0922902.l4E-062.41E-09ESE19672.61E-062.46E-0920672.32E-062.11E-0920232.37E-062.10E-09SE20493.56E-062.36E-0921013.47E-062.26E-0922563.24E-062.00E-09SSE27303.80E-061.58E-0930263.43E-061.32E-0927863.72E-061.52E-09S30065.07E-061.78E-0926995.16E-061.97E-0923465.90E-062.51E-09SSW22586.52E-063.20E-0918367.90E-064.56E-09l6078.9lE-065.73E-09SW14877.47E-065.65E-0912087.72E-066.88E-09l0578.68E-068.61E-09WSW12514.52E-065.93E-0910145.55E-068.44E-09 8895.34E-068.83E-09W12254.73E-069.49E-09 9935.86E-061.34E-08 8716.72E-061.67E-08WNW12443.76E-066.76E-0910104.67E-069.60E-09 8855.37E-061.19E-08NW12543.43E-065.87E-0911913.62E-066.40E-09l0454.l7E-067.98E-09NNW10693.70E-067.26E-0913422.85E-064.87E-09l56l2.93E-064.58E-09 24ODCM Rev. 27TABLE 3-3DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
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 posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD and other detection limits can be found in Currie, L. A., Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (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/m2.
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. 27


==Reference:==
APPENDIX C DEFINITIONS Note:
Regulatory Guide 1.109, Table B-1.Whole Body Dose Factor K iSkinDose Factor L iGamma Air Dose Factor M iBeta Air Dose Factor N iRadionuclidemrem-m 3yr-&#xb5;Ci mrem-m 3yr-&#xb5;Ci mrad-m 3yr-&#xb5;Cimrad-m 3yr-&#xb5;CiKr-83m7.56E-02------------1.93E+012.88E+02Kr-85m1.17E+031.46E+031.23E+031.97E+03 Kr-851.61E+011.34E+031.72E+011.95E+03Kr-875.92E+039.73E+036.17E+031.03E+04Kr-881.47E+042.37E+031.52E+042.93E+03 Kr-891.66E+041.01E+041.73E+041.06E+04Kr-901.56E+047.29E+031.63E+047.83E+03Xe-13lm9.15E+014.76E+021.56E+021.11E+03 Xe-133m2.51E+029.94E+023.27E+021.48E+03Xe-133 2.94E+023.06E+023.53E+021.05E+03Xe-135m3.12E+037.11E+023.36E+037.39E+02 Xe-1351.81E+031.86E+031.92E+032.46E+03Xe-1371.42E+031.22E+041.51E+031.27E+04Xe-1388.83E+034.13E+039.21E+034.75E+03 Ar-418.84E+032.69E+039.30E+033.28E+03 25ODCM Rev. 27TABLE 3-4 P i VALUES FOR THE INHALATION PATHWAY(mrem/yr/&#xb5;Ci/m 3)NUCLIDEAge GroupOrganP iH-3TEENLIVER1.27E+03CR-51TEENLUNG2.10E+04MN-54TEENLUNG1.98E+06FE-59TEENLUNG1.53E+06CO-58TEENLUNG1.34E+06CO-60TEENLUNG8.72E+06ZN-65TEENLUNG1.24E+06SR-89TEENLUNG2.42E+06SR-90TEENBONE1.08E+08ZR-95TEENLUNG2.69E+06SB-124TEENLUNG3.85E+06I-131CHILDTHYROID1.62E+07 I-133CHILDTHYROID3.85E+06CS-134TEENLIVER1.13E+06CS-137CHILDBONE9.07E+05BA-140TEENLUNG2.03E+06CE-141TEENLUNG6.14E+05CE-144TEENLUNG1.34E+07 26ODCM Rev. 273.2Requirements: Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds orCirculating Water System-ConcentrationThe concentration of radioactive material discharged from secondary system liquid waste to thecirculating water system shall be limited to: 5.0E-07&#xb5;Ci/ml for the principal gamma emitters (except Ce-144)3.0E-06&#xb5;Ci/ml for Ce-1441.0E-06&#xb5;Ci/ml for I-1311.0E-03 &#xb5;Ci/ml for H-3The concentration of radioactive material discharged from secondary system liquid waste to theonsite evaporation ponds shall be limited to: 2.0E-06&#xb5;Ci/ml for Cs-1342.0E-06&#xb5;Ci/ml for Cs-137The concentrations specified in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, for all other isotopesApplicability:
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.
At all times.Action:When any secondary system liquid waste discharge pathway concentration determined in accordancewith the surveillance requirements given below exceeds the above Requirements, divert thatdischarge pathway to the liquid radwaste system without delay or terminate the discharge.3.2.1Surveillance Requirementsa.Secondary system liquid wastes shall be sampled and analyzed according to the samplingand analysis program of Table3-5.3.2.2Implementation of the RequirementsThis requirement is implemented by Nuclear Administrative and Technical Manualprocedures.
Definitions:
27ODCM Rev. 27TABLE 3-5RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMSecondary System Liquid Release PathwayDestinationSampling & Analysis FrequencyNotesType OfActivity AnalysisLower Limit Of Detection (LLD)a (&#xb5;Ci/ml)1.Chemical Waste Neutralizer Tank (CWNT) bRetention TankPEach BatchPrincipal Gamma Emitters c 5.0E-07liquid radwasteN. A.I-1311.0E-06H-31.0E-052.Steam Generator Blowdown Low TDS Sump bcirc. waterPEach Batch1Principal Gamma Emitters c 5.0E-07CWNTN. A.I-1311.0E-06H-31.0E-053.Condensate a.Condensate Polishing Low TDS Sump bcirc. waterPEach Batch3Principal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05CWNTN. A.b.Initial Backwash(low TDS sump) to circ. waterPEach DischargePrincipal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05(low TDS sump) to CWNTN. A.c.Pre-service rinse effluentRetention Tank through SC-N-V069PEach Discharge2Principal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05condenser through SC-N-UV232N. A.d.Overboard condensatecirc water through CD-N-V194PEach DischargePrincipal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05Retention Tank through SC-N-V079PEach Discharge24.Turbine Building Sump dRetention TankDGrab Sample3Principal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05CWNTN. A.
The defined terms of this section appear in capitalized type and are applicable throughout the Requirements sections of this ODCM.
28ODCM Rev. 271Sampling and analysis are required only when concentration for chemical waste neutralizer tank or steam generator activity exc eeds the requirement2RU-200 shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, andCHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3-6. The Alarm/Trip setpoints for RU-200 are set to ensure that theconcentrations in the Retention Tanks do not exceed the Requirement3Sampling and analysis are required only when concentration for chemical waste neutralizer tank or condensate activity exceeds the requirement5.North & South Condenser Area Sumps dRetention TankDGrab Sample3Principal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05CWNTN. A.6.Steam Generator Blowdown to Retention TankRetention Tank through SC-N-V064PEach Discharge2Principal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-057.Retention Tank to Evaporation Pondevaporation pondPEach BatchPrincipal Gamma Emitters cI-131H-3 5.0E-07 1.0E-06 1.0E-05TABLE 3-5RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMSecondary System Liquid Release PathwayDestinationSampling & Analysis FrequencyNotesType OfActivity AnalysisLower Limit Of Detection (LLD)a (&#xb5;Ci/ml)MAR 2016 29ODCM Rev. 27 Table 3-5 (Continued)TABLE NOTATIONaThe LLD is defined as the smallest concentration of radioactive material in a sample that will yield a netcount, above system background, that will be detected with 95% probability with only 5% probability offalsely concluding that a blank observation represents a real signal.For a particular measurement system which may include radiochemical separation:Where:LLD is the a priori lower limit of detection as defined above as microcuries per unit mass or volume, s b is the standard deviation of the background counting rate or of the counting rate of a blank sample asappropriate 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, is the radioactive decay constant for the particular radionuclide, andt is the elapsed time between midpoint of sample collection and time of counting.Typical values of E, V, Y, and t should be used in the calculation.It should be recognized that the LLD is defined as an a priori (before the fact) limit representing thecapability of a measurement system and not as an a posteriori (after the fact) limit for a particularmeasurement.bA 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. cThe principal gamma emitters for which the LLD specification applies include the followingradionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shallalso be measured, but with an LLD of 3.0E-06. This list does not mean that only these nuclides are to beconsidered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall alsobe analyzed and reported in the Annual Radioactive Effluent Release Report. dA continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of asystem that has an input flow during the continuous release LLD4.66s bE*V*2.22E6*Y*expt-()-------------------------------------------------------------------------------
ACTION ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.
-=
CHANNEL CALIBRATION See the Technical Specification definition.
30ODCM Rev. 27TABLE 3-6RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONInstrumentChannel CheckSource CheckChannel CalibrationChannel Functional TestMode in which Surveillance is RequiredRU-200PN. A.RQSee Table 3-7TABLE 3-7RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSSecondary System Liquid Release PathwayMode in which Surveillance is RequiredAction if RU-200 is nonfunctionalPre-service rinse to Retention TanksAt All TimesObtain grab sample at least once per 12 hours and analyze in accordance with section 3.2Condensate overboard to Retention Tanks1-4Obtain grab sample at least once per 12 hours and analyses in accordance with section 3.2Steam Generator Blowdown/Drain to Retention TanksAt All TimesModes 1-4: Suspend the releaseModes 5,6 & defueled: Obtain grab sample at least once per 12 hours and analyze in accordance with sec-tion 3.2MAR 2016 31ODCM Rev. 274.0GASEOUS & LIQUID EFFLUENTS - DOSE4.1Requirements: Noble GasesThe air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at andbeyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-5) shall be limited to the following:
CHANNEL CHECK See the Technical Specification definition.
a.During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than orequal to 10 mrads for beta radiation and, b.During any calendar year: Less than or equal to 10mrads for gamma radiation and less than orequal to 20 mrads for beta radiation.Applicability:
CHANNEL FUNCTIONAL TEST See the Technical Specification definition.
At all times.Action:With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any ofthe above limits, prepare and submit to the Commission within 30days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that havebeen taken to reduce the releases and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the above limits.4.1.1Surveillance Requirementsa.Cumulative dose contributions for the current calendar quarter and current calendar yearfor noble gases shall be determined in accordance with the methodology contained inSection4.1.2 at least once per 31 days.
DOSE EQUIVALENT I-131 See the Technical Specification definition.
32ODCM Rev. 274.1.2Implementation of the Requirement: Noble GasThe air dose in unrestricted areas beyond the site boundary due to noble gases released ingaseous effluents from each unit during any specified time period shall be determined by thefollowing equations:For gamma radiation:
FUNCTIONAL-FUNCTIONALITY Functionality is an attribute of a structure, system, or component SSC(s) that is not controlled by the Technical Specifications (TSs). An SSC not controlled by Tss is functional or has functionality when it is capable of performing its function(s) as set forth in the current licensing basis (CLB). These CLB function(s) may include the capability to perform a necessary and related support function for an SSC(s) controlled by TSs.
D u=(3.17E-08) i [(M i) (X/Q)UNIT (Q i)](4-1)For beta radiation:
MAR 2016 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table C-1.
Du=(3.17E-08) i [(N i) (X/Q)UNIT (Q i)](4-2)Where: M i=the air dose factor due to gamma emissions for each identified noble gasradionuclide i, in mrad/yr per
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.
&#xb5;Ci/m 3 from Table3-3.
92                                    ODCM Rev. 27
N i=the air dose factor due to beta emissions for each identified noble gasradionuclide i, in mrad/yr per
&#xb5;Ci/m 3 from Table3-3.(X/Q)UNIT=the highest calculated annual average dispersion parameter, in sec/m 3, at thesite boundary for the particular Unit, from Table3-2. Optionally, the highestvalue may be used for any Unit calculation.=7.47E-06 from Unit l=7.90E-06 from Unit 2=8.91E-06 from Unit 3 D u=the total gamma air dose, for the particular unit, in mrad, due to noble gasesreleased in gaseous effluents for a specified time period at the SITEBOUNDARY.D u=the total beta air dose, for the particular unit, in mrad, due to noble gasesreleased in gaseous effluents for a specified time period at the SITEBOUNDARY.Q i=the integrated release, from the particular unit, in  
&#xb5;Ci, of each identifiednoble 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 bebased on the calculated dose contribution from each specified time period occurring during thereporting time period.
33ODCM Rev. 274.2Requirement: Iodine-131, Iodine-133, Tritium, and All Radionuclides in ParticulateFormWithHalf-Lives Greater Than 8DaysThe dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and allradionuclides in particulate form with half-lives greater than 8days 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 7.5mrems 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 radionuclidesin particulate form with half-lives greater than 8days, in gaseous effluents exceeding any ofthe above limits, prepare and submit to the Commission within 30days, a Special Report thatidentifies the cause(s) for exceeding the limit and defines the corrective actions that have beentaken to reduce the releases and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the above limits.4.2.1Surveillance Requirementsa.Cumulative dose contributions for the current calendar quarter and current calendar yearfor iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-livesgreater than 8days shall be determined in accordance with the methodology andparameters contained in Section4.2.2 at least once per 31days.
34ODCM Rev. 274.2.2Implementation of the RequirementThe organ dose to an individual from I-131, I-133, tritium, and all radionuclides in particulateform, with half-lives greater than eightdays, in gaseous effluents released to unrestricted areasfrom each reactor unit is calculated using the following expressions:
D ou=(3.17E-08) i [k (R ik W k) (Qi)](4-3)Where: D ou=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 atthe controlling location.
Q i=the quantity of radionuclide i, in
&#xb5;Ci, released in gaseous effluents from aparticular unit.
R ik=the dose factor for each identified radionuclide i, for pathway k (for theinhalation pathway in mrem/yr per
&#xb5;Ci/m 3 and for the food and ground planepathways in m 2 - mrem/yr per
&#xb5;Ci/sec, except H-3, which has units ofmrem/yr per
&#xb5;Ci/m 3) at the controlling location. The R iks for each age groupare given in Tables4-1 through 4-15.3.17E-08=the inverse of seconds per year (yr/sec).


W k=the highest annual average dispersion or deposition parameter for theparticular Unit, used for estimating the dose at the site boundary or to aMEMBER OF THE PUBLIC at the controlling location for the particularUnit. Optionally, the highest value may be used for any Unit calculation.=(X/Q)UNIT, in sec/m 3 for the inhalation pathway and for all tritiumcalculations, for organ dose at the site boundary, from Table3-2.=7.47E-06 from Unit 1=7.90E-06 from Unit 2
APPENDIX C DEFINITIONS (Continued)
=8.91E-06 from Unit 3=(X/Q)UNIT, in sec/m 3 for the inhalation pathway and for all tritiumcalculations, for organ dose at the controlling location, from Table 4-16, 4-17or 4-18.=2.92E-06 from Unit 1=2.19E-06 from Unit 2=2.31E-06 from Unit 3=(D/Q)UNIT, in m-2, for the food and ground plane pathways, for organ dose atthe site boundary, from Table3-2.=1.19E-08 from Unit 1=1.34E-08 from Unit 2=1.67E-08 from Unit 3 35ODCM Rev. 27=(D/Q)UNIT, in m-2, for the food and ground plane pathways, for organ dose atthe controlling location, from Table4-16, 4-17, or 4-18.=3.25E-09 from Unit 1=3.88E-10 from Unit 2
MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant.
=4.21E-10 from Unit 3Residences, vegetable gardens and milk animals located within 5miles of the site will beidentified 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.
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.
The R i values were calculated in accordance with the methodologies in NUREG-0133. Thefollowing site specific information was used to calculate R i:ValueThe length of the grazing season for milk animals (f s).Ref. ER-OL, Section 2.1.3.4.30.75The length of the grazing season for meat animals (f s).Ref. ER-OL, Section 2.1.3.4.40.25The fraction of daily feed derived from pasture while on pasture for milk animals (f p).Ref. ER-OL, Section 2.1.3.4.30.35The fraction of daily feed derived from pasture while on pasture for meat animals (f p).Ref. ER-OL, Section 2.1.3.4.30.05The fraction of year vegetables are grown, (f l) approximation.Ref. ER-OL, Section 2.1.3.4, Table 2.1-8.0.667The annual absolute humidity (g/m 3), H,Ref. UFSAR, Table 2.3-166 36ODCM Rev. 274.3Requirements: Gaseous Radwaste TreatmentThe GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENTSYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge whenthe 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 31days, would exceed 0.2mrad forgamma radiation and 0.4mrad for beta radiation. The VENTILATION EXHAUST TREATMENTSYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge whenthe projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond theSITE BOUNDARY (see Figure 6-4 and Figure 6-5) when averaged over 31days would exceed0.3mrem to any organ of a MEMBER OF THE PUBLIC.Applicability:
OPERABLE-OPERABILITY 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).
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 followinginformation:
MODE See the Technical Specification definition.
a.Identification of the nonfunctional equipment or subsystems and the reason for nonfunctionality, b.Action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status, and c.Summary description of action(s) taken to prevent a recurrence.4.3.1Surveillance Requirementsa.Doses due to gaseous releases from the site shall be projected at least once per 31days, inaccordance with the methodology and parameters in Section4.3.2.MAR 2016 37ODCM Rev. 274.3.2Implementation of the RequirementWhere possible, consideration for expected operational evolutions (i.e., outages, etc.) shouldbe taken in the dose projections.Dose Projection - Noble GasesThe air dose, in mrads is determined using the methodology described in Section4.1.2 of thismanual. This information is used to determine an air dose projection for the next 31days usingthe following equations:For gamma radiation:31 day =D + CD(4-4)For beta radiation:31 day =D + CD(4-5)Where: D=the total gamma air dose in mrads at the site boundary due to noble gasesreleased in gaseous effluents for the previous 31 days.
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.
D=the total beta air dose in mrads at the site boundary due to noble gasesreleased in gaseous effluents for the previous 31 days.
PURGE-PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
CD=any current or projected change in gamma air dose, in mrads, due to noblegases released in gaseous effluents, which could have a significant impact on 31 day .CD=any current or projected change in beta air dose, in mrads, due to noble gasesreleased in gaseous effluents, which could have a significant impact on 31 day .When performing the 31 day dose projection using the Gaseous Radioactive Effluent TrackingSystem (GRETS), D and D will include the dose from any release permits that fall withinthe selected 31 day time period. As a result, the actual dose projection will often be based onthe accumulated dose for a time period greater than 31 days.
RATED THERMAL POWER See the Technical Specification definition.
38ODCM Rev. 27Dose Projection - I-131, I-133, tritium, and all radionuclides in particulate form with half-livesgreater than eight daysThe organ dose, in mrem, is determined using the methodology described in Section4.2.2 ofthis manual. This information is used to determine an organ dose projection for the next31days using the following equation:31day o=D o + CD o(4-6)Where: D o=the total organ dose due to I-131, I-133, tritium, and all radionuclides inparticulate form with half-lives greater than eightdays in mrem, released ingaseous effluents for the previous 31 days.
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
CD o=any current or projected change in organ dose, in mrem, which could have asignificant impact on 31 day o.When performing the 31 day dose projection using the Gaseous Radioactive Effluent TrackingSystem (GRETS), D o will include the dose from any release permits that fall within theselected 31 day time period. As a result, the actual dose projection will often be based on theaccumulated dose for a time period greater than 31 days.
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).
39ODCM Rev. 27TABLE 4-1Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAYNUCLIDET. BODYSKINH-30.00E+000.00E+00CR-514.66E+065.51E+06MN-541.39E+091.63E+09FE-592.73E+083.21E+08CO-583.79E+084.44E+08CO-602.15E+102.53E+10ZN-657.47E+088.59E+08SR-892.16E+042.51E+04SR-900.00E+000.00E+00ZR-952.45E+082.84E+08SB-1245.98E+086.90E+08I-1311.72E+072.09E+07 I-1332.45E+062.98E+06CS-1346.86E+098.00E+09CS-1371.03E+101.20E+10BA-1402.05E+072.35E+07CE-1411.37E+071.54E+07CE-1446.95E+078.04E+07 40ODCM Rev. 27TABLE 4-2Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - ADULT RECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+002.87E+032.87E+032.87E+032.87E+032.87E+032.87E+03CR-510.00E+000.00E+004.00E+042.39E+048.82E+035.31E+041.01E+07MN-540.00E+002.97E+085.66E+070.00E+008.83E+070.00E+009.09E+08FE-591.14E+082.68E+081.03E+080.00E+000.00E+007.49E+078.93E+08CO-580.00E+002.84E+076.38E+070.00E+000.00E+000.00E+005.76E+08 CO-600.00E+001.59E+083.51E+080.00E+000.00E+000.00E+002.99E+09ZN-653.00E+089.56E+084.32E+080.00E+006.39E+080.00E+006.02E+08SR-899.08E+090.00E+002.61E+080.00E+000.00E+000.00E+001.46E+09 SR-905.76E+110.00E+001.41E+110.00E+000.00E+000.00E+001.67E+10ZR-951.08E+063.47E+052.35E+050.00E+005.45E+050.00E+001.10E+09SB-1249.53E+071.80E+063.78E+072.31E+050.00E+007.42E+072.71E+09I-1315.49E+077.85E+074.50E+072.57E+101.35E+080.00E+002.07E+07I-1331.39E+062.42E+067.38E+053.56E+084.22E+060.00E+002.17E+06CS-1344.44E+091.06E+108.64E+090.00E+003.42E+091.13E+091.85E+08 CS-1376.06E+098.29E+095.43E+090.00E+002.81E+099.36E+081.60E+08BA-1409.43E+071.19E+056.18E+060.00E+004.03E+046.78E+041.94E+08CE-1411.73E+051.17E+051.33E+040.00E+005.44E+040.00E+004.48E+08 CE-1443.12E+071.30E+071.67E+060.00E+007.73E+060.00E+001.05E+10 41ODCM Rev. 27TABLE 4-3Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - TEEN RECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+003.36E+033.36E+033.36E+033.36E+033.36E+033.36E+03CR-510.00E+000.00E+005.60E+043.11E+041.23E+047.99E+049.41E+06MN-540.00E+004.41E+088.74E+070.00E+001.31E+080.00E+009.04E+08FE-591.69E+083.94E+081.52E+080.00E+000.00E+001.24E+089.31E+08CO-580.00E+004.16E+079.59E+070.00E+000.00E+000.00E+005.74E+08 CO-600.00E+002.42E+085.45E+080.00E+000.00E+000.00E+003.15E+09ZN-654.11E+081.43E+096.65E+080.00E+009.12E+080.00E+006.04E+08SR-891.43E+100.00E+004.10E+080.00E+000.00E+000.00E+001.70E+09 SR-907.30E+110.00E+001.80E+110.00E+000.00E+000.00E+002.05E+10ZR-951.64E+065.17E+053.56E+050.00E+007.60E+050.00E+001.19E+09SB-1241.47E+082.70E+065.73E+073.33E+050.00E+001.28E+082.96E+09I-1315.29E+077.41E+073.98E+072.16E+101.28E+080.00E+001.47E+07I-1331.29E+062.19E+066.68E+053.06E+083.84E+060.00E+001.66E+06CS-1346.90E+091.62E+107.53E+090.00E+005.16E+091.97E+092.02E+08 CS-1379.86E+091.31E+104.57E+090.00E+004.46E+091.73E+091.87E+08BA-1401.07E+081.31E+056.88E+060.00E+004.44E+048.80E+041.65E+08CE-1412.61E+051.74E+052.00E+040.00E+008.19E+040.00E+004.98E+08 CE-1445.11E+072.12E+072.75E+060.00E+001.26E+070.00E+001.29E+10 42ODCM Rev. 27TABLE 4-4Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTORNUCLIDESBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+005.23E+035.23E+035.23E+035.23E+035.23E+035.23E+03CR-510.00E+000.00E+001.08E+056.02E+041.64E+041.10E+055.75E+06MN-540.00E+006.49E+081.73E+080.00E+001.82E+080.00E+005.45E+08FE-593.79E+086.13E+083.05E+080.00E+000.00E+001.78E+086.38E+08CO-580.00E+006.21E+071.90E+080.00E+000.00E+000.00E+003.62E+08 CO-600.00E+003.70E+081.09E+090.00E+000.00E+000.00E+002.05E+09ZN-657.93E+082.11E+091.31E+090.00E+001.33E+090.00E+003.71E+08SR-893.44E+100.00E+009.83E+080.00E+000.00E+000.00E+001.33E+09 SR-901.22E+120.00E+003.09E+110.00E+000.00E+000.00E+001.64E+10ZR-953.72E+068.17E+057.27E+050.00E+001.17E+060.00E+008.52E+08SB-1243.38E+084.39E+061.19E+087.47E+050.00E+001.88E+082.12E+09I-1319.95E+071.00E+085.68E+073.31E+101.64E+080.00E+008.90E+06I-1332.36E+062.91E+061.10E+065.41E+084.85E+060.00E+001.17E+06CS-1341.57E+102.57E+105.43E+090.00E+007.98E+092.86E+091.39E+08 CS-1372.34E+102.24E+103.31E+090.00E+007.31E+092.63E+091.40E+08BA-1402.20E+081.93E+051.28E+070.00E+006.27E+041.15E+051.11E+08CE-1416.15E+053.07E+054.55E+040.00E+001.34E+050.00E+003.83E+08 CE-1441.24E+083.89E+076.62E+060.00E+002.15E+070.00E+001.01E+10 43ODCM Rev. 27TABLE 4-5Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - ADULTRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+004.33E+024.33E+024.33E+024.33E+024.33E+024.33E+02CR-510.00E+000.00E+003.44E+022.06E+027.58E+014.57E+028.65E+04MN-540.00E+002.71E+065.18E+050.00E+008.08E+050.00E+008.31E+06FE-592.60E+076.11E+072.34E+070.00E+000.00E+001.71E+072.04E+08CO-580.00E+002.84E+066.36E+060.00E+000.00E+000.00E+005.75E+07 CO-600.00E+002.61E+075.76E+070.00E+000.00E+000.00E+004.90E+08ZN-659.97E+073.17E+081.43E+080.00E+002.12E+080.00E+002.00E+08SR-893.41E+070.00E+009.79E+050.00E+000.00E+000.00E+005.47E+06 SR-904.43E+090.00E+001.09E+090.00E+000.00E+000.00E+001.28E+08ZR-952.68E+058.58E+045.81E+040.00E+001.35E+050.00E+002.72E+08SB-1242.67E+065.05E+041.06E+066.48E+030.00E+002.08E+067.59E+07I-1311.36E+051.94E+051.11E+056.37E+073.33E+050.00E+005.13E+04I-1334.56E-037.94E-032.42E-031.17E+001.39E-020.00E+007.14E-03CS-1342.17E+085.17E+084.23E+080.00E+001.67E+085.56E+079.05E+06 CS-1373.11E+084.25E+082.78E+080.00E+001.44E+084.79E+078.22E+06BA-1404.35E+055.46E+022.85E+040.00E+001.86E+023.13E+028.95E+05CE-1418.87E+026.00E+026.80E+010.00E+002.79E+020.00E+002.29E+06 CE-1444.23E+051.77E+052.27E+040.00E+001.05E+050.00E+001.43E+08 44ODCM Rev. 27TABLE 4-6Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - TEENRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+002.58E+022.58E+022.58E+022.58E+022.58E+022.58E+02CR-510.00E+000.00E+002.75E+021.53E+026.03E+013.93E+024.62E+04MN-540.00E+002.07E+064.11E+050.00E+006.18E+050.00E+004.25E+06FE-592.08E+074.85E+071.87E+070.00E+000.00E+001.53E+071.15E+08CO-580.00E+002.19E+065.04E+060.00E+000.00E+000.00E+003.02E+07 CO-600.00E+002.03E+074.56E+070.00E+000.00E+000.00E+002.64E+08ZN-657.01E+072.43E+081.14E+080.00E+001.56E+080.00E+001.03E+08SR-892.88E+070.00E+008.24E+050.00E+000.00E+000.00E+003.43E+06 SR-902.87E+090.00E+007.08E+080.00E+000.00E+000.00E+008.05E+07ZR-952.14E+056.76E+044.65E+040.00E+009.93E+040.00E+001.56E+08SB-1242.18E+064.02E+048.52E+054.95E+030.00E+001.91E+064.40E+07I-1311.13E+051.58E+058.49E+044.61E+072.72E+050.00E+003.13E+04I-1333.82E-036.48E-031.98E-039.04E-011.14E-020.00E+004.90E-03CS-1341.73E+084.07E+081.89E+080.00E+001.29E+084.94E+075.06E+06 CS-1372.58E+083.43E+081.20E+080.00E+001.17E+084.54E+074.88E+06BA-1403.59E+054.40E+022.31E+040.00E+001.49E+022.96E+025.54E+05CE-1417.45E+024.97E+025.71E+010.00E+002.34E+020.00E+001.42E+06 CE-1443.56E+051.47E+051.91E+040.00E+008.80E+040.00E+008.96E+07 45ODCM Rev. 27TABLE 4-7Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILDRECEPTORNUCLIDESBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+003.12E+023.12E+023.12E+023.12E+023.12E+023.12E+02CR-510.00E+000.00E+004.29E+022.38E+026.51E+014.35E+022.28E+04MN-540.00E+002.37E+066.31E+050.00E+006.64E+050.00E+001.99E+06FE-593.68E+075.96E+072.97E+070.00E+000.00E+001.73E+076.20E+07CO-580.00E+002.55E+067.82E+060.00E+000.00E+000.00E+001.49E+07 CO-600.00E+002.40E+077.09E+070.00E+000.00E+000.00E+001.33E+08ZN-651.05E+082.80E+081.74E+080.00E+001.77E+080.00E+004.92E+07SR-895.45E+070.00E+001.56E+060.00E+000.00E+000.00E+002.11E+06 SR-903.70E+090.00E+009.39E+080.00E+000.00E+000.00E+004.99E+07ZR-953.81E+058.36E+047.45E+040.00E+001.20E+050.00E+008.73E+07SB-1243.95E+065.12E+041.38E+068.72E+030.00E+002.19E+062.47E+07I-1312.09E+052.11E+051.20E+056.96E+073.46E+050.00E+001.87E+04I-1337.09E-038.77E-033.32E-031.63E+001.46E-020.00E+003.53E-03CS-1343.05E+085.00E+081.06E+080.00E+001.55E+085.56E+072.70E+06 CS-1374.75E+084.55E+086.71E+070.00E+001.48E+085.33E+072.85E+06BA-1406.63E+055.81E+023.87E+040.00E+001.89E+023.46E+023.36E+05CE-1411.40E+036.99E+021.04E+020.00E+003.07E+020.00E+008.72E+05 CE-1446.72E+052.11E+053.58E+040.00E+001.17E+050.00E+005.49E+07 46ODCM Rev. 27TABLE 4-8Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - ADULTRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+001.02E+031.02E+031.02E+031.02E+031.02E+031.02E+03CR-510.00E+000.00E+008.28E+034.95E+031.82E+031.10E+042.08E+06MN-540.00E+003.99E+067.61E+050.00E+001.19E+060.00E+001.22E+07FE-599.69E+062.28E+078.73E+060.00E+000.00E+006.36E+067.59E+07CO-580.00E+001.74E+063.90E+060.00E+000.00E+000.00E+003.53E+07 CO-600.00E+008.41E+061.85E+070.00E+000.00E+000.00E+001.58E+08ZN-656.34E+082.02E+099.12E+080.00E+001.35E+090.00E+001.27E+09SR-894.90E+080.00E+001.41E+070.00E+000.00E+000.00E+007.86E+07 SR-902.43E+100.00E+005.96E+090.00E+000.00E+000.00E+007.02E+08ZR-953.39E+021.09E+027.37E+010.00E+001.71E+020.00E+003.45E+05SB-1249.11E+061.72E+053.61E+062.21E+040.00E+007.09E+062.59E+08I-1317.77E+071.11E+086.37E+073.64E+101.91E+080.00E+002.93E+07I-1331.02E+061.77E+065.39E+052.60E+083.08E+060.00E+001.59E+06CS-1342.83E+096.73E+095.50E+090.00E+002.18E+097.23E+081.18E+08 CS-1373.83E+095.24E+093.43E+090.00E+001.78E+095.91E+081.01E+08BA-1407.11E+068.93E+034.66E+050.00E+003.04E+035.11E+031.46E+07CE-1418.73E+035.90E+036.70E+020.00E+002.74E+030.00E+002.26E+07 CE-1441.01E+064.21E+055.41E+040.00E+002.50E+050.00E+003.41E+08 47ODCM Rev. 27TABLE 4-9Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEENRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+001.33E+031.33E+031.33E+031.33E+031.33E+031.33E+03CR-510.00E+000.00E+001.45E+048.03E+033.17E+032.06E+042.43E+06MN-540.00E+006.64E+061.32E+060.00E+001.98E+060.00E+001.36E+07FE-591.69E+073.95E+071.52E+070.00E+000.00E+001.24E+079.33E+07CO-580.00E+002.93E+066.76E+060.00E+000.00E+000.00E+004.04E+07 CO-600.00E+001.42E+073.21E+070.00E+000.00E+000.00E+001.86E+08ZN-659.74E+083.38E+091.58E+090.00E+002.17E+090.00E+001.43E+09SR-899.03E+080.00E+002.59E+070.00E+000.00E+000.00E+001.08E+08 SR-903.43E+100.00E+008.48E+090.00E+000.00E+000.00E+009.64E+08ZR-955.94E+021.87E+021.29E+020.00E+002.75E+020.00E+004.32E+05SB-1241.62E+072.99E+056.34E+063.69E+040.00E+001.42E+073.27E+08I-1311.41E+081.98E+081.06E+085.76E+103.40E+080.00E+003.91E+07I-1331.86E+063.15E+069.60E+054.39E+085.52E+060.00E+002.38E+06CS-1344.91E+091.16E+105.36E+090.00E+003.67E+091.40E+091.44E+08 CS-1376.95E+099.24E+093.22E+090.00E+003.15E+091.22E+091.32E+08BA-1401.28E+071.57E+048.27E+050.00E+005.33E+031.06E+041.98E+07CE-1411.60E+041.07E+041.23E+030.00E+005.03E+030.00E+003.06E+07 CE-1441.86E+067.68E+059.97E+040.00E+004.59E+050.00E+004.67E+08 48ODCM Rev. 27TABLE 4-10Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - CHILDRECEPTORNUCLIDESBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+002.09E+032.09E+032.09E+032.09E+032.09E+032.09E+03CR-510.00E+000.00E+002.95E+041.64E+044.47E+032.99E+041.56E+06MN-540.00E+009.94E+062.65E+060.00E+002.79E+060.00E+008.34E+06FE-593.92E+076.35E+073.16E+070.00E+000.00E+001.84E+076.61E+07CO-580.00E+004.48E+061.37E+070.00E+000.00E+000.00E+002.61E+07 CO-600.00E+002.21E+076.52E+070.00E+000.00E+000.00E+001.23E+08ZN-651.91E+095.09E+093.17E+090.00E+003.21E+090.00E+008.95E+08SR-892.23E+090.00E+006.38E+070.00E+000.00E+000.00E+008.65E+07 SR-905.80E+100.00E+001.47E+100.00E+000.00E+000.00E+007.81E+08ZR-951.38E+033.03E+022.70E+020.00E+004.34E+020.00E+003.16E+05SB-1243.84E+074.99E+051.35E+078.49E+040.00E+002.13E+072.41E+08I-1313.42E+083.44E+081.96E+081.14E+115.65E+080.00E+003.06E+07I-1334.51E+065.57E+062.11E+061.04E+099.29E+060.00E+002.25E+06CS-1341.13E+101.86E+103.92E+090.00E+005.76E+092.07E+091.00E+08 CS-1371.67E+101.60E+102.36E+090.00E+005.22E+091.88E+091.00E+08BA-1403.10E+072.71E+041.81E+060.00E+008.83E+031.62E+041.57E+07CE-1413.94E+041.97E+042.92E+030.00E+008.62E+030.00E+002.45E+07 CE-1444.57E+061.43E+062.44E+050.00E+007.94E+050.00E+003.74E+08 49ODCM Rev. 27TABLE 4-11Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+003.18E+033.18E+033.18E+033.18E+033.18E+033.18E+03CR-510.00E+000.00E+004.67E+043.05E+046.66E+035.93E+041.36E+06MN-540.00E+001.85E+074.19E+060.00E+004.10E+060.00E+006.79E+06FE-597.32E+071.28E+085.04E+070.00E+000.00E+003.78E+076.11E+07CO-580.00E+008.96E+062.23E+070.00E+000.00E+000.00E+002.23E+07 CO-600.00E+004.52E+071.07E+080.00E+000.00E+000.00E+001.07E+08ZN-652.57E+098.81E+094.06E+090.00E+004.27E+090.00E+007.44E+09SR-894.25E+090.00E+001.22E+080.00E+000.00E+000.00E+008.74E+07 SR-906.31E+100.00E+001.61E+100.00E+000.00E+000.00E+007.88E+08ZR-952.45E+035.97E+024.23E+020.00E+006.43E+020.00E+002.97E+05SB-1247.41E+071.09E+062.30E+071.97E+050.00E+004.64E+072.29E+08I-1317.14E+088.42E+083.70E+082.77E+119.83E+080.00E+003.00E+07I-1339.52E+061.39E+074.06E+062.52E+091.63E+070.00E+002.35E+06CS-1341.82E+103.40E+103.44E+090.00E+008.76E+093.59E+099.24E+07 CS-1372.67E+103.13E+102.22E+090.00E+008.39E+093.40E+099.78E+07BA-1406.37E+076.37E+043.28E+060.00E+001.51E+043.91E+041.57E+07CE-1417.81E+044.77E+045.61E+030.00E+001.47E+040.00E+002.46E+07 CE-1446.55E+062.68E+063.67E+050.00E+001.08E+060.00E+003.76E+08 50ODCM Rev. 27TABLE 4-12Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - ADULTRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+001.26E+031.26E+031.26E+031.26E+031.26E+031.26E+03CR-510.00E+000.00E+001.00E+025.95E+012.28E+011.44E+043.32E+03MN-540.00E+003.96E+046.30E+030.00E+009.84E+031.40E+067.74E+04FE-591.18E+042.78E+041.06E+040.00E+000.00E+001.02E+061.88E+05CO-580.00E+001.58E+032.07E+030.00E+000.00E+009.28E+051.06E+05 CO-600.00E+001.15E+041.48E+040.00E+000.00E+005.97E+062.85E+05ZN-653.24E+041.03E+054.66E+040.00E+006.90E+048.64E+055.34E+04SR-893.04E+050.00E+008.72E+030.00E+000.00E+001.40E+063.50E+05 SR-909.92E+070.00E+006.10E+060.00E+000.00E+009.60E+067.22E+05ZR-951.07E+053.44E+042.33E+040.00E+005.42E+041.77E+061.50E+05SB-1243.12E+045.89E+021.24E+047.55E+010.00E+002.48E+064.06E+05I-1312.52E+043.58E+042.05E+041.19E+076.13E+040.00E+006.28E+03I-1338.64E+031.48E+044.52E+032.15E+062.58E+040.00E+008.88E+03CS-1343.73E+058.48E+057.28E+050.00E+002.87E+059.76E+041.04E+04 CS-1374.78E+056.21E+054.28E+050.00E+002.22E+057.52E+048.40E+03BA-1403.90E+044.90E+012.57E+030.00E+001.67E+011.27E+062.18E+05CE-1411.99E+041.35E+041.53E+030.00E+006.26E+033.62E+051.20E+05 CE-1443.43E+061.43E+061.84E+050.00E+008.48E+057.78E+068.16E+05 51ODCM Rev. 27TABLE 4-13Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - TEENRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+001.27E+031.27E+031.27E+031.27E+031.27E+031.27E+03CR-510.00E+000.00E+001.35E+027.50E+013.07E+012.10E+043.00E+03MN-540.00E+005.11E+048.40E+030.00E+001.27E+041.98E+066.68E+04FE-591.59E+043.70E+041.43E+040.00E+000.00E+001.53E+061.78E+05CO-580.00E+002.07E+032.78E+030.00E+000.00E+001.34E+069.52E+04 CO-600.00E+001.51E+041.98E+040.00E+000.00E+008.72E+062.59E+05ZN-653.86E+041.34E+056.24E+040.00E+008.64E+041.24E+064.66E+04SR-894.34E+050.00E+001.25E+040.00E+000.00E+002.42E+063.71E+05 SR-901.08E+080.00E+006.68E+060.00E+000.00E+001.65E+077.65E+05ZR-951.46E+054.58E+043.15E+040.00E+006.74E+042.69E+061.49E+05SB-1244.30E+047.94E+021.68E+049.76E+010.00E+003.85E+063.98E+05I-1313.54E+044.91E+042.64E+041.46E+078.40E+040.00E+006.49E+03I-1331.22E+042.05E+046.22E+032.92E+063.59E+040.00E+001.03E+04CS-1345.02E+051.13E+065.49E+050.00E+003.75E+051.46E+059.76E+03 CS-1376.70E+058.48E+053.11E+050.00E+003.04E+051.21E+058.48E+03BA-1405.47E+046.70E+013.52E+030.00E+002.28E+012.03E+062.29E+05CE-1412.84E+041.90E+042.17E+030.00E+008.88E+036.14E+051.26E+05 CE-1444.89E+062.02E+062.62E+050.00E+001.21E+061.34E+078.64E+05 52ODCM Rev. 27TABLE 4-14Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILDRECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+001.12E+031.12E+031.12E+031.12E+031.12E+031.12E+03CR-510.00E+000.00E+001.54E+028.55E+012.43E+011.70E+041.08E+03MN-540.00E+004.29E+049.51E+030.00E+001.00E+041.58E+062.29E+04FE-592.07E+043.34E+041.67E+040.00E+000.00E+001.27E+067.07E+04CO-580.00E+001.77E+033.16E+030.00E+000.00E+001.11E+063.44E+04 CO-600.00E+001.31E+042.26E+040.00E+000.00E+007.07E+069.62E+04ZN-654.26E+041.13E+057.03E+040.00E+007.14E+049.95E+051.63E+04SR-895.99E+050.00E+001.72E+040.00E+000.00E+002.16E+061.67E+05 SR-901.01E+080.00E+006.44E+060.00E+000.00E+001.48E+073.43E+05ZR-951.90E+054.18E+043.70E+040.00E+005.96E+042.23E+066.11E+04SB-1245.74E+047.40E+022.00E+041.26E+020.00E+003.24E+061.64E+05I-1314.81E+044.81E+042.73E+041.62E+077.88E+040.00E+002.84E+03I-1331.66E+042.03E+047.70E+033.85E+063.38E+040.00E+005.48E+03CS-1346.51E+051.01E+062.25E+050.00E+003.30E+051.21E+053.85E+03 CS-1379.07E+058.25E+051.28E+050.00E+002.82E+051.04E+053.62E+03BA-1407.40E+046.48E+014.33E+030.00E+002.11E+011.74E+061.02E+05CE-1413.92E+041.95E+042.90E+030.00E+008.55E+035.44E+055.66E+04 CE-1446.77E+062.12E+063.61E+050.00E+001.17E+061.20E+073.89E+05 53ODCM Rev. 27TABLE 4-15Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTORNUCLIDEBONELIVERT.BODYTHYROIDKIDNEYLUNGGI-LLIH-30.00E+006.47E+026.47E+026.47E+026.47E+026.47E+026.47E+02CR-510.00E+000.00E+008.95E+015.75E+011.32E+011.28E+043.57E+02MN-540.00E+002.53E+044.98E+030.00E+004.98E+031.00E+067.06E+03FE-591.36E+042.35E+049.48E+030.00E+000.00E+001.02E+062.48E+04CO-580.00E+001.22E+031.82E+030.00E+000.00E+007.77E+051.11E+04 CO-600.00E+008.02E+031.18E+040.00E+000.00E+004.51E+063.19E+04ZN-651.93E+046.26E+043.11E+040.00E+003.25E+046.47E+055.14E+04SR-893.98E+050.00E+001.14E+040.00E+000.00E+002.03E+066.40E+04 SR-904.09E+070.00E+002.59E+060.00E+000.00E+001.12E+071.31E+05ZR-951.15E+052.79E+042.03E+040.00E+003.11E+041.75E+062.17E+04SB-1243.79E+045.56E+021.20E+041.01E+020.00E+002.65E+065.91E+04I-1313.79E+044.44E+041.96E+041.48E+075.18E+040.00E+001.06E+03I-1331.32E+041.92E+045.60E+033.56E+062.24E+040.00E+002.16E+03CS-1343.96E+057.03E+057.45E+040.00E+001.90E+057.97E+041.33E+03 CS-1375.49E+056.12E+054.55E+040.00E+001.72E+057.13E+041.33E+03BA-1405.60E+045.60E+012.90E+030.00E+001.34E+011.60E+063.84E+04CE-1412.77E+041.67E+041.99E+030.00E+005.25E+035.17E+052.16E+04 CE-1443.19E+061.21E+061.76E+050.00E+005.38E+059.84E+061.48E+05 54ODCM Rev. 27TABLE 4-16PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT l(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.
93                                      ODCM Rev. 27


==References:==
APPENDIX C DEFINITIONS (Continued)
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-A NPP-1385 and NUS-ANPP-1386.DIRECTIONX/Q(Sec/m 3)RESIDENCE(b)
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.
Dist. MilesD/Q (m-2)X/Q(Sec/m 3)GARDEN(b)Dist. Miles D/Q (m-2)X/Q(Sec/m 3)MILK(b)Dist. MilesD/Q (m-2)N2.92E-061.43.25E-092.92E-061.43.25E-097.03E-07(a)3.48E-10 NNE1.81E-061.82.88E-094.70E-07(a)4.04E-104.70E-07(a)4.04E-10 NE1.95E-061.93.85E-091.76E-062.13.29E-095.77E-07(a)6.51E-10 ENE1.03E-062.71.08E-091.03E-062.71.08E-093.86E-07(a)2.86E-10 E9.39E-072.86.68E-103.71E-07(a)1.87E-103.71E-07(a)1.87E-10 ESE6.37E-073.72.84E-104.12E-074.61.60E-104.12E-074.61.60E-10 goat SE8.83E-074.12.61E-108.83E-074.12.61E-105.84E-07(a)1.52E-10 SSE1.27E-064.72.61E-101.09E-06(a)2.15E-101.09E-06(a)2.15E-10 S2.58E-064.64.85E-102.09E-065.23.59E-102.13E-065.13.71E-10 cow SSW3.26E-063.58.26E-102.28E-06(a)4.53E-102.28E-06(a)4.53E-10 SW2.80E-062.99.10E-101.58E-06(a)3.56E-101.58E-06(a)3.56E-10 WSW1.95E-062.61.09E-098.55E-07(a)3.18E-108.55E-07(a)3.18E-10 W7.54E-07(a)4.44E-107.54E-07(a)4.44E-107.54E-07(a)4.44E-10 WNW6.03E-07(a)3.25E-106.03E-07(a)3.25E-106.03E-07(a)3.25E-10 NW8.24E-073.85.25E-107.55E-074.14.61E-106.02E-07(a)3.27E-10 NNW1.46E-062.01.47E-095.20E-07(a)3.04E-105.20E-07(a)3.04E-10 55ODCM Rev. 27TABLE 4-17PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2(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.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED 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.
94                                      ODCM Rev. 27


==References:==
TABLE C-1 FREQUENCY NOTATION NOTATION                                FREQUENCY*
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-A NPP-1385 and NUS-ANPP-1386.DIRECTIONX/Q(Sec/m 3)RESIDENCE(b)
MAR 2016 S            At least once per 12 hours.
Dist. MilesD/Q (m-2)X/Q(Sec/m 3)GARDEN(b)Dist. Miles D/Q (m-2)X/Q(Sec/m 3)MILK(b)Dist. MilesD/Q (m-2) N2.73E-061.52.92E-092.39E-061.72.35E-097.03E-07(a)3.48E-10 NNE2.20E-061.53.87E-092.20E-061.53.87E-094.70E-07(a)4.04E-10 NE1.85E-062.03.55E-091.57E-062.32.78E-095.77E-07(a)6.51E-10 ENE1.03E-062.71.08E-091.03E-062.71.08E-093.86E-07(a)2.86E-10 E8.80E-073.06.06E-103.71E-07(a)1.87E-103.71E-07(a)1.87E-10 ESE6.25E-073.72.76E-103.96E-074.71.51E-103.96E-074.71.51E-10 goat SE9.06E-074.02.72E-109.06E-074.02.72E-105.84E-07(a)1.52E-10 SSE1.34E-064.52.81E-101.09E-06(a)2.15E-101.09E-06(a)2.15E-10 S2.63E-064.55.01E-102.19E-065.03.88E-102.19E-065.03.88E-10 cow SSW3.48E-063.29.19E-102.28E-06(a)4.53E-102.28E-06(a)4.53E-10 SW2.93E-062.79.75E-101.58E-06(a)3.56E-101.58E-06(a)3.56E-10 WSW2.01E-062.51.16E-098.55E-07(a)3.18E-108.55E-07(a)3.18E-10 W7.54E-07(a)4.44E-107.54E-07(a)4.44E-107.54E-07(a)4.44E-10 WNW6.03E-07(a)3.25E-106.03E-07(a)3.25E-106.03E-07(a)3.25E-10 NW7.84E-074.04.88E-107.84E-074.04.88E-106.02E-07(a)3.27E-10 NNW1.46E-062.01.47E-095.20E-075.03.04E-105.20E-07(a)3.04E-10 56ODCM Rev. 27TABLE 4-18PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3(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.
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.
        *The specified Frequency for each Surveillance Requirement and Sampling Requirement is met if the Surveillance Requirement or Sampling Requirement is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
MAR 2016 95                                    ODCM Rev. 27


==References:==
APPENDIX D REFERENCES 1  Title 10, Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation.
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-A NPP-1385 and NUS-ANPP-1386.DIRECTIONX/Q(Sec/m 3)RESIDENCE(b)
2 Title 10, Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities."
Dist. MilesD/Q (m-2)X/Q(Sec/m 3)GARDEN(b)Dist. Miles D/Q (m-2)X/Q(Sec/m 3)MILK(b)Dist. MilesD/Q (m-2)N2.58E-061.82.47E-092.42E-061.92.22E-097.03E-07(a)3.48E-10NNE1.85E-061.72.97E-091.85E-061.72.97E-094.70E-07(a)4.04E-10NE1.66E-062.23.00E-091.48E-062.42.54E-095.77E-07(a)6.51E-10ENE8.75E-072.98.86E-108.75E-072.98.86E-103.86E-07(a)2.86E-10E8.90E-073.06.17E-104.06E-074.62.15E-104.25E-074.52.31E-10 goatESE6.37E-073.72.84E-105.80E-074.02.46E-103.73E-07(a)1.37E-10SE5.84E-07(a)1.52E-105.84E-07(a)1.52E-105.84E-07(a)1.52E-10SSE1.36E-064.42.88E-101.09E-06(a)2.15E-101.09E-06(a)2.15E-10S2.65E-064.25.25E-102.25E-064.94.06E-102.31E-064.84.21E-10 cowSSW3.64E-063.19.82E-102.28E-06(a)4.53E-102.28E-06(a)4.53E-10SW3.19E-062.51.11E-091.58E-06(a)3.56E-101.58E-06(a)3.56E-10WSW2.12E-062.41.26E-098.55E-07(a)3.18E-108.55E-07(a)3.18E-10W7.54E-07(a)4.44E-107.54E-07(a)4.44E-107.54E-10(a)4.44E-10WNW6.03E-07(a)3.25E-106.03E-07(a)3.25E-106.03E-07(a)3.25E-10NW6.83E-074.34.05E-106.82E-074.34.05E-106.02E-07(a)3.27E-10NNW1.34E-062.21.26E-095.16E-075.03.01E-105.20E-07(a)3.04E-10 57ODCM Rev. 274.4Requirements: Liquid EffluentsThe dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquideffluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See Figure6-4 and Figure 6-5) shall be limited:
3 Title 40, Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations.
a.During any calendar quarter to less than or equal to 1.5mrems to the total body and to less thanor equal to 5 mrems to any organ, and b.During any calendar year to less than or equal to 3mrems to the total body and to less than orequal to 10 mrems to any organ.Applicability:
4  Federal Register, Vol. 58, No. 245, Thursday, December 23, 1993, Notices, pages 68170-68179.
At all times.Action:With the calculated dose from the release of radioactive materials in liquid effluents exceeding any ofthe above limits, prepare and submit to the Commission within 30days, a Special Report thatidentifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have beentaken to reduce the releases and the proposed corrective actions to be taken to assure that subsequentreleases will be in compliance with the above limits.4.4.1Surveillance RequirementsCumulative dose contributions from liquid effluents for the current calendar quarter and thecurrent calendar year shall be determined in accordance with the methodology and parametersin the ODCM at least once per 31days.4.4.2Implementation of the RequirementsThis Requirement does not require implementation guidance. There are no offsite liquideffluent releases.
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.
58ODCM Rev. 275.0TOTAL DOSE AND DOSE TO PUBLIC ONSITE5.1Requirement: Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due toreleases of radioactivity and to direct radiation from uranium fuel cycle sources shall be limited toless than or equal to 25mrems to the total body or any organ, except the thyroid, which shall belimited to less than or equal to 75mrems.Applicability:
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.
At all times.Action:With the calculated doses from the release of radioactive materials in liquid and gaseous effluentsexceeding twice the limits of Section4.4a, 4.4b, 4.1a, 4.1b, 4.2a or 4.2b calculations shall be madeincluding direct radiation contributions from the reactor units (including outside storage tanks, etc.) todetermine whether the above limits of Section5.1 have been exceeded. If such is the case, prepareand submit to the Commission within 30days, a Special Report that defines the corrective action tobe taken to reduce subsequent releases to prevent recurrence of exceeding the above limits andincludes the schedule for achieving conformance with the above limits. This Special Report, asdefined in 10CFR20.2203(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 effluentpathways 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 thecause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, andif the release condition resulting in violation of 40CFR Part190 has not already been corrected, theSpecial Report shall include a request for a variance in accordance with the provisions of 40CFR Part190. Submittal of the report within 30days is considered a timely request, and a variance isgranted until staff action on the request is complete.5.1.1Surveillance Requirementsa.Cumulative dose contributions from the gaseous effluents shall be determined inaccordance with the surveillance requirements of Section4.4.1, 4.1.1 and 4.2.1 and in accordance with the methodology and parameters contained in Section5.1.2.b.Cumulative dose contributions from direct radiation from the reactor units and fromradwaste storage tanks shall be determined in accordance with the methodology andparameters in Section5.1.2. This requirement is applicable only under conditions set forth in Section5.1, Action.5.1.2Implementation of the Requirement Since all other uranium fuel cycle sources are greater than 20miles away, only the PVNGS siteneed be considered.The total dose to any MEMBER OF THE PUBLIC will be determined based on a sum of thedoses from all three units releases and doses from direct radiation from PVNGS.
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.
59ODCM Rev. 27This dose evaluation is performed annually and submitted with the Annual RadioactiveEffluent Release Report to assure compliance with 40 CFR Part 190, Environmental RadiationProtection Standards for Nuclear Power Operation. NUREG-0543, Methods forDemonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40CFRPart190), February1980, provides a discussion on compliance with 40CFR Part190 inrelation to the Radiological Environmental Technical Specifications for sites of up to fournuclear power reactors. The NUREG concludes that as long as a nuclear plant site operates at alevel below the 10CFR Part50, AppendixI reporting requirements, and there is no significantsource of direct radiation from the site, no extra analysis is required to demonstrate compliancewith 40CFR Part190. As a result, this dose evaluation will also be performed whenevercalculated doses associated with effluent releases exceed twice the limits of Section4.4a, 4.4b, 4.1a, 4.1b, 4.2a or 4.2b.Dose Contribution from Liquid and Gaseous EffluentsThe annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noblegases released in gaseous effluents is determined by using the following equation:
8  Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Revision 1, April 1975.
D WB=(3.17E-08) i [(K i) (X/Q)UNIT (Q i)](5-1)Where: K i=the whole body dose factor due to gamma emissions for each identified noblegas radionuclide i, in mrem/yr per
9  NUREG-0133, Preparation of Radiological Effluent Technical Specifications For Nuclear Power Plants, Oct. 1978.
&#xb5;Ci/m 3 from Table3-3.
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.
Q i=the integrated release of radionuclide i, in
11 NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactor, Arpil 1991.
&#xb5;Ci for the previous calendar year.(X/Q)UNIT=the highest calculated annual average dispersion parameter, in sec/m 3, for aparticular unit, at the controlling location, from Table4-16, 4-17, or 4-18, orconcurrent meteorological data if available.=2.92E-06 from Unit 1=2.19E-06 from Unit 2=2.31E-06 from Unit 3 D WB=the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at thecontrolling location due to noble gases released in gaseous effluents.3.17E-08=the inverse of seconds in a year (yr/sec).
12 Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station, December 1981.
60ODCM Rev. 27The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-131,iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 daysreleased in gaseous effluents is determined by using the following equation:
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.
D o=(3.17E-08) i [k (R ik W k) (Q i)](5-2)Where: D o=the total annual organ dose from gaseous effluents to a MEMBER OF THEPUBLIC, in mrem, at the controlling location.
15 Calculation 13-NC-ZY-253, Annual Average Dose from Normal Operation Airborne Direct and Sky Shine from the Evaporation Pond, Rev 0.
Q i=the integrated release of radionuclide i, in
16 Calculation 13-NC-ZY-254, Radiation Dose Due to an Evaporation Pond Dike Failure During a Seismic Event, Rev. 0.
&#xb5;Ci, for the previous calendar year.
96                                      ODCM Rev. 27
R ik=the dose factor for each identified radionuclide i, for pathway k (for theinhalation pathway in mrem/yr per
&#xb5;Ci/m 3 and for the food and ground planepathways in m 2-mrem/yr per
&#xb5;Ci/sec) at the controlling location. The R iksfor each age group are given in Tables4-1 through 4-15.
W K=the highest annual average dispersion or deposition parameter for theparticular unit, used for estimating the total annual organ dose to a MEMBEROF THE PUBLIC at the controlling location for the particular unit.=(X/Q)UNIT, in sec/m 3 for the inhalation pathway and for all tritiumcalculations, for organ dose at the controlling location, from Table4-16,4-17, 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=(D/Q)UNIT, in m-2, for the food and ground plane pathways, for organ dose atthe controlling location, from Table4-16, 4-17, or 4-18, or concurrentmeteorological data if available.=3.25E-09 from Unit 1=3.88E-10 from Unit 2
=4.21E-10 from Unit 33.17E-08=the inverse of seconds in a year (yr/sec).
61ODCM Rev. 27Dose Due to Direct RadiationThe component of dose to a MEMBER OF THE PUBLIC due to direct radiation will beevaluated by first determining the direct radiation dose at the site boundary in each sector, andthen extrapolating the site boundary dose to the controlling location by the inverse square lawof distance.Dose from Radioactive Liquid and Gaseous Effluents to MEMBERS OF THE PUBLIC due totheir activities within the SITE BOUNDARY.These activities have been determined to be limited to the vicinity of the Energy InformationCenter (EIC) located inside the SITE BOUNDARY. An assumption was made that noMEMBER 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 Section5.1.2 should be used for this assessment.
62ODCM Rev. 276.0RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)6.1Requirement: REMPThe radiological environmental monitoring program shall be conducted as specified in Table6-1,based on locations determined using data from the pre-operational monitoring period; and/or theoperational 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 inTable6-1, prepare and submit to the Commission, in the Annual Radiological EnvironmentalOperating Report, as required by Section7.2, 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 samplingmedium at a specified location exceeding the reporting levels of Table6-2 when averaged overany calendar quarter, prepare and submit to the Commission within 30 days, a Special Report thatidentifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken toreduce radioactive effluents so that the potential annual dose* to A MEMBER OF THE PUBLICis less than the calendar year limits of Section4.4, 4.1 and 4.2. When more than one of the radionuclides in Table6-2 are detected in the sampling medium, this report shall be submitted if:When radionuclides other than those in Table6-2 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 Section4.4, 4.1 and4.2. This report is notrequired if the measured level of radioactivity was not the result of plant effluents; however, insuch 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 locationsrequired by Table6-1, identify locations for obtaining replacement samples and add them to theRadiological Environmental Monitoring Program within 30days. The specific locations fromwhich 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 OFTHE PUBLIC shall be indicated in this report.concentration(1)reportinglevel(1)------------------------------------------------
-concentration(2)reportinglevel(2)----------------------------------------------...1.0++
63ODCM Rev. 276.1.1Surveillance Requirementsa.The radiological environmental monitoring samples shall be collected pursuant toTable6-1 from the specific locations given in Table6-4 and Figure and Figure 6-2 and shallbe analyzed pursuant to the requirements of Table6-1, and the detection capabilitiesrequired by Table6-3.6.1.2Implementation of the RequirementsThe results of the radiological environmental monitoring program are intended to supplementthe results of the radiological effluent monitoring program by verifying that the measurableconcentrations of radioactive materials and levels of radiation are not higher than expectedbased 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 tothe highest potential radiation exposures to individuals resulting from station operation.This requirement is implemented by Nuclear Administrative and Technical Manualprocedures.
64ODCM Rev. 27 TABLE 6-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMExposure Pathway and/or SampleNumber of Representative Samples and Sample Locations aSampling and Collection Frequency aType and Frequency of Analysis dAirborneRadioiodine and particulatesSamples from 5locations: 4 samples at or near the SITE BOUNDARIES (#14A, 15, 29, 40) including 3 different sectors of the highest calculated annual average ground level D/Q.*1 sample (#40) from areas of special interest, which is from the vicinity of a community having the highest calculated annual average D/Q.1 sample (#6A) from a control location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.
eContinuous sampling collected weekly, or more frequently if required by dust loading.Gross beta weekly c , I-131 weekly; gamma isotopic analysis of composite (by location) quarterly.Direct radiation bForty (40) routine monitoring stations (#5-40, #42, #44, #46, #50) 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 (4-5mi) 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.QuarterlyGamma dose quarterly.* D/Q refers to average annual relative ground deposition rate.
65ODCM Rev. 27WaterborneSurface85 acre Water storagereservoir (#60)45 acre Water storage reservoir (#61)
Evaporation pond #1 (#59)Evaporation pond #2 (#63)Evaporation pond #3 (#64)Quarterly h grab sampleTritium and gamma isotopic analysis quarterly.Ground2 onsite wells f (#57, #58)Quarterly grab sampleTritium and gamma isotopic analysis quarterly.Drinking (well)3 wells from surrounding residences (#46, #48, #49) that would be affected by its discharge.Composite sample of weekly grab samples over 2-week period when I-131 analysis is performed, monthly composite of weekly grab samples otherwiseI-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1mrem per year.g Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.Ingestion MilkSamples from milking animals in 3locations within 5km (3 mi) distant having the highest dose potential. If there are none, 1sample from milking animals in each of three areas between 5 and 8 km (3-5 mi) distant (#51, #54) where doses are calculated to be greater than 1 mrem per year.gOne sample from milking animals at a control location 15 to 30 km (9-18 mi) distant (#53) and in the least prevalent wind direction.
eSemimonthly for animals on pasture; otherwise, monthly.Gamma isotopic and I-131 analysis semimonthly when animals are on pasture or monthly at other times.TABLE 6-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMExposure Pathway and/or SampleNumber of Representative Samples and Sample Locations aSampling and Collection Frequency aType and Frequency of Analysis dMAR 2016 66ODCM Rev. 27Food Products *2 samples (#47, #51) of 3 types of broad leaf vegetation (as available) from locations identified per the criteria of Section 6.2b. of this manual.Monthly during growing season.Gamma isotopic analysis.1 control sample (#62) of 3 types of broad leaf vegetation (as available) grown 15 to 30km (9-18 mi) distant in the least prevalent wind direction.
eMonthly during growing season.Gamma isotopic analysis.*When broad leaf vegetation samples are not available, reports from 4 existing supplemental airborne radioiodine sample loca tions will be substituted.TABLE 6-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMExposure Pathway and/or SampleNumber of Representative Samples and Sample Locations aSampling and Collection Frequency aType and Frequency of Analysis dMAR 2016 67ODCM Rev. 27TABLE 6-1 (Continued)TABLE NOTATIONaThe 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 desiredlocation or time. In these instances suitable alternative media and locations may be chosen for theparticular pathway in question. Actual locations (distance and direction) from the site shall be providedin Table6-4 and Figure 6-1or Figure 6-2 in the ODCM. Refer to Regulatory Guide4.1, Programs forMonitoring Radioactivity in the Environs of Nuclear Power Plants.bRegulatory Guide4.13 provides guidance for thermoluminescence dosimetry (TLD) systems used forenvironmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuringand 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, andtwo or more phosphors in a packet may be considered as two or more dosimeters. Film badges should notbe used for measuring direct radiation.cParticulate sample filters shall be analyzed for gross beta 24hours or more after sampling to allow forradon and thoron daughter decay. If gross beta activity in air or water is greater than 10times the yearlymean of control samples for any medium, gamma isotopic analysis should be performed on theindividual samples.dGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclidesthat may be attributable to the effluents from the facility.eThe purpose of this sample is to obtain background information. If it is not practical to establish controllocations in accordance with the wind direction and distance criteria, other sites that provide validbackground data may be substituted.fGroundwater samples should be taken when this source is tapped for drinking or irrigation purposes inareas where the hydraulic gradient or recharge properties are suitable for contamination.gThe dose shall be calculated for the maximum organ and age group, using the methodology andparameters in the ODCM.hQuarterly grab samples are not required from the onsite evaporation pond if the evaporation pond has notreceived any influent since the last sample was taken.MAR 2016 68ODCM Rev. 27*For drinking water samples. This is a 40CFR141 value. If no drinking water pathway exists, a value of 30,000pCi/l may be used.**If no drinking water pathway exists, a reporting level of 20pCi/l may be used.TABLE 6-2REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLESAnalysisWater (pCi/l)Airborne Particulate or Gas (pCi/m 3)Fresh Milk (pCi/l)Food Products (pCi/kg, wet)H-320,000 *Mn-541,000Fe-59400Co-581,000Co-60300Zn-65300Zr-Nb-95400I-1312 **0.93100Cs-1343010601,000 Cs-1375020702,000Ba-La-140200300 69ODCM Rev. 27 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 3000pCi/l may be used.
**If no drinking water pathway exists, a value of 15pCi/l may be used.TABLE 6-3DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSISLower Limit of Detection (LLD) bAnalysisWater (pCi/l) Airborne Particulate or Gas (pCi/m
: 3) Fresh Milk (pCi/l) Food Products (pCi/kg, wet)Gross Beta40.01H-32000* Mn-5415 Fe-5930 Co-58, -6015 Zn-6530 Zr-9530 Nb-9515 I-1311**0.07160Cs-134150.051560Cs-137180.061880Ba-1406060 La-1401515 a
70ODCM Rev. 27 Table 6-3 (Continued)TABLE NOTATIONaGuidance for detection capabilities for thermoluminescent dosimeters used for environmentalmeasurements is given in Regulatory Guide4.13.bTable6-3 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 isdefined, for purposes of this guide, as the smallest concentration of radioactive material in a sample thatwill yield a net count (above system background) that will be detected with 95% probability with only5% probability of falsely concluding that a blank observation represents a real signal.For a particular measurement system (which may include radiochemical separation):Where:LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume),
s b is the standard deviation of the background counting rate or of the counting rate of a blank sample asappropriate (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), is the radioactive decay constant for the particular radionuclide, andt for environmental samples is the elapsed time between sample collection (or end of the samplecollection period) and time of counting.In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background shouldinclude 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 t should be used in the calculation.It should be recognized that the LLD is defined as an a priori (before the fact) limit representing thecapability of a measurement system and not as an a posteriori (after the fact) limit for a particularmeasurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved underroutine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presenceof interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. Insuch cases, the contributing factors shall be identified and described in the Annual RadiologicalEnvironmental Operating Report.
LLD4.66s bE*V*2.22*Y*expt-()-------------------------------------------------------------------------
=
71ODCM Rev. 276.2Requirement: Land Use CensusA land use census shall be conducted and shall identify within a distance of 8km (5miles) thelocation in each of the 16meteorological sectors of the nearest milk animal, the nearest residence andthe nearest garden* of greater than 50m 2 (500ft 2) producing broad leaf vegetation.Applicability:
At all times.Action: a.With a land use census identifying a location(s) that yields a calculated dose or dose commitmentgreater than the values currently being calculated in Section4.2.1, identify the new location(s) inthe next Annual Radioactive Effluent Release Report, pursuant to Section7.1.
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 currentlybeing obtained in accordance with Section6.1, add the new location(s) to the radiologicalenvironmental monitoring program within 30days. The sampling location(s), excluding thecontrol station location, having the lowest calculated dose or dose commitment(s), via the sameexposure pathway, may then be deleted from the monitoring program. 6.2.1Surveillance Requirementsa.The land use census shall be conducted during the growing season annually using thatinformation 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 censusshall be included in the Annual Radiological Environmental Operating Report pursuant toSection7.2.6.2.2Implementation of the RequirementsThe above Requirement is implemented by Nuclear Administrative and Technical Manualprocedures.
*Broad Leaf vegetation sampling of at least three different kinds of vegetation may be performed atthe SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qsin lieu of the garden census. Specifications for broad leaf vegetation sampling in Table6-1 shallbe followed, including analysis of control samples.
72ODCM Rev. 276.3Requirement: Interlaboratory Comparison ProgramAnalyses shall be performed on radioactive materials supplied as part of an InterlaboratoryComparison 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 toprevent a recurrence to the Commission in the Annual Radiological Environmental OperatingReport pursuant to Section 7.2.6.3.1Surveillance Requirementsa.A summary of the results obtained as part of the above required InterlaboratoryComparison Program and in accordance with the methodology and parameters in this manual shall be included in the Annual Radiological Environmental Operating Reportpursuant to Section 7.2.6.3.2Implementation of the RequirementsPVNGS laboratories or contract laboratories which perform analyses for the RadiologicalEnvironmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program. The participation includes all of the determinations (sample medium-radionuclidecombinations) that are included in the monitoring program.If deviation from specified limits is identified an investigation is made to determine the reasonfor 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.
73ODCM Rev. 27TABLE 6-4RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONSSAMPLE SITESAMPLE TYPENOTE (d)LOCATION DESIGNATION (a)LOCATION DESCRIPTION (c)1TLDSUPE30Goodyear2TLDSUPENE24Scott-Libby School 3TLDSUPE21Liberty School4TLDSUPE16Buckeye4AirSUPE16Same as TLD 5TLD (b)SPESE11Palo Verde School6TLD (b)ControlSSE31APS Gila Bend substation6AAir (b)ControlSSE13Old US 807TLD (b)SPSE7Old US 80 and Arlington School Rd.7AAirSUPESE3Arlington School8TLD (b)ORSSE4Southern Pacific Pipeline Rd.
9TLD (b)OR S5Southern Pacific Pipeline Rd.10TLD (b)ORSE5355th Ave. and Elliot Rd.11TLD (b)ORESE5339th Ave. and Dobbins Rd.
12TLD (b)ORE5339th Ave. and Buckeye-Salome Rd.13TLD (b)IRN1N site boundary14TLD (b)IRNNE2NNE site boundary14AAir (b)NNE2371st Ave. and Buckeye-Salome Rd.15TLD (b)IRNE2NE site boundary, WRF access road15Air (b)NE2Same as TLD 16TLD (b)IRENE2ENE site boundary17TLD (b)IRE2E site boundary17AAirSUPE3351st Ave.18TLD (b) IRESE2 ESE site boundary 19TLD (b)IRSE2SE site boundary20TLD (b)IRSSE2SSE site boundary 74ODCM Rev. 2721TLD (b)IRS3S site boundary21Air SUPS3Same as TLD 22TLD (b)IRSSW3SSW site boundary23TLD (b)ORW5N of Elliot Rd24TLD (b)ORSW4N of Elliot Rd.
25TLD (b)ORWSW5N of Elliot Rd.26TLD (b)ORSSW4Duke Property27TLD (b)IRSW1SW site boundary 28TLD (b)IRWSW1WSW site boundary29TLD (b)IRW1W site boundary29Air (b)W1Same as TLD 30TLD (b)IRWNW1WNW site boundary31TLD (b)IRNW1NW site boundary32TLD (b)IRNNW1NNW site boundary 33TLD (b)ORNW4S of Buckeye Rd.34TLD (b)ORNNW5395th Ave. and Van Buren St.35TLD (b)SPNNW8Tonopah 35AirSUPNNW8Same as TLD36TLD (b)ORN5Wintersburg Rd. and Van Buren St.37TLD (b)ORNNE5363rd Ave. and Van Buren St.38TLD (b)ORNE5355th Ave. and Buckeye Rd.39TLD (b)ORENE5343rd Ave. N of Broadway Rd.40TLD (b)SPN2Wintersburg 40Air (b)N2Same as TLD 41TLD SUPESE3Arlington School42TLD (b)SPN8Ruth Fisher School43TLDSUPNE5Winters Well SchoolTABLE 6-4RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONSSAMPLE SITESAMPLE TYPENOTE (d)LOCATION DESIGNATION (a)LOCATION DESCRIPTION (c) 75ODCM Rev. 27 44TLD (b)ControlENE35El Mirage45TLDSUPTransit ControlONSITECentral lab, lead pig46TLD (b)SPENE30Litchfield Park School46Water (b)WDNNW8Local residence 47TLDSUPE35Littleton School47Vegetation (b)N3Local residence48TLDSUPE24Jackrabbit Trail 48Water (b)WDSW1Local residence49TLDSUPENE11Palo Verde Rd.49Water (b)WDN2Local residence 50TLD (b)ORWNW5S of Buckeye-Salome Rd.51Milk (b)ENE5Local residence (goats)51Vegetation (b)ENE5Local residence 53Milk (b)ControlNE30Local residence (goats)54Milk (b)NNE4Local residence (goats)55Water WDSUPSW3Local residence57Ground Water (b)WGonsiteWell 27ddc 58Ground Water (b)WGonsiteWell 34abb59Surface Water (b)WSonsiteEvaporation Pond #160Surface Water (b)WSonsite85 acre Water storage reservoir 61Surface Water (b)WSonsite45 acre Water storage reservoir62Vegetation (b)ControlENE26Commercial produce company63Surface Water (b)WSonsiteEvaporation Pond #2 64Surface Water (b)WSonsiteEvaporation Pond #3TABLE 6-4RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONSSAMPLE SITESAMPLE TYPENOTE (d)LOCATION DESIGNATION (a)LOCATION DESCRIPTION (c)
MAR 2016 76ODCM Rev. 27NOTES:(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, Table6-1.(c) Refer to Figure 6-1 and Figure 6-2 for relative locations of sample sites.(d) IR - inner ringOR - outer ring SP - school or population centerWS - waterborne surfaceWG - waterborne ground WD - waterborne drinkingSUP -designated supplemental sampling location 77ODCM Rev. 27Figure 6-1Radiological Environmental Monitoring Program Sample Sites0 - 10 miles 78ODCM Rev. 27 Figure 6-2Radiological Environmental Monitoring Program Sample Sites 10 - 35 Miles 79ODCM Rev. 27 Figure 6-3Radiological Environmental Monitoring ProgramSample Sites 35 - 75 MilesDELETED 80ODCM Rev. 27 Figure 6-4Site Exclusion Area BoundaryDELETEDRefer to UFSAR Figure 2.1-4 81ODCM Rev. 27 Figure 6-5Gaseous EffluentRelease Points 82ODCM Rev. 27 Figure 6-6Low Population ZoneDELETEDRefer to UFSAR Figure 2.1-15 83ODCM Rev. 277.0RADIOLOGICAL REPORTS7.1Requirement: Annual Radioactive Effluent Release ReportRoutine Annual Radioactive Effluent Release Reports covering the operation of the units during theprevious 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 ofradioactive liquid and gaseous effluents and solid waste released from the unit as outlined inRegulatory Guide1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled NuclearPower Plants, Revision1, June1974, with data summarized on a quarterly basis following theformat of Appendix B thereof.The Annual Radioactive Effluent Release Report shall include an annual summary of hourlymeteorological data collected over the previous year. This annual summary may be either in the formof an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, andprecipitation (if measured), or in the form of joint frequency distributions of wind speed, winddirection, and atmospheric stability**. This same report shall include an assessment of the radiationdoses due to the radioactive liquid and gaseous effluents released from the unit or station during theprevious calendar year. This same report shall also include an assessment of the radiation doses fromradioactive 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 theseassessments, i.e., specific activity, exposure time and location, shall be included in these reports. Themeteorological conditions concurrent with the time of release of radioactive materials in gaseouseffluents, as determined by sampling frequency and measurement, shall be used for determining thegaseous pathway doses. The assessment of radiation doses shall be performed in accordance with themethodology and parameters in the ODCM.The Annual Radioactive Effluent Release Report shall also include an assessment of radiation dosesto the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearbyuranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, forthe previous calendar year to show conformance with 40CFRPart190, Environmental RadiationProtection Standards for Nuclear Power Operation. Acceptable methods for calculating the dosecontributions are given Section5.0 and Regulatory Guide1.109 Rev.1, October1977.The Annual Radioactive Effluent Release Report shall also include information required by theTechnical Requirements Manual, Section 5.0.600.1. *A single submittal may be made for a multiple unit station. The submittal should combine thosesections 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 theoption of retaining this summary of required meteorological data on site in a file that shall beprovided to the NRC upon request.
* 84ODCM Rev. 27The Annual Radioactive Effluent Release Reports shall include the following information for eachclass of solid waste (as defined by 10CFR Part61) 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 unplannedreleases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquideffluents made during the reporting period.Changes to the ODCM shall be submitted in the form of a complete, legible copy as part of orconcurrent with the Annual Radioactive Effluent Release Report for the period of the report in whichany change in the ODCM was made. Changes made to the Process Control Program shall besubmitted with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the Process Control Program was made.
85ODCM Rev. 277.2Requirement: Annual Radiological Environmental Operating ReportRoutine Annual Radiological Environmental Operating Reports covering the operation of the unitsduring the previous calendar year shall be submitted by May15 of each year in accordance withTechnical 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 thereport period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observedimpacts of the plant operation on the environment. The reports shall also include the results of landuse censuses required by Section6.2.The Annual Radiological Environmental Operating Reports shall include the results of analysis of allradiological environmental samples and of all environmental radiation measurements taken duringthe period pursuant to the locations specified in Table6-4 and Figure and Figure 6-2 as well assummarized and tabulated results of these analyses and measurements in the format of the table in theRadiological Assessment Branch Technical Position, Revision1, November1979. In the event thatsome individual results are not available for inclusion with the report, the report shall be submittednoting 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 environmentalmonitoring program; at least two legible maps** covering all sampling locations keyed to a tablegiving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Section6.3; discussion of all deviations fromthe sampling schedule of Table6-1; and discussion of all analyses in which the LLD required byTable6-3 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 distantstations.*
86ODCM Rev. 27APPENDIX A DETERMINATION OF CONTROLLING LOCATIONThe 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 10CFR50 for radioiodines and particulates isknown to be a function of:(1)Isotopic release rates (2)Meteorology (3)Exposure pathway (4)Receptors ageThe incorporation of these parameters into Equation 5-2 results in the respective equations at the controllinglocation. The isotopic release rates are based upon the source terms calculated using the PVNGS EnvironmentalReport, Operating License Stage, Table3.5-12, without carbon.All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated. Theseinclude 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 vegetablegarden locations. The ground plane exposure pathway is only considered to be present where an infant is notpresent. 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 9yearmeteorological data base, for the vegetable garden, cow milk, and goat milk pathways, are selected for eachunit. The receptor organ doses have been calculated at each of these locations. Based upon these calculations, itis determined that the controlling receptor pathway is a function of unit location. For Unit1, the controllingreceptor is a garden-child pathway; for releases from Unit2 and Unit3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table4-16, 4-17, or 4-18, which, in turn, is based upon the1984 Land Use Census. Locations of the nearest residences, gardens and milk animals, as determined in the1984 Land Use Census, are given in Table4-16, 4-17, and 4-18.
87ODCM Rev. 27APPENDIX B BASES FOR REQUIREMENTSB-2.1RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONThe radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, thereleases of radioactive materials in gaseous effluents during actual or potential releases of gaseouseffluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordancewith the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior toexceeding the limits of 10CFR Part20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria60, 63, 64 of AppendixA to 10CFRPART50.There are two separate radioactive gaseous effluent monitoring systems: the low range effluentmonitors 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 theconcentration of radioactivity in the effluent becomes too high during post-accident conditions. Thehigh range monitors only operate when the concentration of radioactivity in the effluent is above thesetpoint in the low range monitors.B-3.1GASEOUS EFFLUENT - DOSE RATEThis requirement provides reasonable assurance that radioactive material discharged in gaseouseffluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTEDAREA, 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 sitewill be appropriately controlled. It provides operational flexibility for releasing gaseous effluents tosatisfy the SectionII.A and II.C design objectives of AppendixI to 10CFR part50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of thatMEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in theatmospheric 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 ratesabove background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less thanor equal to 500mrems/year to the total body or to less than or equal to 3000mrems/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate abovebackground to a child via the inhalation pathway to less than or equal to 1500mrems/year. Thisrequirement does not affect the requirement to comply with the annual limitations of10CFR20.1301(a).This requirement applies to the release of radioactive materials in gaseous effluents from all reactorunits at the site.The required detection capabilities for radioactive materials in gaseous waste samples are tabulated interms of the lower limits of detection (LLD). Detailed discussion of the LLD and other detection limitscan be found in Currie, L. A., Lower Limit of Detection: Definition and Elaboration of a ProposedPosition for Radiological Effluent and Environmental Measurements, NUREG/CR-4007(September1984), and in the HASL Procedures Manual, HASL-300 (revised annually).
88ODCM Rev. 27B-3.2SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITEEVAPORATIONPONDS - CONCENTRATIONThis requirement is provided to ensure that the annual total effective dose equivalent to individualmembers of the public from the licensed operation does not exceed the requirements of 10 CFR Part20, due to the accumulated activity in the evaporation ponds from the secondary systemdischarges.Restricting the concentrations of the secondary liquid wastes discharged to the onsite evaporationponds 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 ponds contents to anUNRESTRICTED 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 fromall reactor units to the onsite evaporation ponds. The required detection capabilities for radioactive materials in gaseous waste samples are tabulated interms of the lower limits of detection (LLD). Detailed discussion of the LLD and other detection limitscan be found in Currie,L.A., Lower Limit of Detection: Definition and Elaboration of a ProposedPosition for Radiological Effluent and Environmental Measurements, NUREG/CR-4007(September1984), and in the HASL Procedures Manual, HASL-300 (revised annually).B-4.1GASEOUS EFFLUENT - DOSE, Noble GasesThis requirement is provided to implement SectionsII.B, III.A and IV.A of AppendixI, 10CFRPart50. This requirement implements the guides set forth in SectionII.B of AppendixI. The ACTIONstatements provide the required operating flexibility and at the same time implement the guides setforth in SectionIV.A of AppendixI to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. Thesurveillance requirements implement the requirements in SectionIII.A of AppendixI that conformancewith the guides of AppendixI be shown by calculational procedures based on models and data suchthat the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely tobe substantially underestimated. The dose calculation methodology and parameters established in theODCM 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 Guide1.109, Calculation ofAnnual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of EvaluatingCompliance with 10CFR Part50, AppendixI, Revision1, October1977 and Regulatory Guide1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in RoutineReleases from Light-Water Cooled Reactors, Revision1, July1977. The ODCM equations providedfor determining the air doses at and beyond the SITE BOUNDARY are based upon the historicalaverage atmospheric conditions.This requirement applies to the release of radioactive materials in gaseous effluents from each reactorunit at the site.
89ODCM Rev. 27B-4.2GASEOUS EFFLUENT - DOSE - Iodine-131, Iodine-133, Tritium, andAllRadionuclidesinParticulate Form With Half-Lives Greater Than8DaysThis requirement is provided to implement the requirements of SectionsII.C, III.A, IV.A ofAppendixI, 10CFR Part50. This requirement is the guide set forth in SectionII.C of AppendixI. The ACTION statements provide the required operating flexibility and at the same time implement theguides set forth in SectionIV.A of AppendixI to assure that the releases of radioactive materials ingaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. TheODCM calculational methods specified in the surveillance requirements implement the requirements inSectionIII.A of AppendixI that conformance with the guides of AppendixI be shown by calculationalprocedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLICthrough appropriate pathways is unlikely to be substantially underestimated. The ODCM calculationalmethodology and parameters for calculating the doses due to the actual release rates of the subjectmaterials are consistent with the methodology provided in Regulatory Guide1.109, Calculation ofAnnual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of EvaluatingCompliance with 10CFR Part50, AppendixI, Revision1, October1977 and Regulatory Guide1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in RoutineReleases for Light-Water-Cooled Reactors, Revision1, July1977. These equations also provide fordetermining the actual doses based upon the historical average atmospheric conditions. The release ratespecifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-livesgreater than 8days are dependent upon the existing radionuclide pathways to man, in the areas at andbeyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1)individual inhalation of airborne radionuclides, (2)deposition of radionuclidesonto green leafy vegetation with subsequent consumption by man, (3)deposition onto grassy areaswhere 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 reactorunit at the site.B-4.3GASEOUS RADWASTE TREATMENTThe OPERABILITY of the GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUSTTREATMENT 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 ofthese systems be used, when specified, provides reasonable assurance that the releases of radioactivematerials in gaseous effluents will be kept as low as reasonably achievable. This requirementimplements the requirements of 10CFR50.36a, General Design Criterion60 of AppendixA to10CFR Part50, and the design objectives given in SectionII.D of AppendixI to 10CFR Part50. Thespecified limits governing the use of appropriate portions of the systems were specified as a suitablefraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50,for gaseous effluents.This requirement applies to the release of radioactive materials in gaseous effluents from each reactorunit at the site. The minimum analysis frequency of 4/M (i.e., at least 4times per month at intervals no greater than9days and a minimum of 48times a year) is used for certain radioactive gaseous waste sampling inTable3-1. This will eliminate taking double samples when quarterly and weekly samples are requiredat the same time.
90ODCM Rev. 27B-4.4SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITEEVAPORATION PONDS - DOSEThis requirement is provided to implement the requirements of SectionsII.A, III.A and IV.A ofAppendixI, 10CFR Part50. This requirement implements the guides set forth in SectionII.A of AppendixI. The ACTION statements provide the required operating flexibility and at the same timeimplement the guides set forth in SectionIV.A of AppendixI to assure that the releases of radioactivematerial in liquid effluents to UNRESTRICTED AREAS will be kept as low as is reasonablyachievable. Also, for fresh water sites with drinking water supplies that can be potentially affected byplant operations, there is reasonable assurance that the operation of the facility will not result inradionuclide concentrations in the finished drinking water that are in excess of the requirements of40CFR Part141. The dose calculation methodology and parameters in the ODCM implement therequirements in SectionIII.A of AppendixI that conformance with the guides of AppendixI be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OFTHE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. Theequations specified in the ODCM for calculating the doses due to the actual release rates of radioactivematerials in liquid effluents are consistent with the methodology provided in Regulatory Guide1.109,Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose ofEvaluating Compliance with 10CFR Part50, AppendixI, Revision1, October1977 and Regulatory Guide1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine ReactorReleases 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 withshared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.B-5.1TOTAL DOSE AND DOSE TO PUBLIC ONSITEThis requirement is provided to meet the dose limitations of 40CFR Part190 that have beenincorporated into 10CFR20.1301(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 of40CFR Part190 if the individual reactors remain within twice the dose design objectives of AppendixI, 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 ofthe annual dose to a MEMBER OF THE PUBLIC to within the 40CFR Part190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OFTHE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dosecontributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must beconsidered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of40CFR Part190, submittal of the Special Report within 30days with a request for a variance (providedthe release conditions resulting in violation of 40CFR Part190 have not already been corrected), inaccordance with the provisions of 40CFR Part190.11 and 10CFR Part20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40CFR Part190 until NRC staff action iscompleted. The variance only relates to the limits of 40CFR Part190, and does not apply in any way toother requirements for dose limitation of 10CFR Part20, as addressed in Section3.2 and3.1 of theODCM. 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 ofcompliance with the limits of 40CFR Part190 or with the design objectives of AppendixI to 10CFR Part50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.
91ODCM Rev. 27B-6.1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)The Radiological Environmental Monitoring Program required by this requirement providesrepresentative measurements of radiation and of radioactive materials in those exposure pathways andfor those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements SectionIV.B.2 ofAppendixI to 10CFR Part50 and thereby supplements the radiological effluent monitoring programby verifying that the measurable concentrations of radioactive materials and levels of radiation are nothigher than expected on the basis of the effluent measurements and the modeling of the environmentalexposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring programwill be effective for at least the first 3years of commercial operation. Following this period, programchanges may be initiated based on operational experience.The required detection capabilities for environmental sample analyses are tabulated in terms of thelower limits of detection (LLD). The LLDs required by Table6-3 are considered optimum for routineenvironmental measurements in industrial laboratories. It should be recognized that the LLD is definedas an apriori (before the fact) limit representing the capability of a measurement system and not as anaposteriori (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 Limitof Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent andEnvironmental Measurements, NUREG/CR-4007 (September1984), and in the HASL Procedures Manual, HASL-300 (revised annually).B-6.2LAND USE CENSUSThis requirement is provided to ensure that changes in the use of areas at and beyond the SITEBOUNDARY are identified and that modifications to the radiological environmental monitoringprogram are made if required by the results of this census. The best information from the door-to-doorsurvey, from aerial survey or from consulting with local agricultural authorities shall be used. Thiscensus satisfies the requirements of SectionIV.B.3 of AppendixI to 10CFR Part50. Restricting thecensus to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafyvegetables will be identified and monitored since a garden of this size is the minimum required toproduce the quantity (26kg/year) of leafy vegetables assumed in Regulatory Guide1.109 forconsumption by a child. To determine this minimum garden size, the following assumptions weremade: (1)20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce andcabbage), and (2)a vegetation yield of 2kg/m 2.B-6.3INTERLABORATORY COMPARISON PROGRAMThe requirement for participation in an Interlaboratory Comparison Program is provided to ensure thatindependent checks on the precision and accuracy of the measurements of radioactive material inenvironmental sample matrices are performed as part of the quality assurance program forenvironmental monitoring in order to demonstrate that the results are valid for the purposes ofSectionIV.B.2 of AppendixI to 10CFR Part50.
92ODCM Rev. 27APPENDIX CDEFINITIONS Note:The following definitions were derived from the Palo Verde Nuclear Generating Station TechnicalSpecifications. These selected definitions support those portions of the Technical Specifications which weretransferred 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 Requirementssections of this ODCM.ACTIONACTION shall be that part of a requirement which prescribes remedial measures required under designatedconditions.CHANNEL CALIBRATIONSee the Technical Specification definition.
CHANNEL CHECKSee the Technical Specification definition.
CHANNEL FUNCTIONAL TESTSee the Technical Specification definition.
DOSE EQUIVALENT I-131See the Technical Specification definition.
FUNCTIONAL-FUNCTIONALITYFunctionality is an attribute of a structure, system, or component SSC(s) that is not controlled by the TechnicalSpecifications (TSs). An SSC not controlled by Tss is functional or has functionality when it is capable ofperforming its function(s) as set forth in the current licensing basis (CLB). These CLB function(s) may includethe capability to perform a necessary and related support function for an SSC(s) controlled by TSs. FREQUENCY NOTATIONThe FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspondto the intervals defined in TableC-1.GASEOUS RADWASTE SYSTEMA GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseouseffluents by collecting primary coolant system offgases from the primary system and providing for delay orholdup for the purpose of reducing the total radioactivity prior to release to the environment.MAR 2016 93ODCM Rev. 27APPENDIX CDEFINITIONS (Continued)MEMBER(S) OF THE PUBLICMEMBER(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 thiscategory are persons who enter the site to service equipment or to make deliveries. This category does includepersons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.OPERABLE-OPERABILITYA system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it iscapable 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 relatedsupport function(s).
MODESee the Technical Specification definition.
PROCESS CONTROL PROGRAMThe PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, test, anddeterminations to be made to ensure that processing and packaging of solid radioactive wastes based ondemonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assurecompliance with 10CFR Parts20, 61, and 71, State regulations, burial ground requirements, and otherrequirements governing the disposal of solid radioactive waste.PURGE-PURGINGPURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintaintemperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacementair or gas is required to purify the confinement.RATED THERMAL POWERSee the Technical Specification definition.
SITE BOUNDARYThe SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwisecontrolled by the licensee.SOLIDIFICATIONSOLIDIFICATION 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 stablesurface of distinct outline on all sides (free-standing).
94ODCM Rev. 27APPENDIX CDEFINITIONS (Continued)SOURCE CHECKA SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor isexposed to a source of increased radioactivity.THERMAL POWERTHERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED AREAAn UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is notcontrolled by the licensee for the purposes of protection of individuals from exposure to radiation andradioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial,commercial, institutional, and/or recreational purposes.VENTILATION EXHAUST TREATMENT SYSTEMA VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reducegaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or ventexhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines orparticulates from the gaseous exhaust stream prior to the release to the environment. Such a system is notconsidered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanupsystems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.VENTINGVENTING 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 isnot provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
95ODCM Rev. 27*The specified Frequency for each Surveillance Requirement and Sampling Requirement is met if the Surveillance Requirement or Sampling Requirement is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.TABLE C-1FREQUENCY NOTATIONNOTATIONFREQUENCY*SAt least once per 12 hours.DAt least once per 24 hours.WAt least once per 7 days.
4/MAt least 4 times per month at intervals no greater than 9days and a minimum of 48 times per year.MAt least once per 31 days.QAt least once per 92 days.SAAt least once per 184 days.ANNUALLYAt least once per 365 daysRAt least once per 18 months.PCompleted prior to each release.S/UPrior to reactor startup.N.A.Not Applicable.MAR 2016MAR 2016 96ODCM Rev. 27APPENDIX DREFERENCES1Title10, Code of Federal Regulations, Part20, "Standards for Protection Against Radiation.2Title10, Code of Federal Regulations, Part50, "Domestic Licensing of Production and UtilizationFacilities."3Title 40, Code of Federal Regulations, Part 190, Environmental Radiation Protection Standardsfor Nuclear Power Operations.4Federal Register, Vol. 58, No. 245, Thursday, December 23, 1993, Notices, pages 68170-68179.
5Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-CooledNuclear Power Plants, Revision1, June1974.6Regulatory Guide1.109, Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10CFR Part50, AppendixI,Revision1, October1977.7Regulatory Guide1.111, Methods for Estimating Atmospheric Transport and Dispersion ofGaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision1, July1977.8Regulatory Guide4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear PowerPlants, Revision 1, April 1975.9NUREG-0133, Preparation of Radiological Effluent Technical Specifications For Nuclear PowerPlants, Oct. 1978.10NUREG 0841, Final Environmental Statement Related to the Operation of Palo Verde NuclearGenerating Station, Units 1, 2, and 3, Section 5.9.1.4, February, 1982.11NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological EffluentControls for Pressurized Water Reactor, Arpil 1991.12Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station,December 1981.13PVNGS Updated Final Safety Analysis Report 14Calculation 13-NC-ZY-252, Annual Average Dose from Normal Operation Liquid Dischargefrom the Evaporation Pond, Rev 0.15Calculation 13-NC-ZY-253, Annual Average Dose from Normal Operation Airborne Direct andSky Shine from the Evaporation Pond, Rev 0.16Calculation 13-NC-ZY-254, Radiation Dose Due to an Evaporation Pond Dike Failure During aSeismic Event, Rev. 0.


Appendix F Correction to the 2013 and 2015 PVNGS Annual Radiological Effluent Release Reports
Appendix F Correction to the 2013 and 2015 PVNGS Annual Radiological Effluent Release Reports
* 45 Summary of Individual Doses for 2014


These deviations were documented through Corrective Action program document Condition Report (CR) 17-01056.  
Osps                  A subsidiary of Pinnacle West Capital Corporation ID #:          218-04128 DATE:          04/14/2017                          Company Correspondence TO:            File Sta. #
Ext. #
Digitally signed by McDowell, Joshua FROM:          Joshua McDowell Sta. #
McDowell,                  (Z08270)
DN; cn=McDowell, Joshua (Z08270) 7397 Ext. #        82-5482                          Joshua (Z08270)
Date: 2017.04.14 03:52:25 -07'00'


The Nuclear Regulatory Commission questioned a 2013 release of Xenon-133 as documented on the 2013 PVNGS ARERR. In response to this question, it was discovered that an overly conservative value had been applied to a release permit. This is documented through CR 17-05289. 
==SUBJECT:==
Correction to Annual Radioactive Effluent Release Reports for 2015 and 2013 Palo Verde Nuclear Generating Station - Units 1,2, and 3


==REFERENCES:==
: 1. PVNGS Annual Radioactive Effluent Release Report for 2015
: 2. PVNGS Annual Radioactive Effluent Release Report for 2016
==Dear Sir or Madam:==
In accordance with Palo Verde Nuclear Generating Station (PVNGS) Technical Specification (TS) 5.6.2, PVNGS submitted the Annual Radioactive Effluent Release Report (ARERR) for 2015 via Reference 1. It was discovered that a refueling purge permit had been revised after data was gathered for this report. This led to particulate activity not being accounted for in the annual report.
The following 2015 ARERR tables were impacted and therefore revised in this submittal:
* 2 Batch Release Data
* 12 Unit 2 Gaseous Effluents - Summation of All Releases
* 15 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines
* 16 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates
* 17 Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines
* 18 Unit 2 Gaseous Effluents - Continuous and Batch - Particulates
* 30 Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total By Quarter
* 31 Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total By Quarter
* 32 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -
Total By Quarter
* 33 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Quarter
* 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total ByUnit
* 37 Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates - Total By Unit
* 38 Units 1,2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
Total By Unit
* 39 Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Unit
* 43 Doses To Special Locations For 2014
* 44 Integrated Population Dose for 2014
* 45 Summary of Individual Doses for 2014 These deviations were documented through Corrective Action program document Condition Report (CR) 17-01056.
The Nuclear Regulatory Commission questioned a 2013 release of Xenon-133 as documented on the 2013 PVNGS ARERR. In response to this question, it was discovered that an overly conservative value had been applied to a release permit. This is documented through CR 17-05289.
The following 2013 ARERR tables were impacted and therefore revised in this submittal:
The following 2013 ARERR tables were impacted and therefore revised in this submittal:
* 20 Unit 3 Gaseous Effluents - Summation Of All Releases
* 20 Unit 3 Gaseous Effluents - Summation Of All Releases
Line 1,094: Line 1,842:
* 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total By Unit
* 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total By Unit
* 38 Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
* 38 Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
Total By Unit  
Total By Unit


Table 20: Unit 3 Gaseous Effluents - Summation Of All Releases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total For Year Est. Total Error % (1) A. Fission & activation gases
Table 20:
: 1. Total release Ci 5.83E-02 6.98E-02 2.05E-01 2.46E+01 2.49E+01 3.54E+01 2. Average release rate for period  
Unit 3 Gaseous Effluents - Summation Of All Releases Total For  Est. Total Error Unit   Quarter 1   Quarter 2   Quarter 3     Quarter 4 Year           % (1)
&#xb5;Ci/sec 7.42E-03 8.88E-03 2.58E-02 3.09E+00 7.87E-01
A. Fission & activation gases
: 3. Percent of ODCM Requirement limit  
: 1. Total release                           Ci           5.83E-02     6.98E-02     2.05E-01       2.46E+01   2.49E+01     3.54E+01
% NA (2) NA (2) NA (2) NA (2) NA (2)
: 2. Average release rate for period         Ci/sec     7.42E-03     8.88E-03     2.58E-02       3.09E+00   7.87E-01
: 3. Percent of ODCM Requirement limit       %             NA (2)       NA (2)       NA (2)         NA (2)     NA (2)
B. Iodine 131
B. Iodine 131
: 1. Total Iodine 131 Ci 0.00E+00 0.00E+00 0.00E+00 6.58E-06 6.58E-06 3.32E+01 2. Average release rate for period  
: 1. Total Iodine 131                         Ci           0.00E+00     0.00E+00     0.00E+00       6.58E-06   6.58E-06     3.32E+01
&#xb5;Ci/sec 0.00E+00 0.00E+00 0.00E+00 8.28E-07 2.08E-07
: 2. Average release rate for period         Ci/sec     0.00E+00     0.00E+00     0.00E+00       8.28E-07   2.08E-07 35
: 3. Percent of ODCM Requirement limit  
: 3. Percent of ODCM Requirement limit       %             NA (2)       NA (2)       NA (2)         NA (2)     NA (2)
% NA (2) NA (2) NA (2) NA (2) NA (2)
C. Particulates
C. Particulates
: 1. Particulates with half- lives > 8 days Ci 1.51E-06 1.27E-06 2.72E-06 3.50E-04 3.56E-04 3.43E+01 2. Average release rate for period  
: 1. Particulates with half- lives > 8 days   Ci           1.51E-06     1.27E-06     2.72E-06       3.50E-04   3.56E-04     3.43E+01
&#xb5;Ci/sec 1.92E-07 1.61E-07 3.42E-07 4.40E-05 1.12E-05
: 2. Average release rate for period         Ci/sec     1.92E-07     1.61E-07     3.42E-07       4.40E-05   1.12E-05
: 3. Percent of ODCM Requirement limit  
: 3. Percent of ODCM Requirement limit       %
% NA (2) NA (2) NA (2) NA (2) NA (2) 4. Gross Alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium
NA (2)       NA (2)       NA (2)         NA (2)     NA (2)
: 1. Total release Ci 7.03E+01 1.35E+02 5.17E+02 2.13E+02 9.36E+02 3.85E+01 2. Average release rate for period  
: 4. Gross Alpha radioactivity               Ci           < LLD       < LLD       < LLD         < LLD       < LLD PVNGS ARERR 2014 D. Tritium
&#xb5;Ci/sec 8.94E+00 1.72E+01 6.50E+01 2.68E+01 2.96E+01
: 1. Total release                           Ci           7.03E+01     1.35E+02     5.17E+02       2.13E+02   9.36E+02     3.85E+01
: 3. Percent of ODCM Requirement limit  
: 2. Average release rate for period         Ci/sec     8.94E+00     1.72E+01     6.50E+01       2.68E+01   2.96E+01
% NA (2) NA (2) NA (2) NA (2) NA (2) (1) Estimated total error methodology is presented in Table 40. (2) See Table 27 for percent of ODCM Requirement limits.
: 3. Percent of ODCM Requirement limit       %           NA (2)         NA (2)       NA (2)         NA (2)     NA (2)
35 PVNGS A RERR2014 40 PVNGS A RERR2014  Table 25: Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 5.21E-02 6.17E-02 1.84E-01 4.93E-01 7.90E-01 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 3.95E-08 0.00E+00 3.95E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.25E-03 8.00E-03 2.15E-02 1.06E+00 1.10E+00 Xe-133m Ci 0.00E+00 0.00E+00 3.41E-07 8.13E+00 8.13E+00 Xe-135 Ci 0.00E+00 5.03E-05 1.67E-06 1.49E+01 1.49E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 5.83E-02 6.98E-02 2.05E-01 2.46E+01 2.49E+01 2. Iodines I-131 Ci 0.00E+00 0.00E+00 0.00E+00 6.58E-06 6.58E-06 I-132 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 0.00E+00 0.00E+00 0.00E+00 6.58E-06 6.58E-06 3 PVNGS A RERR2014  Table 27: Unit 3 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Air Dose mrad 1.37E-04 1.63E-04 4.84E-04 1.02E-02 1.10E-02 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 % ODCM Limit  
(1) Estimated total error methodology is presented in Table 40.
% 2.74E-03 3.26E-03 9.68E-03 2.04E-01 1.10E-01 Beta Air Dose mrad 5.01E-05 5.96E-05 1.76E-04 1.45E-02 1.48E-02 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 % ODCM Limit  
(2) See Table 27 for percent of ODCM Requirement limits.
% 5.01E-04 5.96E-04 1.76E-03 1.45E-01 7.40E-02 Maximum Organ Dose (excluding skin) mrem 2.52E-02 4.86E-02 1.85E-01 7.67E-02 3.36E-01 Age Teen Teen Teen Teen Teen Organ Thyroid 4.86E-02 Thyroid Lung 3.36E-01 ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 % ODCM Limit  
 
% 3.36E-01 6.48E-01 2.47E+00 1.02E+00 2.24E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.
Table 25:
4 PVNGS A RERR2014  Table 30: Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines -
Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit   Quarter 1     Quarter 2     Quarter 3     Quarter 4   Year total
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 2.08E+00 3.33E-01 3.56E-01 6.22E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 0.00E+00 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.21E-01 3.57E-02 3.52E-02 1.09E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 3.41E-07 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 5.03E-05 1.67E-06 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.83E+00 3.68E-01 3.92E-01 2.48E+01 2.84E+01 2. Iodines I-131 Ci 0.00E+00 9.92E-07 0.00E+00 0.00E+00 9.92E-07 I-132 Ci 0.00E+00 1.50E-05 0.00E+00 0.00E+00 1.50E-05 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 0.00E+00 1.60E-05 0.00E+00 0.00E+00 1.60E-05 5 PVNGS A RERR2014  Table 32: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -
: 1. Fission gases Ar-41             Ci       5.21E-02     6.17E-02       1.84E-01     4.93E-01   7.90E-01 Kr-83m             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Kr-85             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Kr-85m             Ci       0.00E+00     0.00E+00       3.95E-08     0.00E+00   3.95E-08 Kr-87             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Kr-88             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Kr-89             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Kr-90             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Xe-131m           Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Xe-133             Ci       6.25E-03     8.00E-03       2.15E-02     1.06E+00   1.10E+00 Xe-133m           Ci       0.00E+00     0.00E+00       3.41E-07     8.13E+00   8.13E+00 Xe-135             Ci       0.00E+00     5.03E-05       1.67E-06     1.49E+01   1.49E+01 Xe-135m           Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Xe-137             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Xe-138             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Total             Ci       5.83E-02     6.98E-02       2.05E-01     2.46E+01   2.49E+01
Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 2.08E+00 3.33E-01 3.56E-01 6.22E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 0.00E+00 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.21E-01 3.57E-02 3.52E-02 1.09E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 3.41E-07 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 5.03E-05 1.67E-06 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.83E+00 3.68E-01 3.92E-01 2.48E+01 2.84E+01 2. Iodines I-131 Ci 5.35E-06 5.61E-05 0.00E+00 6.58E-06 6.80E-05 I-132 Ci 1.39E-04 4.29E-04 0.00E+00 0.00E+00 5.68E-04 I-133 Ci 6.29E-06 0.00E+00 0.00E+00 0.00E+00 6.29E-06 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 1.51E-04 4.85E-04 0.00E+00 6.58E-06 6.42E-04 51 PVNGS A RERR2014  Table 36: Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine -
: 2. Iodines I-131             Ci       0.00E+00     0.00E+00     0.00E+00     6.58E-06   6.58E-06 I-132             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 I-133             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 I-134             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 I-135             Ci       0.00E+00     0.00E+00     0.00E+00     0.00E+00   0.00E+00 Total             Ci       0.00E+00     0.00E+00     0.00E+00     6.58E-06   6.58E-06 40                      PVNGS ARERR 2014
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 1. Fission gases Ar-41 Ci 2.07E+00 5.31E-01 7.90E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.09E-01 7.37E-02 1.10E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 0.00E+00 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.80E+00 6.05E-01 2.49E+01 2.84E+01 2. Iodines I-131 Ci 9.92E-07 0.00E+00 0.00E+00 9.92E-07 I-132 Ci 1.50E-05 0.00E+00 0.00E+00 1.50E-05 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 1.60E-05 0.00E+00 0.00E+00 1.60E-05
 
Table 27:
Unit 3 Radiation Doses At And Beyond The Site Boundary Unit   Quarter 1     Quarter 2     Quarter 3     Quarter 4 Year total Gamma Air Dose       mrad   1.37E-04     1.63E-04       4.84E-04     1.02E-02   1.10E-02 ODCM Req 4.1 Limit     mrad   5.00E+00     5.00E+00     5.00E+00     5.00E+00   1.00E+01
      % ODCM Limit         %     2.74E-03     3.26E-03       9.68E-03     2.04E-01   1.10E-01 Beta Air Dose       mrad   5.01E-05     5.96E-05       1.76E-04     1.45E-02   1.48E-02 ODCM Req 4.1 Limit     mrad   1.00E+01     1.00E+01     1.00E+01     1.00E+01   2.00E+01
      % ODCM Limit         %     5.01E-04     5.96E-04       1.76E-03     1.45E-01   7.40E-02 Maximum Organ Dose mrem   2.52E-02     4.86E-02       1.85E-01     7.67E-02   3.36E-01 (excluding skin)
Age                     Teen         Teen           Teen         Teen       Teen Organ                   Thyroid     4.86E-02       Thyroid       Lung     3.36E-01 ODCM Req. 4.2 Limit   mrem   7.50E+00     7.50E+00     7.50E+00     7.50E+00   1.50E+01
      % ODCM Limit         %     3.36E-01     6.48E-01     2.47E+00     1.02E+00   2.24E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.
3                          PVNGS ARERR 2014
 
Table 30:
Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines -
Total By Quarter Nuclides Released Unit   Quarter 1     Quarter 2     Quarter 3   Quarter 4 Year total
: 1. Fission gases Ar-41             Ci     2.08E+00       3.33E-01       3.56E-01     6.22E-01 3.39E+00 Kr-83m             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Kr-85             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Kr-85m             Ci     3.20E-08       0.00E+00       3.95E-08     0.00E+00 7.15E-08 Kr-87             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Kr-88             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Kr-89             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Kr-90             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Xe-131m           Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Xe-133             Ci     6.21E-01       3.57E-02       3.52E-02     1.09E+00 1.78E+00 Xe-133m           Ci     4.53E-07       0.00E+00       3.41E-07     8.13E+00 8.13E+00 Xe-135             Ci     1.29E-01       5.03E-05       1.67E-06     1.49E+01 1.51E+01 Xe-135m           Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Xe-137             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Xe-138             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Total             Ci     2.83E+00       3.68E-01       3.92E-01     2.48E+01 2.84E+01
: 2. Iodines I-131             Ci     0.00E+00       9.92E-07       0.00E+00     0.00E+00 9.92E-07 I-132             Ci     0.00E+00       1.50E-05       0.00E+00     0.00E+00 1.50E-05 I-133             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 I-134             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 I-135             Ci     0.00E+00       0.00E+00       0.00E+00     0.00E+00 0.00E+00 Total             Ci     0.00E+00       1.60E-05       0.00E+00     0.00E+00 1.60E-05 4                        PVNGS ARERR 2014
 
Table 32:
Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -
Total By Quarter Nuclides Released   Unit   Quarter 1     Quarter 2     Quarter 3   Quarter 4     Year total
: 1. Fission gases Ar-41               Ci       2.08E+00       3.33E-01     3.56E-01     6.22E-01     3.39E+00 Kr-83m             Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-85               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-85m             Ci       3.20E-08     0.00E+00       3.95E-08   0.00E+00     7.15E-08 Kr-87               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-88               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-89               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-90               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-131m             Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-133             Ci       6.21E-01       3.57E-02     3.52E-02   1.09E+00     1.78E+00 Xe-133m             Ci       4.53E-07     0.00E+00       3.41E-07   8.13E+00     8.13E+00 Xe-135             Ci       1.29E-01       5.03E-05     1.67E-06   1.49E+01     1.51E+01 Xe-135m             Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-137             Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-138             Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Total               Ci       2.83E+00       3.68E-01     3.92E-01   2.48E+01     2.84E+01
: 2. Iodines I-131               Ci       5.35E-06       5.61E-05     0.00E+00     6.58E-06     6.80E-05 I-132               Ci       1.39E-04       4.29E-04     0.00E+00   0.00E+00     5.68E-04 I-133               Ci       6.29E-06     0.00E+00       0.00E+00   0.00E+00     6.29E-06 I-134               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 I-135               Ci       0.00E+00     0.00E+00       0.00E+00   0.00E+00     0.00E+00 Total               Ci       1.51E-04       4.85E-04     0.00E+00     6.58E-06     6.42E-04 5                      PVNGS ARERR 2014
 
Table 36:
Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine -
Total By Unit Total Units Nuclides Released   Unit       Unit 1         Unit 2     Unit 3 1, 2 and 3
: 1. Fission gases Ar-41               Ci       2.07E+00       5.31E-01   7.90E-01     3.39E+00 Kr-83m               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-85               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-85m               Ci       3.20E-08       0.00E+00   3.95E-08     7.15E-08 Kr-87               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-88               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-89               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Kr-90               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-131m             Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-133               Ci       6.09E-01       7.37E-02   1.10E+00     1.78E+00 Xe-133m             Ci       4.53E-07       0.00E+00   8.13E+00     8.13E+00 Xe-135               Ci       1.29E-01       0.00E+00   1.49E+01     1.51E+01 Xe-135m             Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-137               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Xe-138                       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Total               Ci       2.80E+00       6.05E-01   2.49E+01     2.84E+01
: 2. Iodines I-131               Ci       9.92E-07       0.00E+00   0.00E+00     9.92E-07 I-132               Ci       1.50E-05       0.00E+00   0.00E+00     1.50E-05 I-133               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 I-134               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 I-135               Ci       0.00E+00       0.00E+00   0.00E+00     0.00E+00 Total               Ci       1.60E-05       0.00E+00   0.00E+00     1.60E-05 51                    PVNGS ARERR 2014
 
Table 38:
Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
Total By Unit Total Units Nuclides Released    Unit      Unit 1          Unit 2      Unit 3 1, 2 and 3
: 1. Fission gases Ar-41                Ci      2.07E+00        5.31E-01    7.90E-01      3.39E+00 Kr-83m              Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Kr-85                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Kr-85m              Ci      3.20E-08        0.00E+00    3.95E-08      7.15E-08 Kr-87                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Kr-88                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Kr-89                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Kr-90                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Xe-131m              Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Xe-133              Ci      6.09E-01        7.37E-02    1.10E+00      1.78E+00 Xe-133m              Ci      4.53E-07        0.00E+00    8.13E+00      8.13E+00 Xe-135              Ci      1.29E-01        0.00E+00    1.49E+01      1.51E+01 Xe-135m              Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Xe-137              Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Xe-138              Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Total                Ci      2.80E+00        6.05E-01    2.49E+01      2.84E+01
: 2. Iodines I-131                Ci      6.14E-05        0.00E+00    6.58E-06      6.80E-05 I-132                Ci      5.68E-04        0.00E+00    0.00E+00      5.68E-04 I-133                Ci      6.29E-06        0.00E+00    0.00E+00      6.29E-06 I-134                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 I-135                Ci      0.00E+00        0.00E+00    0.00E+00      0.00E+00 Total                Ci      6.36E-04        0.00E+00    6.58E-06      6.42E-04 52                          PVNGS ARERR 2014


52  Table 38: Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -
Table 1: Evaporation Pond Data                                Deleted Evaporation Pond 1(1A, 1B, 1C)            Quarter 1   Quarter 2 Quarter 3   Quarter 4    Year      Deleted Historical volume of water evaporated                                                                Deleted 3.22E+11    8.85E+11  8.85E+11    3.22E+11 (ml)                                                                                                Deleted Tritium Concentration (uCi/cc)              4.85E-06    3.34E-06  3.65E-06  2.98E-06              Deleted Tritium Curies                              1.83E-01    1.16E+00   1.21E+00   3.52E-01    2.91E+00 Deleted Evaporation Pond 2 (2A and 2B)            Quarter 1    Quarter 2 Quarter 3  Quarter 4    Year      Deleted Historical volume of water evaporated 2.40E+11    7.97E+11  7.97E+11    2.90E+11              Deleted (ml)
Total By Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total Units 1, 2 and 3 1. Fission gases Ar-41 Ci 2.07E+00 5.31E-01 7.90E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.09E-01 7.37E-02 1.10E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 0.00E+00 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.80E+00 6.05E-01 2.49E+01 2.84E+01 2. Iodines I-131 Ci 6.14E-05 0.00E+00 6.58E-06 6.80E-05 I-132 Ci 5.68E-04 0.00E+00 0.00E+00 5.68E-04 I-133 Ci 6.29E-06 0.00E+00 0.00E+00 6.29E-06 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 6.36E-04 0.00E+00 6.58E-06 6.42E-04
Deleted Tritium Concentration (uCi/cc)              1.45E-06    1.46E-06  1.75E-06  1.12E-06 Tritium curies                                                                                      Deleted 1.80E-01    4.91E-01  6.04E-01  1.45E-01    1.42E+00 Evaporation Pond 3 (3A and 3B)            Quarter 1    Quarter 2 Quarter 3  Quarter 4    Year      Deleted Historical volume of water evaporated                                                                Deleted 2.22E+11    3.05E+11  3.05E+11    1.11E+11 (ml)                                                                                                Deleted 3B Tritium Concentration (uCi/cc)          1.65E-06    1.08E-06  1.24E-06  8.76E-07              Deleted 3B Tritium curies                          1.81E-01    3.25E-01  3.73E-01  9.62E-02      9.76E-01 Deleted Dose (mRem)                                Quarter 1    Quarter 2 Quarter 3  Quarter 4    Year      Deleted Pond 1                                      7.61E-03    1.43E-02   1.50E-02  4.16E-03      4.12E-02 Deleted Pond 2                                      2.50E-03    6.81E-03  8.38E-03  2.01E-03      1.97E-02 Deleted Pond 3                                      2.51E-03    4.51E-03  5.18E-03  1.33E-03      1.35E-02 Deleted Total                                       6.71E-03    2.57E-02  2.86E-02  7.51E-03      7.44E-02 Deleted Deleted Deleted Table 2: Batch Release Data Deleted All times are in hours                    Unit 1        Unit 2        Unit 3 Deleted January - June Number of batch releases                                  20            24            43            Deleted Total time period for batch releases                    114.54        366.34        1275.06          Deleted Maximum time period for a batch release                  92.00       105.90        168.00          Deleted Average time period for a batch release                  5.73        15.26        29.65 Minimum time period for a batch release                                                              Deleted 0.53          0.51          0.10 July - December                                                                                      Deleted Number of batch releases                                  21            42            19            Deleted Total time period for batch releases                    161.18        1501.48      198.17 Deleted Maximum time period for a batch release                103.80        168.00       123.75 Average time period for a batch release                  7.68        35.75        10.43          Deleted Minimum time period for a batch release                  0.52          0.18          0.50          Deleted January - December                                                                                  Deleted Number of batch releases                                  41            66            62 Deleted Total time period for batch releases                    275.72        1867.82      1473.23 Maximum time period for a batch release                103.80        168.00       168.00           Deleted Average time period for a batch release                  6.72        28.30        23.76          Deleted Minimum time period for a batch release                  0.52          0.18          0.10          Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted


Table 1: Evaporation Pond Data Evaporation Pond 1(1A, 1B, 1C) Quarter1Quarter2Quarter3Quarter 4 YearHistorical volume of water evaporated (ml) 3.22E+11 8.85E+11 8.85E+11 3.22E+11 Tritium Concentration (uCi/cc) 4.85E-06 3.34E-06 3.65E-06 2.98E-06 Tritium Curies 1.83E-01 1.16E+00 1.21E+00 3.52E-01 2.91E+00 Evaporation Pond 2 (2A and 2B) Quarter1Quarter2Quarter3Quarter 4 YearHistorical volume of water evaporated (ml) 2.40E+11 7.97E+11 7.97E+11 2.90E+11 Tritium Concentration (uCi/cc) 1.45E-06 1.46E-06 1.75E-06 1.12E-06 Tritium curies 1.80E-01 4.91E-01 6.04E-01 1.45E-01 1.42E+00 Evaporation Pond 3 (3A and 3B) Quarter1Quarter2Quarter3Quarter 4 YearHistorical volume of water evaporated (ml) 2.22E+11 3.05E+11 3.05E+11 1.11E+11 3B Tritium Concentration (uCi/cc) 1.65E-06 1.08E-06 1.24E-06 8.76E-07  3B Tritium curies 1.81E-01 3.25E-01 3.73E-01 9.62E-02 9.76E-01 Dose (mRem) Quarter1Quarter2Quarter3Quarter 4 YearPond 1 7.61E-031.43E-021.50E-024.16E-03 4.12E-02Pond 2 2.50E-03 6.81E-03 8.38E-03 2.01E-03 1.97E-02 Pond 3 2.51E-03 4.51E-03 5.18E-03 1.33E-03 1.35E-02 Total 6.71E-03 2.57E-02 2.86E-02 7.51E-03 7.44E-02
Table 12:
Unit 2 Gaseous Effluents - Summation Of All Releases Total For  Est. Total Error Unit    Quarter 1     Quarter 2    Quarter 3    Quarter 4 Year          % (1)
A. Fission & activation gases
: 1. Total release                            Ci            8.53E-02      9.98E-02      1.12E-01    9.63E+00      9.93E+00        3.54E+01  Deleted
: 2. Average release rate for period          Ci/sec      1.10E-02      1.27E-02      1.41E-02    1.21E+00       3.15E-01                 Deleted
: 3. Percent of ODCM Requirement limit        %                                                                                              Deleted NA (2)        NA (2)        NA (2)       NA (2)       NA (2)
Deleted B. Iodine 131 Deleted
: 1. Total Iodine 131                        Ci          0.00E+00      0.00E+00      0.00E+00      2.38E-05      2.38E-05                  Deleted 3.32E+01
: 2. Average release rate for period          Ci/sec                                                                                        Deleted 0.00E+00      0.00E+00      0.00E+00      2.99E-06      7.55E-07 Deleted
: 3. Percent of ODCM Requirement limit        %        NA (2)        NA (2)        NA (2)       NA (2)       NA (2)                        Deleted C. Particulates                                                                                                                            Deleted
: 1. Particulates with half- lives > 8 days  Ci                                                                                              Deleted 0.00E+00      0.00E+00      0.00E+00      8.97E-04      8.97E-04        3.43E+01 Deleted
: 2. Average release rate for period          Ci/sec      0.00E+00      0.00E+00      0.00E+00      1.13E-04      2.85E-05                  Deleted
: 3. Percent of ODCM Requirement limit        %        NA (2)      NA (2)        NA (2)        NA (2)        NA (2)                        Deleted
: 4. Gross Alpha radioactivity                Ci                                                                                              Deleted
                                                    < LLD        < LLD        < LLD        < LLD        < LLD Deleted D. Tritium Deleted
: 1. Total release                            Ci          3.18E+02      1.04E+02      1.76E+02      3.22E+02      9.20E+02       3.85E+01  Deleted
: 2. Average release rate for period          Ci/sec      4.09E+01      1.32E+01      2.21E+01      4.05E+01      2.92E+01 Deleted Deleted
: 3. Percent of ODCM Requirement limit        %
NA (2)        NA (2)        NA (2)        NA (2)        NA (2)                        Deleted (1) Estimated total error methodology is presented in Table 40.                                                                             Deleted (2) See Table 19 for percent of ODCM Requirement limits.                                                                                   Deleted Deleted Deleted


Table 2: Batch ReleaseDataAll times are in hours Unit 1 Unit 2 Unit 3 Januar y - June Number of batch releases 20 24 43 Total time period for batch releases 114.54 366.34 1275.06 Maximum time period for a batch release 92.00 105.90 168.00 Average time period for a batch release5.73 15.26 29.65 Minimum time period for a batch release0.53 0.51 0.10 July - Decembe r    Number of batch releases 21 42 19 Total time period for batch releases 161.18 1501.48 198.17 Maximum time period for a batch release 103.80 168.00 123.75 Average time period for a batch release7.68 35.75 10.43 Minimum time period for a batch release0.52 0.18 0.50 January - Decembe r    Number of batch releases 41 66 62 Total time period for batch releases 275.72 1867.82 1473.23 Maximum time period for a batch release 103.80 168.00 168.00 Average time period for a batch release6.72 28.30 23.76 Minimum time period for a batch release0.52 0.18 0.10 Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Table 12: Unit 2 Gaseous Effluents - Summation Of All Releases Unit  Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total For Year Est. Total Error % (1) A. Fission & activation gases
Table 15:
: 1. Total release Ci 8.53E-029.98E-021.12E-019.63E+009.93E+003.54E+012. Average release rate for period
Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released   Unit   Quarter 1   Quarter 2     Quarter 3     Quarter 4   Year total
&#xb5;Ci/sec 1.10E-021.27E-021.41E-021.21E+003.15E-01 3. Percent of ODCM Requirement limit
: 1. Fission gases Ar-41               Ci         7.29E-02    8.42E-02      9.39E-02      7.60E+00      7.86E+00 Kr-83m             Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Kr-85               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Kr-85m             Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Kr-87               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Kr-88               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Kr-89               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Kr-90               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Xe-131m             Ci         0.00E+00      0.00E+00    0.00E+00      9.77E-04      9.77E-04 Xe-133             Ci         1.24E-02    1.56E-02      1.79E-02      1.73E+00      1.77E+00 Xe-133m             Ci         0.00E+00      0.00E+00    0.00E+00      1.38E-03      1.38E-03 Xe-135             Ci         0.00E+00      0.00E+00      9.12E-05      0.00E+00      9.12E-05 Deleted Xe-135m             Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted Xe-137             Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted Xe-138             Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Total              Ci                                                                         Deleted 8.53E-02    9.98E-02      1.12E-01      9.34E+00      9.63E+00
% NA (2)  NA (2) NA (2) NA (2) NA (2)  B. Iodine 131
: 2. Iodines                                                                                     Deleted I-131               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted I-132               Ci         0.00E+00      0.00E+00    0.00E+00      7.30E-05      7.30E-05 Deleted I-133               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted I-134               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted I-135               Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted Total              Ci         0.00E+00      0.00E+00    0.00E+00      0.00E+00      0.00E+00 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 30                        PVNGS ARERR 2014}}
: 1. Total Iodine 131 Ci 0.00E+000.00E+000.00E+002.38E-052.38E-053.32E+012. Average release rate for period
&#xb5;Ci/sec 0.00E+000.00E+000.00E+002.99E-067.55E-07
: 3. Percent of ODCM Requirement limit
% NA (2)  NA (2)  NA (2) NA (2) NA (2)  C. Particulates
: 1. Particulates with half- lives > 8 days Ci 0.00E+000.00E+000.00E+008.97E-048.97E-043.43E+012. Average release rate for period
&#xb5;Ci/sec 0.00E+000.00E+000.00E+001.13E-042.85E-05 3. Percent of ODCM Requirement limit
%  NA (2)  NA (2)  NA (2) NA (2) NA (2)  4. Gross Alpha radioactivity Ci < LLD  < LLD < LLD  < LLD  < LLD  D. Tritium
: 1. Total release Ci 3.18E+021.04E+021.76E+023.22E+029.20E+023.85E+012. Average release rate for period
&#xb5;Ci/sec 4.09E+011.32E+012.21E+014.05E+012.92E+01
: 3. Percent of ODCM Requirement limit
% NA (2)  NA (2)  NA (2) NA (2) NA (2)
(1) Estimated total error methodology is presented in Table 40. (2) See Table 19 for percent of ODCM Requirement limits.
Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d 30 PVNGS A RERR2014  Table 15: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 1. Fission gases Ar-41 Ci 7.29E-028.42E-029.39E-027.60E+007.86E+00Kr-83m Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Kr-85 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Kr-85m Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Kr-87 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Kr-88 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Kr-89 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Kr-90 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00 Xe-131m Ci 0.00E+000.00E+000.00E+009.77E-049.77E-04Xe-133 Ci 1.24E-021.56E-021.79E-021.73E+001.77E+00 Xe-133m Ci 0.00E+000.00E+000.00E+001.38E-031.38E-03Xe-135 Ci 0.00E+000.00E+009.12E-050.00E+009.12E-05 Xe-135m Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Xe-137 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Xe-138 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Total Ci 8.53E-029.98E-021.12E-019.34E+009.63E+002. Iodines I-131 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00I-132 Ci 0.00E+000.00E+000.00E+007.30E-057.30E-05I-133 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00I-134 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00I-135 Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00Total Ci 0.00E+000.00E+000.00E+000.00E+000.00E+00 Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d Delete d}}

Latest revision as of 18:51, 4 February 2020

Annual Radioactive Effluent Release Report 2016
ML17115A383
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/21/2017
From: Weber T
Arizona Public Service Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
102-07491 TNW/MDD/TMJ
Download: ML17115A383 (215)
v • d • e


Text

Technical Specification 5.6.3 Technical Requirements Manual 3.7.102.4 Qaps Palo Verde Nuclear Generating Station PO Box 52034 102-07491 TNW/MDD/TMJ Phoenix, Arizona 85072-2034 April 21, 2017 Maii Station 7636 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, 3 and Independent Spent Fuel Storage Installation Docket Nos. STN 50-528/529/530 and 72-44 Annual Radioactive Effluent Release Report 2016 In accordance with Technical Specification 5.6.3, the annual radioactive effluent release report for 2016 is enclosed.

PVNGS Technical Requirement Manual section 3.7.102.4 requires an annual report to be prepared and submitted if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 micro curies of removable radiation. There were no events in 2016 that met this reporting threshold.

No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Michael DiLorenzo, Licensing Section Leader, at (623) 393-3495.

Sincerely, Weber, Thomas DN: cn=Weber, Thomas N(Z00499)

N(Z00499) Reason: l am approving this document Date: 2017.04.21 14:47:11 -07'00' Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/TMJ/sma

Enclosure:

Palo Verde Nuclear Generating Station Units 1, 2 and 3 2016 Annual Radioactive Effluent Release Report cc: K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. M. Watford NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS A. V. Godwin Arizona Radiation Regulatory Agency (ARRA)

T. Morales Arizona Radiation Regulatory Agency (ARRA)

A member of the STARS Alliance LLC Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure Palo Verde Nuclear Generating Station Units 1, 2, & 3 2016 Annual Radioactive Effluent Release Report

PALO VERDE NUCLEAR GENERATING STATION UNITS 1,2 AND 3 2016 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT USNRC Docket No. STN 50-528/529/530 RCTSA11566 e 4 McDowell, Digitally signed by McDowell, Joshua (Z08270)

DN: cn=McDowel(. Joshua (Z08270)

Joshua Reason; I am the author of this document Prepared by: (Z08270) Date; 2017.04.14 17:42:41

-OT-OO*

Routolo, M(Z99739)

Oigtially signed by RouUilo, Robert Reviewed by: Robert ON: cneRoototo, Robert M(Ze9739)

Reason: t have reviewed trtls document M(Z99739)

Date: 2017.04,15 05:55:37 -07W Approved by: Digitally signed by Moeller, Carl (Z09119)

DN: cn=Moeller, Carl Carl (Z09119)

Date: 2017.04.15 (Z09119) 07:46:51 -07'00'

TABLE OF CONTENTS SECTION PAGE INTRODUCTION ........................................................................................................................................... 5 BIBLIOGRAPHY ............................................................................................................................................ 6 APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS........................... 7 APPENDIX B METEOROLOGY .................................................................................................................. 61 APPENDIX C DOSE CALCULATIONS ....................................................................................................... 84 APPENDIX D NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING ................................ 93 LIST OF TABLES TABLE PAGE 1 Evaporation Pond Data ..................................................................................................................................... 17 2 Batch Release Data .......................................................................................................................................... 17 3 Units 1, 2 & 3 Gaseous Effluents Average Lower Limit Of Detection ............................................................... 18 4 Unit 1 Gaseous Effluents - Summation of All Releases .................................................................................... 19 5 Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ...................... 20 6 Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates.............................................. 21 7 Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines ............................... 22 8 Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates ....................................................... 23 9 Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines .............................................. 24 10 Unit 1 Gaseous Effluents - Continuous and Batch - Particulates ..................................................................... 25 11 Unit 1 Radiation Doses at and Beyond the Site Boundary ............................................................................... 26 PVNGS 2016 ARERR Page 2

LIST OF TABLES TABLE PAGE 12 Unit 2 Gaseous Effluents - Summation of All Releases ................................................................................... 27 13 Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ..................... 28 14 Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates ............................................. 29 15 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines............................... 30 16 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates ...................................................... 31 17 Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines ............................................. 32 18 Unit 2 Gaseous Effluents - Continuous and Batch - Particulates ..................................................................... 33 19 Unit 2 Radiation Doses at and Beyond the Site Boundary ............................................................................... 34 20 Unit 3 Gaseous Effluents - Summation of All Releases ................................................................................... 35 21 Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines ..................... 36 22 Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates ............................................. 37 23 Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines............................... 38 24 Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates ...................................................... 39 25 Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines ............................................. 40 26 Unit 3 Gaseous Effluents - Continuous and Batch - Particulates ..................................................................... 41 27 Unit 3 Radiation Doses at and Beyond the Site Boundary ............................................................................... 42 PVNGS 2016 ARERR Page 3

LIST OF TABLES TABLE PAGE 28 Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines - Total By Quarter ................ 43 29 Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates - Total By Quarter ........................................ 44 30 Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total By Quarter.......................... 45 31 Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total By Quarter ................................................. 46 32 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines - Total By Quarter 47 33 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Quarter ....................... 48 34 Units 1, 2 and 3 Gaseous Effluents- Continuous - Fission Gases and Iodine - Total By Unit .......................... 49 35 Units 1, 2 and 3 Gaseous Effluents- Continuous - Particulates - Total By Unit ................................................ 50 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total By Unit ................................... 51 37 Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates - Total By Unit ......................................................... 52 38 Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine - Total By Unit ......... 53 39 Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Unit .............................. 54 40 Estimation of Total Percent Error ...................................................................................................................... 55 41 Effluent Monitoring Instrumentation Out of Service Greater than 30 Days ...................................................... 56 42 Solid Waste Summary ...................................................................................................................................... 57 43 Doses To Special Locations For 2016 .............................................................................................................. 87 44 Integrated Population Dose for 2016 ................................................................................................................ 88 45 Summary of Individual Doses for 2016 ............................................................................................................ 92 PVNGS 2016 ARERR Page 4

INTRODUCTION This report summarizes effluent and waste disposal source term data, meteorological data, and doses from radioactive effluents for the Palo Verde Nuclear Generating Station (PVNGS) for the period of January through December 2016. The data presented meets the reporting requirements of Regulatory Guide 1.21 (Revision 1, June 1974) of the U.S. Nuclear Regulatory Commission and the PVNGS Technical Specifications.

PVNGS 2016 ARERR Page 5

BIBLIOGRAPHY U.S. Nuclear Regulatory Commission, 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, 1974.

U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23 (Safety Guide 23), Onsite Meteorological Programs, 1972.

U.S. Nuclear Regulatory Commission, NUREG/CR-2919, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, 1982.

U.S. Nuclear Regulatory Commission, NUREG-0579, Users Guide to GASPAR Code, June 1980.

U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, Revision 1, 1977.

U.S. Nuclear Regulatory Commission, NUREG-0172, Age-specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, 1977.

U.S. Nuclear Regulatory Commission, NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, 1978.

Technical Specifications, Palo Verde Nuclear Generating Station, Units 1, 2 and 3, Docket No. 50-528/529/530.

Bechtel Power Corp., Cooling Tower Blowdown System Solar Evaporation Pond, Sept. 1980.

Generation Engineering, Geotechnical Exploration for Evaporation Pond #2, Oct. 1986 Letter No. 212-00789-WFQ/RHM, 1989 PVNGS Evaporation Pan Data, Jan. 1989.

Offsite Dose Calculation Manual Palo Verde Nuclear Generating Station Units 1, 2 and 3, Rev. 27.

NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.

Calculation 13-NC-CH-0200, Rev 7,FSAR - Primary Coolant Activities (PCA)

PVNGS 2016 ARERR Page 6

APPENDIX A SOURCE TERMS AND EFFLUENT AND WASTE DISPOSAL REPORTS PVNGS 2016 ARERR Page 7

Supplemental Information 1.0 REGULATORY LIMITS 1.1 Liquid Releases 1.1.1 PVNGS ODCM Requirement 3.2 The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:

5.0E-07 Ci/ml for principal gamma-emitters (except Ce-144) 3.0E-06 Ci/ml for Ce-144 1.0E-06 Ci/ml for I-131.

1.0E-03 Ci/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 Ci/ml for Cs-134 2.0E-06 Ci/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 1.1.2 PVNGS ODCM Requirement 4.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor, to areas at and beyond the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

PVNGS 2016 ARERR Page 8

1.2 Gaseous Releases 1.2.1 PVNGS ODCM Requirement 3.1 The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

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

1.2.2 PVNGS ODCM Requirement 4.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

1.2.3 PVNGS ODCM Requirement 4.2 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 shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
b. During any calendar year: Less than or equal to 15 mrem to any organ.

1.2.4 PVNGS ODCM Requirement 4.3 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, 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 when averaged over 31 days, would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

PVNGS 2016 ARERR Page 9

1.3 Total Dose 1.3.1 PVNGS ODCM Requirement 5.1 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 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS Air: Release Concentrations are limited to dose rate limits described in section 1.2.1 of this report.

3.0 AVERAGE ENERGY The average energy (E) of the radionuclide mixture in releases of fission and activation gases is not applicable to PVNGS.

4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY IN GASEOUS EFFLUENTS For continuous releases, sampling is in accordance with PVNGS ODCM Table 3-1.

Particulate and iodine radionuclides are sampled continuously at the Plant Vent and Fuel Building exhaust points. The particulate filters and charcoal cartridges are exchanged for analysis at least four times per month. Noble gas and tritium are sampled at least once per 31 days. The hourly average Radiation Monitoring System (RMS) effluent monitor readings are used, when available, to account for increases and decreases in noble gas concentrations between noble gas grab samples. The tritium concentration is assumed constant between sampling periods.

For batch releases, sampling is also in accordance with PVNGS ODCM Table 3-1. For containment purges, the noble gas concentration may be adjusted to account for decreases or increases in concentration during the purge using RMS readings. The volume of air released during the purge is determined using the exhaust fan rated flow rate. For Waste Gas Decay Tank releases, the volume released is corrected to standard pressure.

Effective January 1, 2004, Containment Purge release permits are updated by removing the permit pre-release particulate and iodine activity. This eliminates double accounting for the Containment Purge particulate and iodine activity at the Plant Vent but allows the particulate and iodine activity to be included in the Containment Purge pre-release dose projection.

The Lower Limit of Detection (LLD) of a measurement system is defined in Table 3 - 1 of the PVNGS ODCM. An average LLD for each radionuclide is provided in Table 3.

PVNGS 2016 ARERR Page 10

5.0 BATCH RELEASES 5.1 Gaseous Batch release durations are presented in Table 2.

5.2 Liquid None.

6.0 ABNORMAL RELEASES None 7.0 OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL PROGRAM (PCP) REVISIONS 7.1 The Offsite Dose Calculation Manual (ODCM) was revised in 2016. A complete copy of the ODCM is attached as Appendix E of this report. Revision 27 of the ODCM went effective on 3/25/2016.

7.1 There were no revisions to the Process Control Program (PCP) in 2016.

8.0 EFFLUENTS AND SOLID WASTES 8.1 Gaseous Effluents Gaseous effluent information is presented in Table 1 through Table 41. Included in these tables are summaries of the effluents and estimated total error.

8.2 Liquid Effluents There were no liquid effluent releases beyond the Site Boundary from PVNGS.

8.3 Solid Waste Solid waste shipments are summarized in Table 42.

PVNGS 2016 ARERR Page 11

9.0 MISCELLANEOUS INFORMATION 9.1 EVAPORATION PONDS Releases made to the Evaporation Ponds are limited to the concentrations specified in PVNGS ODCM Requirement 3.2. The Evaporation Ponds were monitored in accordance with PVNGS ODCM Requirement 6.1.

The average historical evaporation is approximately 12 inches, per pond, for each of the first and fourth quarters, and 33 inches, per pond, for each of the second and third quarters. Evaporation Pond One is approximately 250 acres. This equates to 3.08E+11 cc evaporated from Pond One for each of the first and fourth quarters and 8.48E+11 cc evaporated from Pond One for each of the second and third quarters. Evaporation Pond Two is approximately 235 acres. The amount evaporated from Pond Two is 2.90E+11 cc for each of the first and fourth quarters and 7.97E+11 cc for each of the second and third quarters.

Evaporation Pond Three is constructed of two smaller ponds of 90 acres each (3A and 3B). The amount evaporated from each section of Pond Three is 1.11E+11 cc for each of the first and fourth quarters and 3.05E+11 cc for each of the second and third quarters.

Using a site boundary X/Q of 5.0E-05 sec/m 3 for the evaporation ponds and equation 4-3 from the ODCM, the dose from the evaporation ponds to a hypothetical individual at the site boundary, for all pathways, is summarized in Table 1.

9.2 RADIATION MONITORING SYSTEM SETPOINT VERIFICATION Current effluent monitor noble gas channel alert alarm setpoints are based on an assumed one percent failed fuel source term. The current method used for the setpoint values are more reliable than basing the setpoints upon the constantly varying values of the actual noble gas source term presented in Table 38.

9.3 RCS RADIOIODINE (TRM T5.0.600)

There were no cases where primary coolant specific activity exceeded the Technical Specification 3.4.17 limits during the reporting period.

9.4 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

There are no radioactive effluents from the NAC-UMS System. Direct dose at the Site Boundary is reported in the Annual Radiological Environmental Operating Report.

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9.5 MAJOR CHANGES TO THE RADIOACTIVE WASTE SYSTEMS (liquid, gaseous, and solid).

None.

9.6 SAMPLES RESULTS FROM GROUNDWATER WELLS THAT ARE NOT DESCRIBED IN THE ODCM AS PART OF THE REMP (NEI 07-07, Industry Groundwater Protection Initiative, August 2007), are included in Appendix D. This initiative provides added assurance that groundwater will not be adversely affected by PVNGS operations.

There were no NEI 07-07 reportable leaks or spills. There were no positive sample results.

9.7 REPORT ADDENDUM There were two addendums to this report. The first is a correction to the 2013 ARERR and the second is a correction to the 2013 ARERR.

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10.0 DISCUSSION 10.1 Unit One Unit One operated with a refueling outage (1R19) from April 9, 2016 to May 14, 2016.

Maintenance outages:

1M20A September 7, 2016 to September 13, 2016 Estimated number of fuel defects (source: INPO, CDE)

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 0 0 0 0 0 0 0 0 0 0 0 10.2 Unit Two Unit Two operated without a refueling outage during 2016.

Maintenance outages:

NONE Estimated number of fuel defects (source: INPO, CDE)

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 0 0 0 0 0 0 0 0 0 0 0 10.3 Unit Three Unit Three operated with a refueling outage (3R19) from October 8, 2016 to November 5, 2016.

Maintenance outages:

3M19A September 19, 2016 to September 23, 2016.

Estimated number of fuel defects (source: INPO, CDE)

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 0 0 0 0 0 0 0 0 0 0 0 PVNGS 2016 ARERR Page 14

10.4 Carbon-14 Carbon-14 is formed naturally in the upper atmosphere and also is formed in operating nuclear reactors.

Carbon-14 is not a new power plant emission. Because the overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations, carbon-14 may now qualify as a "principal radionuclide" under revised federal regulatory guidance. The levels of other releases have declined, so carbon-14 releases, expressed as a percentage of total releases, have the potential to achieve "principal radionuclide" status (anything greater than one percent of overall radioactivity in effluents) per updated federal regulatory guidance.

The radiation dose to the public from carbon-14 is much lower than regulatory limits and has been a very small contributor to the total radiation dose that Americans receive each year from natural and man-made sources.

Studies by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Research Councils BEIR VII study group and the National Council on Radiation Protection and Measurements all show that the risk associated with low-dose radiation from natural and man-made sources, including nuclear power plants, is negligible.

Radiation is measured in units called millirem. The average American is exposed to 620 millirem of radiation every year. Approximately 311 millirem of this comes from natural sources. The majority of the remaining dose (approximately 300 millirem) comes from medical procedures such as CAT scans. Less than one-tenth of a percent of all radiation exposure is from nuclear facilities.

Reference:

NCRPReport No. 160, Table 1.1.

Starting with the 2010 Annual Radioactive Effluent Release Report, PVNGS will include the estimated exposure from carbon-14 in the Appendix C, dose calculations. The PVNGS calculated production of carbon-14 is 18.5 Curies per cycle (500 days) or 13.5 curies per year. Based on published literature, twenty percent (20%) of the carbon-14 released is assumed to be in an inorganic form (CO2). PVNGS will use an estimated value of 2.7 curies of carbon-14 released, per reactor, per year. The 2.7 curies will be divided equally between each quarter (0.68 curies per reactor, per quarter). Appendix C, dose calculations include this estimated carbon-14 dose. Appendix C also includes the dose excluding carbon-14 for comparison with historical reports.

10.5 Tritium PVNGS does not have a liquid release pathway. Removal of tritium is performed by operation of the Boric Acid Concentrator (BAC) in the release mode.

Comparison of PVNGS annual tritium Curies released to other utilities should be made only after summing both liquid and gaseous tritium Curies released.

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10.6 Dose Summary Dose for 2016 was primarily due to the release of tritium. Tritium production is estimated to be 1000 curies per reactor per year. In order to control plant tritium concentrations, tritium releases should match tritium production. For 2016, PVNGS released a total of 2360 curies of tritium (see Table 39).

Total dose due to releases from all three Units for 2016 were higher than 2015, primarily due to increased releases of tritium.

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Table 1: Evaporation Pond Data Evaporation Pond 1 (1A, 1B, 1C) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Historical volume of water evaporated (ml) 3.22E+11 8.85E+11 8.85E+11 3.22E+11 Tritium Concentration (uCi/cc) 2.84E-06 4.23E-06 2.38E-06 2.38E-06 Tritium Curies 3.22E-01 1.26E+00 7.22E-01 2.63E-01 2.57E+00 Evaporation Pond 2 (2A and 2B) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Historical volume of water evaporated (ml) 2.49E+11 7.97E+11 7.97E+11 2.90E+11 Tritium Concentration (uCi/cc) 1.36E-06 1.32E-06 1.80E-06 2.88E-06 Tritium curies 1.73E-01 4.60E-01 5.99E-01 3.66E-01 1.60E+00 Evaporation Pond 3 (3A and 3B) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Historical volume of water evaporated (ml) 2.20E+11 3.05E+11 3.05E+11 1.11E+11 3B Tritium Concentration (uCi/cc) 1.48E-06 1.51E-06 2.88E-06 2.27E-06 3B Tritium curies 1.63E-01 4.55E-01 8.69E-01 2.49E-01 1.74E+00 Dose (mRem) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Pond 1 3.80E-03 1.34E-02 8.60E-03 3.13E-03 2.89E-02 Pond 2 2.40E-03 6.38E-03 8.31E-03 5.08E-03 2.22E-02 Pond 3 2.26E-03 6.31E-03 1.20E-02 3.45E-03 2.41E-02 Total 8.46E-03 2.61E-02 2.90E-02 1.17E-02 7.52E-02 Table 2: Batch Release Data All times are in hours Unit 1 Unit 2 Unit 3 January - June Number of batch releases 44 20 16 Total time period for batch releases 1901.21 58.82 76.17 Maximum time period for a batch release 168.00 35.27 53.70 Average time period for a batch release 43.21 2.94 4.76 Minimum time period for a batch release 0.10 0.31 0.60 July - December Number of batch releases 23 24 47 Total time period for batch releases 322.13 1184.67 1908.40 Maximum time period for a batch release 100.85 1045.92 168.00 Average time period for a batch release 14.01 49.36 40.60 Minimum time period for a batch release 0.57 0.57 0.02 January - December Number of batch releases 67 44 63 Total time period for batch releases 2223.34 1243.50 1984.57 Maximum time period for a batch release 168.00 1045.92 168.00 Average time period for a batch release 33.18 28.26 31.50 Minimum time period for a batch release 0.10 0.31 0.02 PVNGS 2016 ARERR Page 17

Table 3:

Units 1, 2 & 3 Gaseous Effluents Average Lower Limit Of Detection Ci/cc Nuclide Continuous Batch Nuclide Continuous Batch Antimony-122 2.20E-13 1.90E-11 Argon-41 4.50E-08 4.50E-08 Antimony-124 8.40E-14 1.70E-11 Krypton-85 7.40E-06 7.40E-06 Barium-140 3.40E-13 5.70E-11 Krypton-85m 2.20E-08 2.20E-08 Bromine-82 3.30E-13 1.40E-11 Krypton-87 5.70E-08 5.70E-08 Cerium-141 8.70E-14 3.10E-11 Krypton-88 7.40E-08 7.40E-08 Cerium-144 3.60E-13 6.50E-11 Xenon-125 2.20E-08 2.20E-08 Cesium-134 1.00E-13 2.60E-11 Xenon-127 2.10E-08 2.10E-08 Cesium-137 8.10E-14 1.70E-11 Xenon-131m 9.10E-07 9.10E-07 Cesium-138 5.20E-10 7.30E-10 Xenon-133 6.30E-08 6.30E-08 Chromium-51 6.90E-13 1.40E-10 Xenon-133m 1.90E-07 1.90E-07 Cobalt-58 8.50E-14 1.70E-11 Xenon-135 2.00E-08 2.00E-08 Cobalt-60 1.00E-13 1.90E-11 Xenon-135m 8.90E-08 8.90E-08 Iron-59 1.70E-13 3.20E-11 Xenon-138 2.00E-07 2.00E-07 Lanthanum-140 2.80E-13 2.10E-11 Iodine-131 8.00E-14 7.00E-12 Manganese-54 8.30E-14 1.70E-11 Iodine-132 6.60E-12 1.90E-11 Molybdenum-99 2.40E-13 2.80E-11 Iodine-133 4.70E-13 1.10E-11 Niobium-95 8.70E-14 1.80E-11 Iodine-134 5.90E-11 8.20E-11 Rubidium-88 1.90E-08 1.90E-08 Iodine-135 7.00E-12 5.50E-11 Ruthenium-103 7.40E-14 1.50E-11 Strontium-89 2.15E-15 (1)

Strontium-90 5.60E-16 (1)

Tellurium-123m 6.60E-14 1.50E-11 Tritium 3.80E-07 3.80E-07 Zinc-65 1.90E-13 3.80E-11 Zirconium-95 1.80E-13 4.10E-11 Gross Alpha 3.60E-15 (1)

(1) Not required for batch releases.

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Table 4:

Unit 1 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year  % (1)

A. Fission & activation gases

1. Total release Ci 1.14E-01 4.67E-01 6.17E-02 5.42E-02 6.97E-01 3.54E+01
2. Average release rate for period Ci/sec 1.45E-02 5.94E-02 7.76E-03 6.82E-03 2.20E-02
3. Percent of ODCM Requirement limit  %

NA (2) NA (2) NA (2) NA (2) NA (2)

B. Iodine 131

1. Total Iodine 131 Ci < LLD 1.72E-05 < LLD < LLD 1.72E-05 3.32E+01
2. Average release rate for period Ci/sec < LLD 2.19E-06 < LLD < LLD 5.44E-07 19 3. Percent of ODCM Requirement limit  %

NA (2) NA (2) NA (2) NA (2) NA (2)

C. Particulates

1. Particulates with half- lives > 8 days Ci 1.33E-06 1.03E-02 1.52E-06 < LLD 1.03E-02 3.43E+01
2. Average release rate for period Ci/sec 1.69E-07 1.31E-03 1.91E-07 < LLD 3.25E-04
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)
4. Gross Alpha radioactivity Ci < LLD 1.46E-07 < LLD < LLD < LLD PVNGS ARERR 2016 D. Tritium
1. Total release Ci 4.95E+02 3.49E+02 1.08E+02 1.03E+02 1.06E+03 3.85E+01
2. Average release rate for period Ci/sec 6.30E+01 4.44E+01 1.36E+01 1.30E+01 3.35E+01
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 11 for percent of ODCM Requirement limits.

PVNGS 2016 ARERR Page 19

Table 5:

Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02
2. Iodines I-131 Ci < LLD 1.72E-05 < LLD < LLD 1.72E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD < LLD 2.90E-04 PVNGS 2016 ARERR Page 20

Table 6:

Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total 3.Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.59E-03 1.52E-06 < LLD 1.59E-03 Co-60 Ci 1.33E-06 5.21E-04 < LLD < LLD 5.22E-04 Cr-51 Ci < LLD 5.72E-03 < LLD < LLD 5.72E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 9.54E-05 < LLD < LLD 9.54E-05 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.31E-04 < LLD < LLD 1.31E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 1.98E-04 < LLD < LLD 1.98E-04 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.32E-04 < LLD < LLD 1.32E-04 Total Ci 1.33E-06 8.47E-03 1.52E-06 < LLD 8.47E-03 4.Tritium H-3 Ci 2.58E+01 3.73E+01 3.86E+01 2.27E+01 1.24E+02 PVNGS 2016 ARERR Page 21

Table 7:

Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 1.14E-01 2.38E-01 6.14E-02 5.42E-02 4.68E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 3.28E-04 1.61E-01 2.28E-04 < LLD 1.62E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 < LLD < LLD 3.33E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 1.14E-01 4.05E-01 6.16E-02 5.42E-02 6.35E-01
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 22

Table 8:

Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD < LLD 1.53E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD 4.01E-04 < LLD < LLD 4.01E-04 Co-60 Ci < LLD 1.52E-04 < LLD < LLD 1.52E-04 Cr-51 Ci < LLD 1.15E-03 < LLD < LLD 1.15E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 8.86E-06 < LLD < LLD 8.86E-06 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 3.44E-05 < LLD < LLD 3.44E-05 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 5.04E-05 < LLD < LLD 5.04E-05 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 5.29E-06 < LLD < LLD 5.29E-06 Total Ci < LLD 1.82E-03 < LLD < LLD 1.82E-03 4.Tritium H-3 Ci 4.69E+02 3.11E+02 6.96E+01 8.06E+01 9.30E+02 Note 1 - Not required for batch releases PVNGS 2016 ARERR Page 23

Table 9:

Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 1.14E-01 2.38E-01 6.14E-02 5.42E-02 4.68E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 3.28E-04 2.23E-01 2.28E-04 < LLD 2.23E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 < LLD < LLD 3.33E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 1.14E-01 4.66E-01 6.16E-02 5.42E-02 6.97E-01
2. Iodines I-131 Ci < LLD 1.72E-05 < LLD < LLD 1.72E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD < LLD 2.90E-04 PVNGS 2016 ARERR Page 24

Table 10:

Unit 1 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD < LLD 1.53E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.99E-03 1.52E-06 1.52E-06 1.99E-03 Co-60 Ci 1.33E-06 6.73E-04 < LLD < LLD 6.74E-04 Cr-51 Ci < LLD 6.87E-03 < LLD < LLD 6.87E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 1.04E-04 < LLD < LLD 1.04E-04 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.65E-04 < LLD < LLD 1.65E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 2.48E-04 < LLD < LLD 2.48E-04 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.37E-04 < LLD < LLD 1.37E-04 Total Ci 1.33E-06 1.03E-02 1.52E-06 1.52E-06 1.03E-02 Total > 8 days Ci 1.33E-06 1.03E-02 1.52E-06 < LLD 1.03E-02 4.Tritium H-3 Ci 4.95E+02 3.48E+02 1.08E+02 1.03E+02 1.05E+03 PVNGS 2016 ARERR Page 25

Table 11:

Unit 1 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Air Dose mrad 2.99E-04 6.50E-04 1.61E-04 1.42E-04 1.25E-03 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit  % 5.98E-03 1.30E-02 3.22E-03 2.84E-03 1.25E-02 Beta Air Dose mrad 1.06E-04 2.90E-04 5.70E-05 5.02E-05 5.03E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit  % 1.06E-03 2.90E-03 5.70E-04 5.02E-04 2.52E-03 Maximum Organ Dose mrem 1.78E-01 1.29E-01 3.88E-02 3.71E-02 3.83E-01 (excluding skin)

Age Teen Teen Teen Teen Teen Organ Thyroid Lung Thyroid Thyroid Lung ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit  % 2.37E+00 1.72E+00 5.17E-01 4.95E-01 2.55E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.

PVNGS 2016 ARERR Page 26

Table 12:

Unit 2 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year  % (1)

A. Fission & activation gases

1. Total release Ci 8.56E-02 7.08E-02 9.60E-02 8.95E-02 3.42E-01 3.54E+01
2. Average release rate for period Ci/sec 1.09E-02 9.00E-03 1.21E-02 1.13E-02 1.08E-02
3. Percent of ODCM Requirement limit  %

NA (2) NA (2) NA (2) NA (2) NA (2)

B. Iodine 131

1. Total Iodine 131 Ci < LLD < LLD < LLD < LLD < LLD 3.32E+01
2. Average release rate for period Ci/sec < LLD < LLD < LLD < LLD < LLD
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

C. Particulates

1. Particulates with half- lives > 8 days Ci

< LLD < LLD < LLD < LLD < LLD 3.43E+01

2. Average release rate for period Ci/sec < LLD < LLD < LLD < LLD < LLD
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)
4. Gross Alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium
1. Total release Ci 4.52E+01 2.93E+01 8.12E+01 9.55E+01 2.51E+02 3.85E+01
2. Average release rate for period Ci/sec 5.75E+00 3.73E+00 1.02E+01 1.20E+01 7.94E+00
3. Percent of ODCM Requirement limit  %

NA (2) NA (2) NA (2) NA (2) NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 19 for percent of ODCM Requirement limits.

PVNGS 2016 ARERR Page 27

Table 13:

Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD < LLD < LLD Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 28

Table 14:

Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD
4. Tritium H-3 Ci 3.01E+01 2.93E+01 2.11E+01 1.85E+01 9.90E+01 PVNGS 2016 ARERR Page 29

Table 15:

Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 7.12E-02 4.88E-02 7.50E-02 7.21E-02 2.67E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci 1.43E-02 1.02E-02 2.09E-02 1.74E-02 6.28E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD 1.33E-04 5.78E-05 1.91E-04 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 8.55E-02 5.90E-02 9.60E-02 8.96E-02 3.30E-01
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 30

Table 16:

Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD
4. Tritium H-3 Ci 1.50E+01 1.89E-02 6.00E+01 7.69E+01 1.52E+02 Note 1 - Not required for batch releases PVNGS 2016 ARERR Page 31

Table 17:

Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 7.12E-02 4.88E-02 7.50E-02 7.21E-02 2.67E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci 1.43E-02 1.02E-02 2.09E-02 1.74E-02 6.28E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD 1.33E-04 5.78E-05 1.91E-04 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 8.55E-02 5.90E-02 9.60E-02 8.96E-02 3.30E-01
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 32

Table 18:

Unit 2 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD Total > 8 days Ci < LLD < LLD < LLD < LLD < LLD
4. Tritium H-3 Ci 4.51E+01 2.93E+01 8.11E+01 9.54E+01 2.51E+02 PVNGS 2016 ARERR Page 33

Table 19:

Unit 2 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Unit 2 Q1 Q2 Q3 Q4 year Gamma Air Dose mrad 1.89E-04 1.56E-04 1.99E-04 1.91E-04 7.34E-04 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit  % 3.78E-03 3.12E-03 3.98E-03 3.82E-03 7.34E-03 Beta Air Dose mrad 7.03E-05 5.80E-05 7.57E-05 7.20E-05 2.76E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit  % 7.03E-04 5.80E-04 7.57E-04 7.20E-04 1.38E-03 Maximum Organ Dose mrem 1.62E-02 1.05E-02 2.91E-02 3.42E-02 9.01E-02 (excluding skin)

Age Teen Teen Teen Teen Teen Organ Thyroid Thyroid Thyroid Thyroid Thyroid ODCM Req. 4.2 Limit  % 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit  % 2.16E-01 1.40E-01 3.88E-01 4.56E-01 6.01E-01 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.

PVNGS 2016 ARERR Page 34

Table 20:

Unit 3 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year  % (1)

A. Fission & activation gases

1. Total release Ci 4.38E-02 4.81E-02 8.04E-02 1.03E-01 2.76E-01 3.54E+01
2. Average release rate for period Ci/sec 5.57E-03 6.12E-03 1.01E-02 1.30E-02 8.73E-03
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

B. Iodine 131

1. Total Iodine 131 Ci < LLD < LLD < LLD 2.35E-05 2.35E-05 3.32E+01
2. Average release rate for period Ci/sec < LLD < LLD < LLD 2.96E-06 7.43E-07
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

C. Particulates

1. Particulates with half- lives > 8 days Ci < LLD < LLD < LLD 1.40E-04 1.40E-04 3.43E+01
2. Average release rate for period Ci/sec < LLD < LLD < LLD 1.76E-05 4.41E-06
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)
4. Gross Alpha radioactivity Ci < LLD 1.68E-08 < LLD < LLD < LLD D. Tritium
1. Total release Ci 6.92E+01 2.73E+01 5.82E+02 3.71E+02 1.05E+03 3.85E+01
2. Average release rate for period Ci/sec 8.80E+00 3.47E+00 7.32E+01 4.67E+01 3.32E+01
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 27 for percent of ODCM Requirement limits.

PVNGS 2016 ARERR Page 35

Table 21:

Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD < LLD < LLD Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD
2. Iodines I-131 Ci < LLD < LLD < LLD 2.35E-05 2.35E-05 I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD 3.28E-05 3.28E-05 PVNGS 2016 ARERR Page 36

Table 22:

Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 2.19E-05 2.19E-05 Co-60 Ci < LLD < LLD < LLD 7.52E-06 7.52E-06 Cr-51 Ci < LLD < LLD < LLD 4.49E-06 4.49E-06 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD 3.53E-05 3.53E-05
4. Tritium H-3 Ci 2.92E+01 2.73E+01 2.43E+01 1.09E+02 1.90E+02 PVNGS 2016 ARERR Page 37

Table 23:

Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 4.38E-02 4.81E-02 8.04E-02 5.10E-02 2.23E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD 5.23E-02 5.23E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 4.38E-02 4.81E-02 8.04E-02 1.03E-01 2.76E-01
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 38

Table 24:

Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD 3.07E-06 3.07E-06 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 3.33E-05 3.33E-05 Co-60 Ci < LLD < LLD < LLD 2.27E-05 2.27E-05 Cr-51 Ci < LLD < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD 1.34E-07 1.34E-07 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD 2.72E-05 2.72E-05 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD 2.09E-05 2.09E-05 Total Ci < LLD < LLD < LLD 1.07E-04 1.07E-04
4. Tritium H-3 Ci 4.00E+01 2.48E-02 5.58E+02 2.62E+02 8.60E+02 Note 1 - Not required for batch releases PVNGS 2016 ARERR Page 39

Table 25:

Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 4.38E-02 4.81E-02 8.04E-02 5.10E-02 2.23E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD < LLD 5.23E-02 5.23E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 4.38E-02 4.81E-02 8.04E-02 1.03E-01 2.76E-01
2. Iodines I-131 Ci < LLD < LLD < LLD 2.35E-05 2.35E-05 I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD 3.28E-05 3.28E-05 PVNGS 2016 ARERR Page 40

Table 26:

Unit 3 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD 3.07E-06 3.07E-06 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 5.52E-05 5.52E-05 Co-60 Ci < LLD < LLD < LLD 3.02E-05 3.02E-05 Cr-51 Ci < LLD < LLD < LLD 4.49E-06 4.49E-06 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD 1.34E-07 1.34E-07 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD 2.72E-05 2.72E-05 Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD 2.09E-05 2.09E-05 Total Ci < LLD < LLD < LLD 1.43E-04 1.43E-04 Total > 8 days Ci < LLD < LLD < LLD 1.40E-04 1.40E-04
4. Tritium H-3 Ci 6.92E+01 2.73E+01 5.82E+02 3.71E+02 1.05E+03 PVNGS 2016 ARERR Page 41

Table 27:

Unit 3 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Air Dose mrad 1.15E-04 1.26E-04 2.11E-04 1.39E-04 5.92E-04 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit  % 2.30E-03 2.52E-03 4.22E-03 2.78E-03 5.92E-03 Beta Air Dose mrad 4.06E-05 4.46E-05 7.45E-05 6.28E-05 2.22E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit  % 4.06E-04 4.46E-04 7.45E-04 6.28E-04 1.11E-03 Maximum Organ Dose mrem 2.48E-02 9.80E-03 2.09E-01 1.33E-01 3.77E-01 (excluding skin)

Age Teen Teen Teen Teen Teen Organ Thyroid Thyroid Thyroid Thyroid Thyroid ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit  % 3.31E-01 1.31E-01 2.79E+00 1.77E+00 2.51E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.

PVNGS 2016 ARERR Page 42

Table 28:

Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD < LLD Xe-133 Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 6.18E-02 < LLD < LLD 6.18E-02
2. Iodines I-131 Ci < LLD 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD 3.28E-05 3.23E-04 PVNGS 2016 ARERR Page 43

Table 29:

Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.59E-03 1.52E-06 2.19E-05 1.61E-03 Co-60 Ci 1.33E-06 5.21E-04 < LLD 7.52E-06 5.30E-04 Cr-51 Ci < LLD 5.72E-03 < LLD 4.49E-06 5.72E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 9.54E-05 < LLD < LLD 9.54E-05 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.31E-04 < LLD < LLD 1.31E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 1.98E-04 < LLD < LLD 1.98E-04 Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.32E-04 < LLD < LLD 1.32E-04 Total Ci 1.33E-06 8.47E-03 1.52E-06 3.53E-05 8.51E-03
4. Tritium H-3 Ci 8.51E+01 9.39E+01 8.40E+01 1.50E+02 4.13E+02 PVNGS 2016 ARERR Page 44

Table 30:

Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 2.29E-01 3.35E-01 2.17E-01 1.77E-01 9.58E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 1.46E-02 1.71E-01 2.11E-02 6.97E-02 2.77E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 1.33E-04 5.78E-05 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 2.44E-01 5.12E-01 2.38E-01 2.47E-01 1.24E+00
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 45

Table 31:

Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD 3.07E-06 1.84E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD 4.01E-04 < LLD 3.33E-05 4.34E-04 Co-60 Ci < LLD 1.52E-04 < LLD 2.27E-05 1.75E-04 Cr-51 Ci < LLD 1.15E-03 < LLD < LLD 1.15E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 8.86E-06 < LLD < LLD 8.86E-06 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 3.44E-05 < LLD 1.34E-07 3.45E-05 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 5.04E-05 < LLD 2.72E-05 7.76E-05 Os-191 Ci < LLD < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 5.29E-06 < LLD 2.09E-05 2.62E-05 Total Ci < LLD 1.82E-03 < LLD 1.07E-04 1.92E-03
4. Tritium H-3 Ci 5.24E+02 3.11E+02 6.88E+02 4.20E+02 1.94E+03 Note 1 - Not required for batch releases PVNGS 2016 ARERR Page 46

Table 32:

Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 2.29E-01 3.35E-01 2.17E-01 1.77E-01 9.58E-01 Kr-83m Ci < LLD < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD < LLD Xe-131m Ci < LLD 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 1.46E-02 2.33E-01 2.11E-02 6.97E-02 3.38E-01 Xe-133m Ci < LLD 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci < LLD 3.33E-03 1.33E-04 5.78E-05 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD < LLD Total Ci 2.44E-01 5.73E-01 2.38E-01 2.47E-01 1.30E+00
2. Iodines I-131 Ci < LLD 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci < LLD 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD < LLD Total Ci < LLD 2.90E-04 < LLD 3.28E-05 3.23E-04 PVNGS 2016 ARERR Page 47

Table 33:

Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD < LLD Br-82 Ci < LLD 1.53E-05 < LLD 3.07E-06 1.84E-05 Ce-141 Ci < LLD < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD < LLD Co-57 Ci < LLD 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci < LLD 1.99E-03 < LLD 5.52E-05 2.05E-03 Co-60 Ci 1.33E-06 6.73E-04 < LLD 3.02E-05 7.05E-04 Cr-51 Ci < LLD 6.87E-03 < LLD 4.49E-06 6.87E-03 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD < LLD Fe-59 Ci < LLD 1.04E-04 < LLD < LLD 1.04E-04 La-140 Ci < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD 1.65E-04 < LLD 1.34E-07 1.66E-04 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD 2.48E-04 < LLD 2.72E-05 2.76E-04 Os-191 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD < LLD Sb-124 Ci < LLD 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD 1.37E-04 < LLD 2.09E-05 1.58E-04 Total Ci 1.33E-06 1.03E-02 < LLD 1.43E-04 1.04E-02 Total > 8 days Ci 1.33E-06 1.03E-02 < LLD 1.40E-04 1.04E-02
4. Tritium H-3 Ci 6.09E+02 4.05E+02 7.72E+02 5.70E+02 2.36E+03 PVNGS 2016 ARERR Page 48

Table 34:

Units 1, 2 and 3 Gaseous Effluents- Continuous - Fission Gases and Iodine -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

1. Fission gases Ar-41 Ci < LLD < LLD < LLD < LLD Kr-83m Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD Xe-133 Ci 6.18E-02 < LLD < LLD 6.18E-02 Xe-133m Ci < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD Total Ci 6.18E-02 < LLD < LLD 6.18E-02
2. Iodines I-131 Ci 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci 2.90E-04 < LLD 3.28E-05 3.23E-04 PVNGS 2016 ARERR Page 49

Table 35:

Units 1, 2 and 3 Gaseous Effluents- Continuous - Particulates -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD Br-82 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Co-57 Ci 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci 1.59E-03 < LLD 2.19E-05 1.62E-03 Co-60 Ci 5.22E-04 < LLD 7.52E-06 5.29E-04 Cr-51 Ci 5.72E-03 < LLD 4.49E-06 5.72E-03 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD Fe-59 Ci 9.54E-05 < LLD < LLD 9.54E-05 La-140 Ci < LLD < LLD < LLD < LLD Mn-54 Ci 1.31E-04 < LLD < LLD 1.31E-04 Mo-99 Ci < LLD < LLD < LLD < LLD Nb-95 Ci 1.98E-04 < LLD < LLD 1.98E-04 Os-191 Ci < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD Sb-124 Ci 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Zr-95 Ci 1.32E-04 < LLD < LLD 1.32E-04 Total Ci 8.47E-03 < LLD 3.53E-05 8.51E-03
4. Tritium H-3 Ci 1.24E+02 9.91E+01 1.89E+02 4.13E+02 PVNGS 2016 ARERR Page 50

Table 36:

Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

1. Fission gases Ar-41 Ci 5.43E+00 2.77E-01 2.35E-01 5.94E+00 Kr-83m Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD Xe-131m Ci 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 1.62E-01 6.47E-02 5.23E-02 2.79E-01 Xe-133m Ci 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci 3.33E-03 1.90E-04 < LLD 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD Xe-138 < LLD < LLD < LLD < LLD Total Ci 5.60E+00 3.42E-01 2.87E-01 6.23E+00
2. Iodines I-131 Ci < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < LLD < LLD I-134 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD PVNGS 2016 ARERR Page 51

Table 37:

Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1,2 and 3

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD Br-82 Ci 1.44E-03 < LLD 4.20E-06 1.44E-03 Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Co-57 Ci < LLD < LLD < LLD < LLD Co-58 Ci 4.01E-04 < LLD 3.33E-05 4.34E-04 Co-60 Ci 1.52E-04 < LLD 2.27E-05 1.75E-04 Cr-51 Ci 1.15E-03 < LLD < LLD 1.15E-03 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD Fe-59 Ci 8.86E-06 < LLD < LLD 8.86E-06 La-140 Ci < LLD < LLD < LLD < LLD Mn-54 Ci 3.44E-05 < LLD 1.34E-07 3.46E-05 Mo-99 Ci < LLD < LLD < LLD < LLD Nb-95 Ci 5.04E-05 < LLD 2.72E-05 7.76E-05 Os-191 Ci < LLD < LLD < LLD < LLD Rb-88 Ci < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Tc-99m Ci < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Zr-95 Ci 5.29E-06 < LLD 2.09E-05 2.62E-05 Total Ci 3.24E-03 < LLD 1.08E-04 3.34E-03
4. Tritium H-3 Ci 9.31E+02 1.52E+02 9.44E+02 2.03E+03 Note 1 - Not required for batch releases PVNGS 2016 ARERR Page 52

Table 38:

Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

1. Fission gases Ar-41 Ci 5.43E+00 2.77E-01 2.35E-01 5.94E+00 Kr-83m Ci < LLD < LLD < LLD < LLD Kr-85 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Kr-87 Ci < LLD < LLD < LLD < LLD Kr-88 Ci < LLD < LLD < LLD < LLD Kr-89 Ci < LLD < LLD < LLD < LLD Kr-90 Ci < LLD < LLD < LLD < LLD Xe-131m Ci 1.24E-03 < LLD < LLD 1.24E-03 Xe-133 Ci 2.24E-01 6.47E-02 5.23E-02 3.41E-01 Xe-133m Ci 1.02E-03 < LLD < LLD 1.02E-03 Xe-135 Ci 3.33E-03 1.90E-04 < LLD 3.52E-03 Xe-135m Ci < LLD < LLD < LLD < LLD Xe-137 Ci < LLD < LLD < LLD < LLD Xe-138 Ci < LLD < LLD < LLD < LLD Total Ci 5.66E+00 3.42E-01 2.87E-01 6.29E+00
2. Iodines I-131 Ci 1.72E-05 < LLD 2.35E-05 4.07E-05 I-132 Ci 2.73E-04 < LLD < LLD 2.73E-04 I-133 Ci < LLD < LLD 9.27E-06 9.27E-06 I-134 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci 2.90E-04 < LLD 3.28E-05 3.23E-04 PVNGS 2016 ARERR Page 53

Table 39:

Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

3. Particulates Ag-110m Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD Br-82 Ci 1.44E-03 < LLD 4.20E-06 1.44E-03 Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Co-57 Ci 4.88E-06 < LLD < LLD 4.88E-06 Co-58 Ci 1.99E-03 < LLD 5.52E-05 2.05E-03 Co-60 Ci 6.74E-04 < LLD 3.02E-05 7.04E-04 Cr-51 Ci 6.86E-03 < LLD 4.49E-06 6.87E-03 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-136 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Cs-138 Ci < LLD < LLD < LLD < LLD Fe-59 Ci 1.04E-04 < LLD < LLD 1.04E-04 La-140 Ci < LLD < LLD < LLD < LLD Mn-54 Ci 1.65E-04 < LLD 1.34E-07 1.65E-04 Mo-99 Ci < LLD < LLD < LLD < LLD Nb-95 Ci 2.48E-04 < LLD 2.72E-05 2.75E-04 Os-191 Ci < LLD < LLD 1.38E-06 1.38E-06 Rb-88 Ci < LLD < LLD < LLD < LLD Ru-103 Ci < LLD < LLD < LLD < LLD Ru-106 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD < LLD < LLD Sb-124 Ci 7.86E-05 < LLD < LLD 7.86E-05 Sb-125 Ci < LLD < LLD < LLD < LLD Se-75 Ci < LLD < LLD < LLD < LLD Sn-113m Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD < LLD Te-123m Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Zr-95 Ci 1.37E-04 < LLD 2.09E-05 1.58E-04 Total Ci 1.17E-02 < LLD 1.44E-04 1.19E-02 Total > 8 days Ci 1.33E-06 1.03E-02 1.52E-06 1.03E-02
4. Tritium H-3 Ci 1.06E+03 2.51E+02 1.13E+03 2.44E+03 PVNGS 2016 ARERR Page 54

Table 40:

Estimation of Total Percent Error The estimated total error is calculated as follows:

Total Percent Error = (E 12 + E22 + E32 + ... + En2 )1/2 Where En = Percent error associated with each contributing parameter.

Parameters contributing to errors in the measurement of gaseous effluents; process flow rates, sample collection, analytical counting and tank volumes.

The following values (%) were used for error calculations.

Fission & Act gases I-131 Particulates Tritium 25 25 25 25 Sample counting error 10 10 10 10 Counting system calibration error 5 5 5 5 Counting system source error 20 N/A N/A N/A Temperature/volume correction error 10 10 10 10 Process flow measuring device (1)

N/A 15 15 15 Sample flow measuring device N/A 5 N/A N/A Iodine collection efficiency error N/A N/A 10 N/A Plateout error N/A N/A N/A 20 Bubbler collection efficiency error N/A N/A N/A 2 Sample volume transfer error (pipette)

N/A N/A N/A 2 Sample volume error (graduate)

Note 1 - % of full scale PVNGS 2016 ARERR Page 55

Table 41:

Effluent Monitoring Instrumentation Out Of Service Greater Than 30 Days Date span of Cause of Unit Instrument Explanation inoperability inoperability 2 Unit 2 Fuel 2/11/2016 Condition Report 16- Condition Report 16-03957 Building through 02244 documents the determined that a ventilation Ventilation Flow 4/14/2016 flow transmitter failing inspection panel was found transmitter its acceptance criteria open, however, it took greater 2JHFBFT0093**I for FUNCTIONALITY than 30 days to find and fix the XMITR due to low flow problem.

indication.

PVNGS 2016 ARERR Page 56

Table 42:

Solid Waste Summary A. Solid Waste Shipped Offsite For Burial Or Disposal (not irradiated fuel) 1.0 Type of Waste Unit Jan-Dec 2016 estimated total error %

1.a. Spent resin, filters, sludges, m3 9.25E+01 2.50E+01 evaporator bottoms, etc. Ci 2.12E+02 2.50E+01 1.b. Dry compressible waste, m3 5.87E+02 2.50E+01 contaminated equipment, etc Ci 1.19E+01 2.50E+01 1.c. Irradiated components, control rods, m3 3.56E-01 2.50E+01 etc. Ci 6.05E+00 2.50E+01 m3 5.36E+00 2.50E+01 1.d. Other (Oil)

Ci 8.12E-07 2.50E+01 PVNGS 2016 ARERR Page 57

2.0 Estimate of major nuclide composition 2.a. Spent resin, filters, sludge, evaporator bottoms, etc.

Nuclide Percent Estimated Total Curies Name Abundance Error %

Ni-63 5.24E+01 1.11E+02 2.50E+01 Fe-55 1.76E+01 3.72E+01 2.50E+01 Co-60 1.28E+01 2.71E+01 2.50E+01 Co-58 6.82E+00 1.44E+01 2.50E+01 Cs-137 3.11E+00 6.58E+00 2.50E+01 C-14 2.19E+00 4.64E+00 2.50E+01 Mn-54 1.44E+00 3.06E+00 2.50E+01 Sb-125 1.40E+00 2.96E+00 2.50E+01 H-3 1.33E+00 2.81E+00 2.50E+01 Co-57 6.21E-01 1.31E+00 2.50E+01 Ni-59 6.74E-02 1.43E-01 2.50E+01 Sr-90 5.56E-02 1.18E-01 2.50E+01 Tc-99 5.25E-02 1.11E-01 2.50E+01 Ce-144 4.87E-02 1.03E-01 2.50E+01 Pu-241 1.74E-02 3.68E-02 2.50E+01 Ag-110m 1.68E-02 3.57E-02 2.50E+01 Cs-134 1.44E-02 3.05E-02 2.50E+01 Zr-95 1.32E-02 2.79E-02 2.50E+01 I-129 1.21E-02 2.57E-02 2.50E+01 Cr-51 8.18E-03 1.73E-02 2.50E+01 Zn-65 7.61E-03 1.61E-02 2.50E+01 Nb-95 7.21E-03 1.53E-02 2.50E+01 Sn-113 3.06E-03 6.48E-03 2.50E+01 Sb-124 2.82E-03 5.96E-03 2.50E+01 Am-241 1.22E-03 2.58E-03 2.50E+01 Pu-238 7.64E-04 1.62E-03 2.50E+01 Cm-243 6.56E-04 1.39E-03 2.50E+01 Pu-239 4.91E-04 1.04E-03 2.50E+01 Fe-59 4.33E-04 9.17E-04 2.50E+01 Sr-89 2.41E-04 5.11E-04 2.50E+01 Am-243 5.62E-05 1.19E-04 2.50E+01 Cm-242 2.11E-05 4.47E-05 2.50E+01 Te-123m 7.65E-06 1.62E-05 2.50E+01 Pu-242 6.89E-06 1.46E-05 2.50E+01 Be-7 4.16E-11 8.81E-11 2.50E+01 Hf-181 8.41E-18 1.78E-17 2.50E+01 Ru-103 2.99E-27 6.32E-27 2.50E+01 Ce-141 5.48E-30 1.16E-29 2.50E+01 Total 2.12E+02 PVNGS 2016 ARERR Page 58

2.b. Dry compressible waste, contaminated equip, etc.

Estimated Nuclide Percent Abundance Curies Total Error Name Cr-51 4.87E+01 5.82E+00 2.50E+01 Co-58 1.41E+01 1.69E+00 2.50E+01 Nb-95 1.25E+01 1.50E+00 2.50E+01 Zr-95 1.07E+01 1.27E+00 2.50E+01 Co-60 7.57E+00 9.05E-01 2.50E+01 Fe-55 2.04E+00 2.44E-01 2.50E+01 Mn-54 1.52E+00 1.82E-01 2.50E+01 Fe-59 7.88E-01 9.42E-02 2.50E+01 Ni-63 4.70E-01 5.62E-02 2.50E+01 H-3 2.90E-01 3.47E-02 2.50E+01 Sn-113 2.25E-01 2.69E-02 2.50E+01 Sb-125 1.84E-01 2.20E-02 2.50E+01 Zn-65 1.67E-01 1.99E-02 2.50E+01 Ce-144 1.56E-01 1.86E-02 2.50E+01 C-14 1.45E-01 1.73E-02 2.50E+01 Hf-181 9.76E-02 1.17E-02 2.50E+01 Te-6.54E-02 7.82E-03 2.50E+01 123m Sb-124 6.05E-02 7.23E-03 2.50E+01 Co-57 5.36E-02 6.40E-03 2.50E+01 Cs-137 3.84E-02 4.59E-03 2.50E+01 Tc-99 3.53E-02 4.22E-03 2.50E+01 Sr-90 8.52E-03 1.02E-03 2.50E+01 I-129 7.06E-03 8.44E-04 2.50E+01 Cm-242 2.16E-04 2.58E-05 2.50E+01 Pu-239 8.84E-05 1.06E-05 2.50E+01 Am-241 7.03E-05 8.40E-06 2.50E+01 Sc-46 6.53E-05 7.80E-06 2.50E+01 Cm-243 5.98E-05 7.14E-06 2.50E+01 Sr-89 1.58E-05 1.89E-06 2.50E+01 Pu-241 1.73E-06 2.07E-07 2.50E+01 Pu-238 1.82E-08 2.18E-09 2.50E+01 1.00E+02 1.19E+01 PVNGS 2016 ARERR Page 59

2.c. Irradiated components, control rods, etc.

Estimated Nuclide Percent Curies Total Error Name Abundance Co-60 7.14E+01 4.32E+00 2.50E+01 Fe-55 1.75E+01 1.06E+00 2.50E+01 Ni-63 9.50E+00 5.75E-01 2.50E+01 Cr-51 4.69E-01 2.84E-02 2.50E+01 Co-58 4.26E-01 2.58E-02 2.50E+01 Zr-95 3.01E-01 1.82E-02 2.50E+01 Nb-95 1.80E-01 1.09E-02 2.50E+01 Mn-54 8.28E-02 5.01E-03 2.50E+01 Ni-59 6.21E-02 3.76E-03 2.50E+01 H-3 2.15E-02 1.30E-03 2.50E+01 C-14 2.08E-02 1.26E-03 2.50E+01 Fe-59 1.56E-02 9.44E-04 2.50E+01 Sb-125 1.07E-02 6.47E-04 2.50E+01 Sn-113 8.99E-03 5.44E-04 2.50E+01 Zn-65 8.42E-03 5.10E-04 2.50E+01 Ce-144 7.14E-03 4.32E-04 2.50E+01 Co-57 2.73E-03 1.65E-04 2.50E+01 Te-123m 2.66E-03 1.61E-04 2.50E+01 Cs-137 2.21E-03 1.34E-04 2.50E+01 Hf-181 1.82E-03 1.10E-04 2.50E+01 Sb-124 1.62E-03 9.80E-05 2.50E+01 Nb-94 1.05E-03 6.35E-05 2.50E+01 Sr-90 5.24E-04 3.17E-05 2.50E+01 I-129 9.71E-05 5.88E-06 2.50E+01 Tc-99 6.31E-05 3.82E-06 2.50E+01 Cm-242 9.90E-06 5.99E-07 2.50E+01 Pu-239 5.48E-06 3.32E-07 2.50E+01 Am-241 4.34E-06 2.63E-07 2.50E+01 Cm-243 3.68E-06 2.23E-07 2.50E+01 Ta-182 2.73E-11 1.65E-12 2.50E+01 Total 6.05E+00 PVNGS 2016 ARERR Page 60

2.d. Other (Soil/Oil)

Estimated Nuclide Percent Curies Total Name Abundance Error %

H-3 6.70E+01 7.93E-04 2.50E+01 Tc-99 2.43E+01 2.88E-04 2.50E+01 C-14 8.53E+00 1.01E-04 2.50E+01 I-129 1.01E-01 1.19E-06 2.50E+01 Cs-137 2.95E-02 3.49E-07 2.50E+01 Sb-125 2.95E-02 3.49E-07 2.50E+01 Co-60 9.63E-03 1.14E-07 2.50E+01 Total 1.18E-03 PVNGS 2016 ARERR Page 61

3.b Irradiated Fuel Shipments: None 3.c Supplemental Information:

Number of Mode Of Destination Shipments Transport 11 Highway EnergySolutions, UT (BWF)

EnergySolutions, UT (Treatment 20 Highway Facility) 3 Highway EnergySolutions, UT (CWF) 8 Highway Waste Control Specialist, TX (CWDF) 1 Highway EnergySolutions, TN BWF = Bulk Waste Facility CWF = Containerized Waste Facility CWDF = Containerized Waste Dispoal Facility TSD = Treatment, Storage, Disposal

1) Container Volume in M3 by Waste Class Waste Class A Waste Class B Waste Class C
a. material 8.10E+01 1.03E+01 1.20E+00
b. material 5.87E+02 0 0
c. material 3.56E-01 0 0
d. material 5.36E+00 0 0
2) Container Activity in Ci by Waste Class (calculated)

Waste Class A Waste Class B Waste Class C

a. material 5.13E+00 1.63E+02 4.39E+01
b. material 1.19E+01 0 0
c. material 6.05E+00 0 0
d. material 8.12E-07 0 0
3) Principal Radionuclides
a. material See section 2.0 of the report
b. material See section 2.0 of the report
c. material See section 2.0 of the report
d. material See section 2.0 of the report
4) Source of waste and processing employed spent resin-dewatered/dried, mechanical filters-no processing,
a. material concentrates-dried,concentrates as a liquid-no processing employed
b. material non-compacted dry active waste - no processing employed
c. material Activated material - no processing empoyed
d. material Oil - no processing empoyed PVNGS 2016 ARERR Page 62
5) Type of Container (1) Metal Tank or Liner transported as LSA-I, (10) Type A transportation casks transported as LSA-I, (12) Type A transportation casks transported as LSA-II, (4)Type A tranportation casks transported
a. material as Type A (20) 20' sea land containers transported as LSA-I, (3) Type A
b. material tranportation casks transported as Type A
c. material (1) Type A transportation casks transported as LSA-I
d. material (1) Type A tranportation casks transported as Exempt Quantity
6) Solidification agent or absorbent
a. material No solidification agents or absorbents used to process material
b. material No solidification agents or absorbents used to process material
c. material No solidification agents or absorbents used to process material
d. material No solidification agents or absorbents used to process material PVNGS 2016 ARERR Page 63

APPENDIX B METEOROLOGY PVNGS 2016 ARERR Page 61

JOINT FREQUENCY DISTRIBUTION TABLES The tables presented in this section are results obtained from processing the hourly meteorological data collected at the Palo Verde Nuclear Generating Station for the period of January -

December 2016. The joint frequency distribution (JFD) tables represent the frequency, in terms of the number of observations, that a particular wind speed, wind direction, and stability category occurred simultaneously. On a quarterly, semiannual and annual basis, the JFDs were produced for 35-foot wind speed and wind direction by atmospheric stability class corresponding to the seven Pasquill stability categories, and for wind speed and wind direction for all stability classes combined. Atmospheric stability was classified per Regulatory Guide 1.23, using the 200-foot to 35-foot temperature difference (delta T).

In accordance with NUREG-0133, the batch releases for the year were considered as long term, since the batch releases are sufficiently random in both time of day and duration. Consequently, the JFDs for the batch releases for all quarters are the same as for the continuous releases.

Discussion A summary of 2016 Joint Frequency Distribution (JFD) shows a somewhat typical, but variable year. Of the 8784 hours0.102 days <br />2.44 hours <br />0.0145 weeks <br />0.00334 months <br /> available, 223 hours0.00258 days <br />0.0619 hours <br />3.687169e-4 weeks <br />8.48515e-5 months <br /> of data were lost due to data being overwritten for an effective 97.6% data recovery.

The average 35 foot mean wind speed was 6.7 mph. Distribution of directions was spread over the compass with a predominant direction (3 sectors of 22.5 degrees each) centered on southwest (29.9%). A secondary maximum of three sectors centered on the north contained 2 6 .9% of the total. Southwesterly flow winds averaged higher speeds with the most frequent speed at 10 mph. With the northerly directions, the highest frequency occurred at 4.0 mph.

Stability class summary:

Stability class E, F, G, (stable categories) 59.1%.

Stability class G, (extremely stable) 25.2%.

Stability class A, B, C, (unstable categories) 21.8%.

Stability class D, (neutral category) 19.1%.

Overall stable conditions (E,F,G) existed for the year.

PVNGS 2016 ARERR Page 62

ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 3/31/2016

      • 1ST QRTR ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.51- 5.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.51- 6.50 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 6.51- 8.50 0 0 0 0 0 2 0 2 2 0 1 3 1 0 0 0 11 8.51-11.50 1 0 0 0 0 1 0 0 0 1 4 1 5 4 3 1 21 11.51-14.50 0 0 0 0 0 0 0 0 0 1 6 5 1 0 2 1 16 14.51-20.50 0 0 0 0 0 0 0 0 0 4 0 2 0 3 0 3 12

>20.50 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 TOTAL 1 0 0 0 0 3 0 2 2 8 11 11 7 7 5 5 62 STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 4.51- 5.50 0 1 0 1 0 0 0 1 0 1 0 0 0 1 1 0 6 5.51- 6.50 0 1 0 0 0 0 0 1 4 1 3 2 1 0 0 0 13 6.51- 8.50 0 1 3 3 1 1 0 2 1 3 6 4 2 1 0 0 28 8.51-11.50 0 1 0 1 0 1 0 0 0 2 3 4 1 1 0 2 16 11.51-14.50 0 0 0 0 0 0 0 0 0 2 5 1 0 0 0 0 8 14.51-20.50 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 2

>20.50 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 TOTAL 0 4 3 5 1 2 0 4 6 11 18 11 4 3 1 2 75 STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 1 3.51- 4.50 0 0 0 0 0 0 0 0 1 2 1 2 2 0 0 1 9 4.51- 5.50 1 0 1 3 3 0 1 2 6 4 2 0 1 0 0 3 27 5.51- 6.50 2 2 4 1 1 1 0 2 5 8 5 2 0 1 0 2 36 6.51- 8.50 0 3 4 2 4 2 2 0 4 3 3 2 0 1 0 1 31 8.51-11.50 0 0 4 1 1 1 0 0 2 1 0 0 0 0 0 0 10 11.51-14.50 0 0 0 0 0 0 0 0 0 1 3 0 1 0 0 0 5 14.51-20.50 0 0 0 0 0 0 0 0 0 1 2 0 0 1 0 0 4

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4 5 13 7 9 4 3 4 18 20 16 7 4 3 0 7 124 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 3/31/2016

      • 1ST QRTR ***

PVNGS 2016 ARERR Page 63

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1.51- 2.50 1 1 2 0 0 0 2 3 2 5 5 2 2 0 1 2 28 2.51- 3.50 12 4 1 3 3 3 5 7 16 15 13 8 3 6 2 5 106 3.51- 4.50 5 5 7 5 0 1 2 3 13 18 11 4 5 1 6 3 89 4.51- 5.50 6 11 9 5 1 1 6 5 9 7 9 4 2 3 1 3 82 5.51- 6.50 2 3 8 3 0 1 0 2 3 9 5 5 0 1 2 1 45 6.51- 8.50 5 4 5 6 1 0 0 0 2 3 6 4 3 1 1 1 42 8.51-11.50 0 0 4 1 6 3 0 0 0 4 6 6 4 0 2 1 37 11.51-14.50 0 0 0 1 4 0 0 0 0 4 7 3 2 0 0 1 22 14.51-20.50 0 0 0 0 6 0 0 0 2 3 2 1 4 6 0 0 24

>20.50 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 0 3 TOTAL 31 28 37 24 21 9 15 20 47 71 64 37 25 18 15 17 479 STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 1 0 0 0 0 0 1 1 0 0 2 0 5 1.51- 2.50 5 4 0 0 1 0 0 2 0 2 1 5 0 2 2 1 25 2.51- 3.50 3 2 1 1 0 0 0 0 0 5 4 7 5 5 6 1 40 3.51- 4.50 3 1 0 1 0 0 0 0 2 5 6 6 3 2 5 4 38 4.51- 5.50 3 3 1 1 1 0 0 0 7 9 4 2 1 1 2 3 38 5.51- 6.50 2 2 2 0 0 0 0 0 1 2 4 0 0 3 2 2 20 6.51- 8.50 1 3 1 1 0 1 0 1 3 7 7 6 8 3 2 1 45 8.51-11.50 2 2 1 3 0 3 1 0 0 4 7 4 6 4 1 1 39 11.51-14.50 0 1 0 4 2 0 0 0 0 3 5 2 1 13 1 0 32 14.51-20.50 0 0 0 0 13 0 0 0 1 2 8 3 3 4 0 0 34

>20.50 0 0 0 0 1 0 0 0 3 0 2 2 0 0 0 0 8 TOTAL 19 18 6 11 19 4 1 3 17 39 49 38 27 37 23 13 324 STABILITY CLASS F SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 4 2 0 0 0 0 0 1 1 1 3 3 2 5 3 3 28 2.51- 3.50 4 1 1 3 2 0 0 1 0 2 5 2 5 4 13 7 50 3.51- 4.50 4 2 1 0 0 0 0 0 1 4 5 3 3 2 10 10 45 4.51- 5.50 4 0 1 0 0 0 1 0 1 5 2 4 3 1 5 4 31 5.51- 6.50 1 4 2 0 0 0 0 0 0 6 4 3 4 3 4 5 36 6.51- 8.50 2 3 1 2 1 0 0 2 0 6 10 10 2 5 5 7 56 8.51-11.50 0 1 0 0 0 0 0 0 0 11 4 1 1 9 4 4 35 11.51-14.50 0 0 0 0 0 0 0 0 0 1 0 0 1 0 0 2 4 14.51-20.50 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 19 13 6 5 4 0 1 4 3 36 33 26 21 29 44 42 286 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 3/31/2016

      • 1ST QRTR ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 1 0 0 0 0 0 0 0 0 0 0 0 1 1 0 3 1.51- 2.50 11 3 3 1 2 0 0 0 0 2 1 4 6 7 16 18 74 2.51- 3.50 49 11 8 5 2 3 1 2 2 5 3 1 8 19 34 48 201 3.51- 4.50 68 13 3 3 1 1 1 2 1 2 1 2 7 12 26 71 214 4.51- 5.50 66 14 2 2 0 1 0 0 1 1 3 3 2 5 17 38 155 5.51- 6.50 36 19 3 1 0 0 0 0 0 2 1 1 2 5 5 12 87 6.51- 8.50 42 10 1 0 0 0 0 0 1 2 1 1 1 0 1 12 72 8.51-11.50 13 10 1 0 0 0 0 0 0 2 0 0 0 0 0 2 28 11.51-14.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 285 81 21 12 5 5 2 4 5 16 10 12 26 49 100 201 834 PVNGS 2016 ARERR Page 64

STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 1 1 0 1 0 0 0 0 0 1 1 0 1 3 0 9 1.51- 2.50 22 10 5 1 3 0 2 6 3 10 10 14 10 14 22 24 156 2.51- 3.50 68 18 11 12 7 6 6 10 18 27 25 19 21 34 55 61 398 3.51- 4.50 80 21 11 9 1 2 3 5 19 31 24 17 20 17 47 89 396 4.51- 5.50 80 29 14 12 5 2 8 8 24 27 20 13 9 11 26 51 339 5.51- 6.50 43 31 19 5 1 2 0 5 13 29 22 13 7 13 13 22 238 6.51- 8.50 50 24 15 14 7 6 2 7 13 24 34 30 17 11 9 22 285 8.51-11.50 16 14 10 6 7 9 1 0 2 25 24 16 17 18 10 11 186 11.51-14.50 0 1 0 5 6 0 0 0 0 12 26 11 6 13 3 4 87 14.51-20.50 0 0 0 0 20 0 0 0 3 11 13 6 7 14 0 3 77

>20.50 0 0 0 0 1 0 0 0 3 5 2 2 0 0 0 0 13 TOTAL 359 149 86 64 59 27 22 41 98 201 201 142 114 146 188 287 2184 TOTAL NUMBER OF OBSERVATIONS: 2184 TOTAL NUMBER OF VALID OBSERVATIONS: 2184 TOTAL NUMBER OF MISSING OBSERVATIONS: 0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %

MEAN WIND SPEED FOR THIS PERIOD: 5.9 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 2.84 3.43 5.68 21.93 14.84 13.10 38.19 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 1 0 0 0 0 3 0 2 2 8 11 11 7 7 5 5 0 B 0 4 3 5 1 2 0 4 6 11 18 11 4 3 1 2 0 C 4 5 13 7 9 4 3 4 18 20 16 7 4 3 0 7 0 D 31 28 37 24 21 9 15 20 47 71 64 37 25 18 15 17 0 E 19 18 6 11 19 4 1 3 17 39 49 38 27 37 23 13 0 F 19 13 6 5 4 0 1 4 3 36 33 26 21 29 44 42 0 G 285 81 21 12 5 5 2 4 5 16 10 12 26 49 100 201 0 TOTAL 359 149 86 64 59 27 22 41 98 201 201 142 114 146 188 287 0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 4/01/2016 TO 6/30/2016

      • 2ND QRTR ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.51- 5.50 0 0 0 1 1 1 2 1 3 0 1 0 0 0 0 0 10 5.51- 6.50 0 1 0 0 2 0 1 6 13 7 4 0 0 0 0 0 34 6.51- 8.50 0 0 1 4 3 2 6 8 25 10 18 4 3 3 1 0 88 8.51-11.50 0 1 0 4 8 9 0 4 8 18 21 9 5 0 2 1 90 11.51-14.50 1 1 5 1 1 1 4 0 7 13 16 5 3 3 4 2 67 14.51-20.50 0 0 5 3 2 2 0 1 5 8 3 0 2 1 0 1 33

>20.50 0 0 1 0 0 0 0 0 0 1 6 1 0 1 1 0 11 TOTAL 1 3 12 13 17 15 13 20 61 57 69 19 13 8 8 4 333 STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 4.51- 5.50 0 0 1 2 1 1 1 4 12 0 2 1 1 0 0 1 27 5.51- 6.50 1 1 0 2 1 1 2 3 17 9 4 5 1 2 2 0 51 6.51- 8.50 0 1 2 2 2 5 1 3 9 10 8 4 4 1 0 0 52 8.51-11.50 0 0 2 3 3 2 3 2 2 10 9 2 2 0 0 0 40 11.51-14.50 0 1 0 0 1 3 0 1 0 4 4 0 0 2 0 0 16 14.51-20.50 0 0 2 0 1 0 0 0 0 3 3 1 0 0 0 0 10

>20.50 0 0 0 0 0 1 0 0 0 1 0 0 0 1 0 0 3 TOTAL 1 3 7 9 9 13 7 13 40 37 31 13 8 6 2 1 200 PVNGS 2016 ARERR Page 65

STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 3.51- 4.50 0 0 0 0 0 0 0 0 2 2 1 0 0 0 0 0 5 4.51- 5.50 1 0 2 2 1 1 2 4 11 7 0 1 0 1 1 0 34 5.51- 6.50 0 0 2 1 0 0 1 1 6 11 2 5 3 1 0 0 33 6.51- 8.50 0 1 4 5 3 1 1 1 4 6 2 3 3 1 1 0 36 8.51-11.50 0 0 2 1 2 3 1 2 1 4 2 2 3 0 0 0 23 11.51-14.50 1 0 1 0 3 0 1 0 0 2 4 0 0 0 0 0 12 14.51-20.50 0 0 0 0 0 0 0 0 0 1 3 0 0 0 0 0 4

>20.50 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTAL 2 1 11 9 9 5 6 8 24 33 15 11 9 4 2 0 149 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 4/01/2016 TO 6/30/2016

      • 2ND QRTR ***

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 1 0 0 0 0 0 1 0 0 1 0 0 0 0 0 0 3 1.51- 2.50 0 0 0 1 0 1 4 0 1 1 0 0 3 1 0 0 12 2.51- 3.50 2 1 3 1 3 1 5 4 4 5 6 1 2 2 0 4 44 3.51- 4.50 2 4 4 2 2 4 3 3 8 6 6 2 2 0 0 1 49 4.51- 5.50 0 4 2 0 2 2 3 3 3 10 7 2 3 1 0 0 42 5.51- 6.50 0 0 3 3 0 3 1 0 5 2 2 2 2 1 1 1 26 6.51- 8.50 0 1 4 6 2 0 1 1 4 3 5 4 2 1 0 0 34 8.51-11.50 0 3 2 2 2 5 2 3 2 7 5 4 7 2 0 0 46 11.51-14.50 0 0 1 2 1 0 0 1 2 5 6 1 2 3 0 1 25 14.51-20.50 1 2 1 1 0 2 2 0 2 5 11 2 0 0 2 0 31

>20.50 0 0 0 0 0 0 0 1 0 1 2 0 0 0 0 0 4 TOTAL 6 15 20 18 12 18 22 16 31 46 50 18 23 11 3 7 316 STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 1 0 0 0 0 0 0 0 0 0 0 0 0 2 1.51- 2.50 0 1 0 1 2 2 0 1 1 0 1 0 2 2 0 2 15 2.51- 3.50 4 3 0 1 2 1 2 0 0 0 0 1 3 1 7 2 27 3.51- 4.50 0 1 1 1 3 1 0 1 2 1 1 0 0 2 3 1 18 4.51- 5.50 1 1 1 0 0 0 1 0 1 4 4 1 0 1 2 0 17 5.51- 6.50 2 3 4 0 0 0 2 1 3 4 6 5 3 2 1 1 37 6.51- 8.50 3 3 13 3 2 1 3 2 4 9 21 5 6 2 0 3 80 8.51-11.50 4 4 5 3 0 1 2 2 4 12 33 13 8 2 1 7 101 11.51-14.50 4 0 3 0 2 2 3 1 5 14 17 1 0 4 9 4 69 14.51-20.50 1 0 0 0 5 0 0 2 0 6 12 1 2 2 5 3 39

>20.50 0 0 0 0 1 0 0 1 0 0 0 0 0 0 0 0 2 TOTAL 19 16 28 10 17 8 13 11 20 50 95 27 24 18 28 23 407 STABILITY CLASS F SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 1 0 1 0 0 0 0 0 0 0 0 0 0 3 1.51- 2.50 1 0 0 2 0 1 4 0 1 0 2 2 3 1 2 1 20 2.51- 3.50 5 6 1 4 2 3 3 1 1 1 3 2 5 5 4 6 52 3.51- 4.50 3 2 0 4 1 3 0 0 0 7 5 3 2 5 0 2 37 4.51- 5.50 1 5 5 1 1 1 3 0 0 4 10 9 3 4 1 4 52 5.51- 6.50 3 5 6 3 1 1 3 1 1 6 9 8 3 2 0 5 57 6.51- 8.50 4 5 6 2 0 2 1 0 2 14 20 4 4 2 4 1 71 8.51-11.50 3 0 2 2 0 1 0 0 1 7 16 6 3 3 5 5 54 11.51-14.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 14.51-20.50 0 0 0 1 0 0 0 0 0 0 1 0 0 0 0 0 2

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 20 23 21 20 5 13 14 2 6 39 66 34 23 22 16 24 348 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION PVNGS 2016 ARERR Page 66

JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 4/01/2016 TO 6/30/2016

      • 2ND QRTR ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0 2 1.51- 2.50 4 2 0 0 2 1 1 0 0 0 0 1 3 3 2 4 23 2.51- 3.50 21 1 1 3 3 7 4 2 0 0 3 1 0 9 7 8 70 3.51- 4.50 25 9 5 5 0 4 6 0 0 2 3 6 4 6 9 15 99 4.51- 5.50 29 10 2 2 1 4 7 0 0 0 3 1 1 1 4 10 75 5.51- 6.50 11 5 2 0 1 0 2 2 1 1 0 2 0 1 0 4 32 6.51- 8.50 4 2 2 2 1 0 1 1 0 1 0 1 1 0 0 4 20 8.51-11.50 3 1 0 1 0 0 0 0 0 0 0 0 0 0 1 0 6 11.51-14.50 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 97 30 12 13 8 17 22 5 1 4 9 12 9 20 24 45 328 STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 1 0 2 2 0 1 2 0 0 1 0 0 0 0 1 0 10 1.51- 2.50 5 3 0 4 4 5 9 1 3 1 3 3 11 7 4 7 70 2.51- 3.50 32 11 5 9 10 12 14 7 5 6 12 5 10 18 18 20 194 3.51- 4.50 30 16 10 12 6 12 9 4 12 18 17 11 8 13 12 19 209 4.51- 5.50 32 20 13 8 7 10 19 12 30 25 27 15 8 8 8 15 257 5.51- 6.50 17 15 17 9 5 5 12 14 46 40 27 27 12 9 4 11 270 6.51- 8.50 11 13 32 24 13 11 14 16 48 53 74 25 23 10 6 8 381 8.51-11.50 10 9 13 16 15 21 8 13 18 58 86 36 28 7 9 13 360 11.51-14.50 6 2 10 3 8 7 8 3 14 38 47 7 5 12 13 7 190 14.51-20.50 2 2 8 5 8 4 2 3 7 23 33 4 4 3 7 4 119

>20.50 0 0 1 0 1 1 0 2 0 3 9 1 0 2 1 0 21 TOTAL 146 91 111 92 77 89 97 75 183 266 335 134 109 89 83 104 2081 TOTAL NUMBER OF OBSERVATIONS: 2088 TOTAL NUMBER OF VALID OBSERVATIONS: 2081 TOTAL NUMBER OF MISSING OBSERVATIONS: 7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.7 %

MEAN WIND SPEED FOR THIS PERIOD: 7.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 16.00 9.61 7.16 15.19 19.56 16.72 15.76 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 1 3 12 13 17 15 13 20 61 57 69 19 13 8 8 4 0 B 1 3 7 9 9 13 7 13 40 37 31 13 8 6 2 1 0 C 2 1 11 9 9 5 6 8 24 33 15 11 9 4 2 0 0 D 6 15 20 18 12 18 22 16 31 46 50 18 23 11 3 7 0 E 19 16 28 10 17 8 13 11 20 50 95 27 24 18 28 23 0 F 20 23 21 20 5 13 14 2 6 39 66 34 23 22 16 24 0 G 97 30 12 13 8 17 22 5 1 4 9 12 9 20 24 45 0 TOTAL 146 91 111 92 77 89 97 75 183 266 335 134 109 89 83 104 0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 6/30/2016

      • 1ST SEMI ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.51- 5.50 0 0 0 1 1 1 2 1 3 0 1 0 0 0 0 0 10 5.51- 6.50 0 1 0 0 2 0 1 6 13 8 4 0 0 0 0 0 35 6.51- 8.50 0 0 1 4 3 4 6 10 27 10 19 7 4 3 1 0 99 8.51-11.50 1 1 0 4 8 10 0 4 8 19 25 10 10 4 5 2 111 11.51-14.50 1 1 5 1 1 1 4 0 7 14 22 10 4 3 6 3 83 14.51-20.50 0 0 5 3 2 2 0 1 5 12 3 2 2 4 0 4 45

>20.50 0 0 1 0 0 0 0 0 0 2 6 1 0 1 1 0 12 TOTAL 2 3 12 13 17 18 13 22 63 65 80 30 20 15 13 9 395 PVNGS 2016 ARERR Page 67

STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 0 2 4.51- 5.50 0 1 1 3 1 1 1 5 12 1 2 1 1 1 1 1 33 5.51- 6.50 1 2 0 2 1 1 2 4 21 10 7 7 2 2 2 0 64 6.51- 8.50 0 2 5 5 3 6 1 5 10 13 14 8 6 2 0 0 80 8.51-11.50 0 1 2 4 3 3 3 2 2 12 12 6 3 1 0 2 56 11.51-14.50 0 1 0 0 1 3 0 1 0 6 9 1 0 2 0 0 24 14.51-20.50 0 0 2 0 1 0 0 0 0 4 4 1 0 0 0 0 12

>20.50 0 0 0 0 0 1 0 0 0 2 0 0 0 1 0 0 4 TOTAL 1 7 10 14 10 15 7 17 46 48 49 24 12 9 3 3 275 STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 2 3.51- 4.50 0 0 0 0 0 0 0 0 3 4 2 2 2 0 0 1 14 4.51- 5.50 2 0 3 5 4 1 3 6 17 11 2 1 1 1 1 3 61 5.51- 6.50 2 2 6 2 1 1 1 3 11 19 7 7 3 2 0 2 69 6.51- 8.50 0 4 8 7 7 3 3 1 8 9 5 5 3 2 1 1 67 8.51-11.50 0 0 6 2 3 4 1 2 3 5 2 2 3 0 0 0 33 11.51-14.50 1 0 1 0 3 0 1 0 0 3 7 0 1 0 0 0 17 14.51-20.50 0 0 0 0 0 0 0 0 0 2 5 0 0 1 0 0 8

>20.50 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTAL 6 6 24 16 18 9 9 12 42 53 31 18 13 7 2 7 273 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 6/30/2016

      • 1ST SEMI ***

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 1 0 1 0 0 0 1 0 0 1 0 0 0 0 0 0 4 1.51- 2.50 1 1 2 1 0 1 6 3 3 6 5 2 5 1 1 2 40 2.51- 3.50 14 5 4 4 6 4 10 11 20 20 19 9 5 8 2 9 150 3.51- 4.50 7 9 11 7 2 5 5 6 21 24 17 6 7 1 6 4 138 4.51- 5.50 6 15 11 5 3 3 9 8 12 17 16 6 5 4 1 3 124 5.51- 6.50 2 3 11 6 0 4 1 2 8 11 7 7 2 2 3 2 71 6.51- 8.50 5 5 9 12 3 0 1 1 6 6 11 8 5 2 1 1 76 8.51-11.50 0 3 6 3 8 8 2 3 2 11 11 10 11 2 2 1 83 11.51-14.50 0 0 1 3 5 0 0 1 2 9 13 4 4 3 0 2 47 14.51-20.50 1 2 1 1 6 2 2 0 4 8 13 3 4 6 2 0 55

>20.50 0 0 0 0 0 0 0 1 0 4 2 0 0 0 0 0 7 TOTAL 37 43 57 42 33 27 37 36 78 117 114 55 48 29 18 24 795 STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 1 1 0 0 0 0 0 1 1 0 0 2 0 7 1.51- 2.50 5 5 0 1 3 2 0 3 1 2 2 5 2 4 2 3 40 2.51- 3.50 7 5 1 2 2 1 2 0 0 5 4 8 8 6 13 3 67 3.51- 4.50 3 2 1 2 3 1 0 1 4 6 7 6 3 4 8 5 56 4.51- 5.50 4 4 2 1 1 0 1 0 8 13 8 3 1 2 4 3 55 5.51- 6.50 4 5 6 0 0 0 2 1 4 6 10 5 3 5 3 3 57 6.51- 8.50 4 6 14 4 2 2 3 3 7 16 28 11 14 5 2 4 125 8.51-11.50 6 6 6 6 0 4 3 2 4 16 40 17 14 6 2 8 140 11.51-14.50 4 1 3 4 4 2 3 1 5 17 22 3 1 17 10 4 101 14.51-20.50 1 0 0 0 18 0 0 2 1 8 20 4 5 6 5 3 73

>20.50 0 0 0 0 2 0 0 1 3 0 2 2 0 0 0 0 10 TOTAL 38 34 34 21 36 12 14 14 37 89 144 65 51 55 51 36 731 PVNGS 2016 ARERR Page 68

STABILITY CLASS F SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 1 0 1 0 0 0 0 0 0 0 0 0 0 3 1.51- 2.50 5 2 0 2 0 1 4 1 2 1 5 5 5 6 5 4 48 2.51- 3.50 9 7 2 7 4 3 3 2 1 3 8 4 10 9 17 13 102 3.51- 4.50 7 4 1 4 1 3 0 0 1 11 10 6 5 7 10 12 82 4.51- 5.50 5 5 6 1 1 1 4 0 1 9 12 13 6 5 6 8 83 5.51- 6.50 4 9 8 3 1 1 3 1 1 12 13 11 7 5 4 10 93 6.51- 8.50 6 8 7 4 1 2 1 2 2 20 30 14 6 7 9 8 127 8.51-11.50 3 1 2 2 0 1 0 0 1 18 20 7 4 12 9 9 89 11.51-14.50 0 0 0 0 0 0 0 0 0 1 0 0 1 0 0 2 4 14.51-20.50 0 0 0 1 1 0 0 0 0 0 1 0 0 0 0 0 3

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 39 36 27 25 9 13 15 6 9 75 99 60 44 51 60 66 634 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 6/30/2016

      • 1ST SEMI ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 1 0 0 0 0 1 0 0 0 0 0 0 1 2 0 5 1.51- 2.50 15 5 3 1 4 1 1 0 0 2 1 5 9 10 18 22 97 2.51- 3.50 70 12 9 8 5 10 5 4 2 5 6 2 8 28 41 56 271 3.51- 4.50 93 22 8 8 1 5 7 2 1 4 4 8 11 18 35 86 313 4.51- 5.50 95 24 4 4 1 5 7 0 1 1 6 4 3 6 21 48 230 5.51- 6.50 47 24 5 1 1 0 2 2 1 3 1 3 2 6 5 16 119 6.51- 8.50 46 12 3 2 1 0 1 1 1 3 1 2 2 0 1 16 92 8.51-11.50 16 11 1 1 0 0 0 0 0 2 0 0 0 0 1 2 34 11.51-14.50 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 382 111 33 25 13 22 24 9 6 20 19 24 35 69 124 246 1162 STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 1 1 3 2 1 1 2 0 0 1 1 1 0 1 4 0 19 1.51- 2.50 27 13 5 5 7 5 11 7 6 11 13 17 21 21 26 31 226 2.51- 3.50 100 29 16 21 17 18 20 17 23 33 37 24 31 52 73 81 592 3.51- 4.50 110 37 21 21 7 14 12 9 31 49 41 28 28 30 59 108 605 4.51- 5.50 112 49 27 20 12 12 27 20 54 52 47 28 17 19 34 66 596 5.51- 6.50 60 46 36 14 6 7 12 19 59 69 49 40 19 22 17 33 508 6.51- 8.50 61 37 47 38 20 17 16 23 61 77 108 55 40 21 15 30 666 8.51-11.50 26 23 23 22 22 30 9 13 20 83 110 52 45 25 19 24 546 11.51-14.50 6 3 10 8 14 7 8 3 14 50 73 18 11 25 16 11 277 14.51-20.50 2 2 8 5 28 4 2 3 10 34 46 10 11 17 7 7 196

>20.50 0 0 1 0 2 1 0 2 3 8 11 3 0 2 1 0 34 TOTAL 505 240 197 156 136 116 119 116 281 467 536 276 223 235 271 391 4265 TOTAL NUMBER OF OBSERVATIONS: 4272 TOTAL NUMBER OF VALID OBSERVATIONS: 4265 TOTAL NUMBER OF MISSING OBSERVATIONS: 7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.8 %

MEAN WIND SPEED FOR THIS PERIOD: 6.8 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 9.26 6.45 6.40 18.64 17.14 14.87 27.25 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 2 3 12 13 17 18 13 22 63 65 80 30 20 15 13 9 0 B 1 7 10 14 10 15 7 17 46 48 49 24 12 9 3 3 0 C 6 6 24 16 18 9 9 12 42 53 31 18 13 7 2 7 0 D 37 43 57 42 33 27 37 36 78 117 114 55 48 29 18 24 0 E 38 34 34 21 36 12 14 14 37 89 144 65 51 55 51 36 0 F 39 36 27 25 9 13 15 6 9 75 99 60 44 51 60 66 0 G 382 111 33 25 13 22 24 9 6 20 19 24 35 69 124 246 0 TOTAL 505 240 197 156 136 116 119 116 281 467 536 276 223 235 271 391 0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 9/30/2016 PVNGS 2016 ARERR Page 69

      • 3RD QRTR ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 4.51- 5.50 0 0 1 0 0 0 1 1 0 0 0 0 0 0 0 0 3 5.51- 6.50 0 0 0 2 2 4 3 7 14 5 1 2 0 0 0 1 41 6.51- 8.50 1 2 1 2 4 10 9 18 24 18 18 10 5 3 2 1 128 8.51-11.50 0 1 0 0 3 18 1 5 11 15 26 15 11 3 2 2 113 11.51-14.50 0 0 0 0 1 2 0 2 0 3 12 4 1 0 0 0 25 14.51-20.50 0 0 0 1 0 0 0 1 0 2 3 0 0 0 0 0 7

>20.50 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 TOTAL 2 3 3 5 10 34 14 34 49 43 60 31 17 6 4 4 319 STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.51- 5.50 1 0 0 0 0 0 2 3 6 2 2 0 1 0 0 1 18 5.51- 6.50 0 2 2 0 1 0 0 3 10 6 7 1 1 1 0 0 34 6.51- 8.50 0 2 1 4 3 5 4 5 8 8 13 7 4 0 0 1 65 8.51-11.50 0 0 2 3 3 6 0 0 4 6 17 9 2 2 0 0 54 11.51-14.50 0 0 1 0 1 1 1 0 4 3 7 1 0 0 0 0 19 14.51-20.50 0 0 0 0 2 0 0 1 0 0 2 0 0 0 0 0 5

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 4 6 7 10 12 7 12 32 25 48 18 8 3 0 2 195 STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 1 0 0 1 1 0 0 0 0 0 1 0 1 0 5 4.51- 5.50 0 1 1 0 1 1 3 2 8 5 3 1 0 0 2 2 30 5.51- 6.50 1 0 0 0 2 0 1 1 8 4 6 4 1 0 0 1 29 6.51- 8.50 0 1 2 2 1 2 2 1 5 12 14 2 3 1 2 0 50 8.51-11.50 0 1 0 1 0 0 0 0 1 5 11 0 1 0 0 0 20 11.51-14.50 1 1 1 0 4 0 0 0 1 0 3 0 0 0 0 0 11 14.51-20.50 1 0 0 0 3 1 0 1 0 1 1 0 0 0 0 0 8

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 4 5 3 11 5 7 5 23 27 38 7 6 1 5 3 153 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 9/30/2016

      • 3RD QRTR ***

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 2 0 0 3 1 0 0 0 1 0 1 1 1 3 0 1 14 2.51- 3.50 2 1 2 1 1 1 0 3 5 5 1 2 4 2 5 2 37 3.51- 4.50 2 2 2 3 2 2 1 1 8 5 6 2 1 4 0 3 44 4.51- 5.50 2 1 3 2 3 2 0 1 6 7 7 6 2 2 0 3 47 5.51- 6.50 1 2 1 0 0 0 0 2 5 7 9 6 2 1 1 1 38 6.51- 8.50 2 1 2 2 4 4 3 1 9 6 14 3 4 1 2 0 58 8.51-11.50 3 4 2 3 6 4 1 0 4 16 22 7 3 2 1 0 78 11.51-14.50 1 6 4 1 16 4 0 2 1 2 20 4 0 0 0 0 61 14.51-20.50 0 3 0 2 11 1 3 3 1 0 22 2 1 0 1 1 51

>20.50 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 0 2 TOTAL 15 20 16 17 44 19 8 14 40 48 102 33 18 15 10 11 430 PVNGS 2016 ARERR Page 70

STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 1.51- 2.50 2 1 1 0 2 1 0 0 2 0 0 1 1 4 2 5 22 2.51- 3.50 7 1 3 2 0 1 0 0 1 0 4 2 2 4 8 3 38 3.51- 4.50 4 4 1 1 2 1 0 0 3 2 4 9 6 2 3 3 45 4.51- 5.50 5 1 4 1 1 2 1 0 2 9 12 6 2 1 2 1 50 5.51- 6.50 6 2 5 2 1 4 0 3 2 14 10 6 3 1 3 1 63 6.51- 8.50 3 5 3 6 7 6 2 6 4 18 36 7 4 2 2 2 113 8.51-11.50 3 2 3 10 14 6 4 4 4 25 62 15 1 4 1 3 161 11.51-14.50 2 0 0 3 21 4 3 1 0 9 33 7 0 1 0 1 85 14.51-20.50 3 2 2 0 18 4 0 0 1 2 9 0 0 0 0 0 41

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 35 18 22 25 66 29 10 14 20 79 170 53 19 19 21 19 619 STABILITY CLASS F SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 1.51- 2.50 3 1 1 0 1 0 1 0 0 0 3 1 3 3 2 1 20 2.51- 3.50 5 1 2 3 0 0 0 2 0 2 3 4 2 1 4 5 34 3.51- 4.50 6 5 4 0 0 0 0 0 0 3 3 5 7 8 7 5 53 4.51- 5.50 10 6 3 2 0 0 1 1 3 6 15 4 3 3 3 2 62 5.51- 6.50 1 4 1 1 0 0 1 1 1 3 7 2 2 0 2 3 29 6.51- 8.50 6 2 2 1 0 0 2 0 1 8 21 6 3 1 1 0 54 8.51-11.50 1 3 1 0 0 0 0 0 0 2 9 2 0 2 0 0 20 11.51-14.50 0 1 0 0 1 0 1 0 0 0 0 1 0 0 0 1 5 14.51-20.50 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 TOTAL 34 23 14 7 2 0 6 5 5 24 61 25 20 18 20 17 281 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 9/30/2016

      • 3RD QRTR ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 4 0 0 0 0 0 0 0 0 0 0 1 0 0 5 3 13 2.51- 3.50 5 5 1 1 0 1 0 0 0 0 2 0 1 4 5 10 35 3.51- 4.50 24 5 1 1 0 0 0 0 1 0 0 1 2 0 1 8 44 4.51- 5.50 20 12 2 0 0 0 0 0 1 0 1 2 0 0 4 5 47 5.51- 6.50 7 5 2 0 0 0 0 0 1 0 1 1 0 0 0 2 19 6.51- 8.50 11 6 0 0 0 0 0 0 0 1 2 0 0 0 0 2 22 8.51-11.50 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 11.51-14.50 1 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 2 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 TOTAL 76 33 6 3 0 1 0 0 3 1 6 5 3 4 16 30 187 STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 2 1.51- 2.50 11 2 2 3 4 1 1 0 3 0 4 4 5 10 9 10 69 2.51- 3.50 19 8 8 7 1 3 0 5 6 7 10 8 9 11 22 20 144 3.51- 4.50 36 16 10 5 4 4 2 1 12 10 13 17 17 14 12 19 192 4.51- 5.50 38 21 14 5 5 5 8 8 26 29 40 19 8 6 11 14 257 5.51- 6.50 16 15 11 5 6 8 5 17 41 39 41 22 9 3 6 9 253 6.51- 8.50 23 19 11 17 19 27 22 31 51 71 118 35 23 8 9 6 490 8.51-11.50 11 11 8 17 26 34 6 9 24 69 147 48 18 13 4 5 450 11.51-14.50 5 8 6 5 44 11 5 5 6 17 75 17 1 1 0 2 208 14.51-20.50 6 5 2 3 34 6 3 6 2 5 37 2 1 0 1 1 114

>20.50 1 0 0 0 0 1 0 1 0 0 0 0 0 0 2 0 5 TOTAL 166 105 72 67 143 100 52 84 172 247 485 172 91 66 76 86 2184 TOTAL NUMBER OF OBSERVATIONS: 2184 TOTAL NUMBER OF VALID OBSERVATIONS: 2184 TOTAL NUMBER OF MISSING OBSERVATIONS: 0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %

MEAN WIND SPEED FOR THIS PERIOD: 7.8 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 14.61 8.93 7.01 19.69 28.34 12.87 8.56 PVNGS 2016 ARERR Page 71

DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 2 3 3 5 10 34 14 34 49 43 60 31 17 6 4 4 0 B 1 4 6 7 10 12 7 12 32 25 48 18 8 3 0 2 0 C 3 4 5 3 11 5 7 5 23 27 38 7 6 1 5 3 0 D 15 20 16 17 44 19 8 14 40 48 102 33 18 15 10 11 0 E 35 18 22 25 66 29 10 14 20 79 170 53 19 19 21 19 0 F 34 23 14 7 2 0 6 5 5 24 61 25 20 18 20 17 0 G 76 33 6 3 0 1 0 0 3 1 6 5 3 4 16 30 0 TOTAL 166 105 72 67 143 100 52 84 172 247 485 172 91 66 76 86 0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016

      • 4TH QRTR ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.51- 5.50 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 5.51- 6.50 0 0 0 1 0 0 2 1 1 0 0 0 0 0 0 0 5 6.51- 8.50 0 0 1 0 2 1 6 4 2 0 2 0 0 0 2 0 20 8.51-11.50 0 0 0 1 0 3 0 0 0 1 0 0 1 2 0 1 9 11.51-14.50 0 0 0 0 0 0 0 0 0 0 1 0 1 1 0 0 3 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 1 2 3 4 8 5 3 1 3 0 2 3 2 1 38 STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 1 0 0 1 0 0 0 0 0 0 2 4.51- 5.50 0 0 0 2 1 1 1 4 5 0 1 0 0 0 1 2 18 5.51- 6.50 0 0 2 2 1 1 3 4 2 2 0 1 0 0 0 0 18 6.51- 8.50 0 0 0 5 5 2 3 6 0 7 2 0 0 0 0 1 31 8.51-11.50 1 0 0 0 5 0 1 0 0 3 3 0 0 0 1 0 14 11.51-14.50 0 0 0 1 3 0 0 1 0 0 1 0 0 0 0 0 6 14.51-20.50 0 0 1 2 0 0 0 0 0 0 0 0 0 0 0 0 3

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 0 3 12 15 4 9 15 7 13 7 1 0 0 2 3 92 STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 3.51- 4.50 0 0 0 0 0 2 3 6 6 4 1 0 1 1 1 0 25 4.51- 5.50 1 2 2 5 2 0 1 8 10 3 0 1 1 1 1 0 38 5.51- 6.50 0 1 0 1 0 1 0 3 1 0 1 0 1 0 1 1 11 6.51- 8.50 0 0 2 3 1 0 1 0 2 2 3 1 0 0 1 1 17 8.51-11.50 0 1 4 0 3 2 0 0 0 3 4 0 0 0 0 2 19 11.51-14.50 0 1 0 0 7 0 0 0 0 2 0 1 0 1 0 1 13 14.51-20.50 0 0 0 0 1 0 0 0 0 0 2 0 0 0 0 0 3

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 5 8 9 14 5 5 17 19 14 12 3 3 3 4 5 127 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016

      • 4TH QRTR ***

PVNGS 2016 ARERR Page 72

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 1 2 2 1 1 0 1 3 1 0 5 2 0 0 3 2 24 2.51- 3.50 10 2 3 5 2 1 1 4 6 9 7 6 10 8 2 7 83 3.51- 4.50 6 4 7 3 1 2 1 4 13 11 6 1 2 3 5 8 77 4.51- 5.50 1 3 4 3 3 1 4 3 3 4 6 4 3 1 0 4 47 5.51- 6.50 3 1 4 3 0 1 0 0 3 4 4 4 1 1 1 0 30 6.51- 8.50 5 4 1 2 1 3 1 1 2 5 12 4 1 0 3 3 48 8.51-11.50 0 1 6 3 5 1 2 0 0 4 8 3 1 1 1 2 38 11.51-14.50 0 1 0 1 15 3 2 0 0 0 9 3 2 0 0 0 36 14.51-20.50 0 0 1 0 18 0 1 0 1 1 2 1 0 0 0 0 25

>20.50 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 TOTAL 26 18 28 21 47 12 13 15 29 38 59 28 20 14 15 26 409 STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 1.51- 2.50 5 4 0 1 0 1 1 1 2 3 7 4 5 11 4 1 50 2.51- 3.50 3 2 0 1 1 3 0 1 4 3 3 3 3 4 2 6 39 3.51- 4.50 8 6 1 2 1 0 0 1 3 3 5 4 2 4 6 3 49 4.51- 5.50 1 6 0 2 0 0 1 3 2 2 8 7 1 0 3 5 41 5.51- 6.50 3 3 3 2 0 0 0 1 2 2 3 4 3 2 1 0 29 6.51- 8.50 4 3 4 2 2 3 1 1 0 5 9 3 3 0 1 1 42 8.51-11.50 1 2 0 3 6 8 1 1 3 3 2 3 0 1 1 2 37 11.51-14.50 0 1 1 0 6 4 1 0 0 1 1 5 1 1 1 0 23 14.51-20.50 0 0 0 0 6 0 0 0 0 1 6 1 0 3 0 1 18

>20.50 0 0 0 0 0 0 0 0 0 0 0 1 1 3 0 0 5 TOTAL 25 27 9 13 22 19 5 9 17 23 44 35 19 29 19 19 334 STABILITY CLASS F SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 1.51- 2.50 5 3 6 0 1 1 0 3 1 0 1 7 3 8 7 2 48 2.51- 3.50 11 4 4 0 0 0 2 0 0 2 3 2 5 7 5 4 49 3.51- 4.50 8 1 2 4 1 0 0 0 4 1 7 5 7 5 11 8 64 4.51- 5.50 7 1 3 0 1 0 0 0 2 2 9 6 0 2 5 3 41 5.51- 6.50 5 0 0 0 1 0 0 0 0 2 6 3 2 3 2 6 30 6.51- 8.50 4 1 2 5 0 0 1 0 1 4 10 2 1 2 4 5 42 8.51-11.50 1 2 3 4 0 0 1 1 0 0 2 0 1 2 0 3 20 11.51-14.50 0 0 1 1 1 0 0 0 0 0 0 0 0 0 0 1 4 14.51-20.50 0 0 0 1 4 0 0 0 0 0 0 0 0 0 0 0 5

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 41 12 21 15 9 1 4 4 8 12 38 25 19 29 34 32 304 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 10/01/2016 TO 12/31/2016

      • 4TH QRTR ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 4 1.51- 2.50 20 12 3 2 1 1 1 1 2 2 2 4 8 15 16 20 110 2.51- 3.50 56 17 3 4 0 0 0 3 1 1 5 4 6 22 36 53 211 3.51- 4.50 79 37 5 6 2 1 0 1 2 1 3 0 10 7 20 52 226 4.51- 5.50 45 30 4 1 0 0 0 0 0 0 1 0 1 1 3 24 110 5.51- 6.50 23 14 7 2 0 0 0 0 0 1 0 1 0 0 4 10 62 6.51- 8.50 26 19 2 2 0 0 0 0 0 0 0 0 0 0 1 13 63 8.51-11.50 5 8 5 1 0 0 0 0 0 0 0 0 0 0 0 2 21 11.51-14.50 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 254 137 29 19 3 2 1 5 5 5 11 9 27 45 80 176 808 PVNGS 2016 ARERR Page 73

STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 1 1 0 0 2 0 0 2 6 1.51- 2.50 31 21 11 4 3 3 3 8 6 5 15 17 16 34 30 25 232 2.51- 3.50 80 25 10 10 3 4 3 8 11 15 19 15 24 41 45 70 383 3.51- 4.50 101 48 15 15 5 5 5 12 28 21 22 10 22 20 43 71 443 4.51- 5.50 55 42 13 13 8 2 7 18 22 11 25 18 6 5 13 38 296 5.51- 6.50 34 19 16 11 2 3 5 9 9 11 14 13 7 6 9 17 185 6.51- 8.50 39 27 12 19 11 9 13 12 7 23 38 10 5 2 12 24 263 8.51-11.50 8 14 18 12 19 14 5 2 3 14 19 6 3 6 3 12 158 11.51-14.50 0 3 2 4 32 7 3 1 0 3 12 9 4 3 1 2 86 14.51-20.50 0 0 2 3 29 0 1 0 1 2 10 2 0 3 0 1 54

>20.50 0 0 0 0 1 0 0 0 0 0 0 1 1 3 0 0 6 TOTAL 348 199 99 91 113 47 45 70 88 106 174 101 90 123 156 262 2112 TOTAL NUMBER OF OBSERVATIONS: 2112 TOTAL NUMBER OF VALID OBSERVATIONS: 2112 TOTAL NUMBER OF MISSING OBSERVATIONS: 0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %

MEAN WIND SPEED FOR THIS PERIOD: 5.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 1.80 4.36 6.01 19.37 15.81 14.39 38.26 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 0 0 1 2 3 4 8 5 3 1 3 0 2 3 2 1 0 B 1 0 3 12 15 4 9 15 7 13 7 1 0 0 2 3 0 C 1 5 8 9 14 5 5 17 19 14 12 3 3 3 4 5 0 D 26 18 28 21 47 12 13 15 29 38 59 28 20 14 15 26 0 E 25 27 9 13 22 19 5 9 17 23 44 35 19 29 19 19 0 F 41 12 21 15 9 1 4 4 8 12 38 25 19 29 34 32 0 G 254 137 29 19 3 2 1 5 5 5 11 9 27 45 80 176 0 TOTAL 348 199 99 91 113 47 45 70 88 106 174 101 90 123 156 262 0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016

      • 2ND SEMI ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 4.51- 5.50 0 0 1 0 1 0 1 1 0 0 0 0 0 0 0 0 4 5.51- 6.50 0 0 0 3 2 4 5 8 15 5 1 2 0 0 0 1 46 6.51- 8.50 1 2 2 2 6 11 15 22 26 18 20 10 5 3 4 1 148 8.51-11.50 0 1 0 1 3 21 1 5 11 16 26 15 12 5 2 3 122 11.51-14.50 0 0 0 0 1 2 0 2 0 3 13 4 2 1 0 0 28 14.51-20.50 0 0 0 1 0 0 0 1 0 2 3 0 0 0 0 0 7

>20.50 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 TOTAL 2 3 4 7 13 38 22 39 52 44 63 31 19 9 6 5 357 STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 1 0 0 1 0 0 0 0 0 0 2 4.51- 5.50 1 0 0 2 1 1 3 7 11 2 3 0 1 0 1 3 36 5.51- 6.50 0 2 4 2 2 1 3 7 12 8 7 2 1 1 0 0 52 6.51- 8.50 0 2 1 9 8 7 7 11 8 15 15 7 4 0 0 2 96 8.51-11.50 1 0 2 3 8 6 1 0 4 9 20 9 2 2 1 0 68 11.51-14.50 0 0 1 1 4 1 1 1 4 3 8 1 0 0 0 0 25 14.51-20.50 0 0 1 2 2 0 0 1 0 0 2 0 0 0 0 0 8

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 2 4 9 19 25 16 16 27 39 38 55 19 8 3 2 5 287 PVNGS 2016 ARERR Page 74

STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 3.51- 4.50 0 0 1 0 0 3 4 6 6 4 1 0 2 1 2 0 30 4.51- 5.50 1 3 3 5 3 1 4 10 18 8 3 2 1 1 3 2 68 5.51- 6.50 1 1 0 1 2 1 1 4 9 4 7 4 2 0 1 2 40 6.51- 8.50 0 1 4 5 2 2 3 1 7 14 17 3 3 1 3 1 67 8.51-11.50 0 2 4 1 3 2 0 0 1 8 15 0 1 0 0 2 39 11.51-14.50 1 2 1 0 11 0 0 0 1 2 3 1 0 1 0 1 24 14.51-20.50 1 0 0 0 4 1 0 1 0 1 3 0 0 0 0 0 11

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4 9 13 12 25 10 12 22 42 41 50 10 9 4 9 8 280 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016

      • 2ND SEMI ***

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 3 2 2 4 2 0 1 3 2 0 6 3 1 3 3 3 38 2.51- 3.50 12 3 5 6 3 2 1 7 11 14 8 8 14 10 7 9 120 3.51- 4.50 8 6 9 6 3 4 2 5 21 16 12 3 3 7 5 11 121 4.51- 5.50 3 4 7 5 6 3 4 4 9 11 13 10 5 3 0 7 94 5.51- 6.50 4 3 5 3 0 1 0 2 8 11 13 10 3 2 2 1 68 6.51- 8.50 7 5 3 4 5 7 4 2 11 11 26 7 5 1 5 3 106 8.51-11.50 3 5 8 6 11 5 3 0 4 20 30 10 4 3 2 2 116 11.51-14.50 1 7 4 2 31 7 2 2 1 2 29 7 2 0 0 0 97 14.51-20.50 0 3 1 2 29 1 4 3 2 1 24 3 1 0 1 1 76

>20.50 0 0 0 0 1 1 0 1 0 0 0 0 0 0 0 0 3 TOTAL 41 38 44 38 91 31 21 29 69 86 161 61 38 29 25 37 839 STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 2 1.51- 2.50 7 5 1 1 2 2 1 1 4 3 7 5 6 15 6 6 72 2.51- 3.50 10 3 3 3 1 4 0 1 5 3 7 5 5 8 10 9 77 3.51- 4.50 12 10 2 3 3 1 0 1 6 5 9 13 8 6 9 6 94 4.51- 5.50 6 7 4 3 1 2 2 3 4 11 20 13 3 1 5 6 91 5.51- 6.50 9 5 8 4 1 4 0 4 4 16 13 10 6 3 4 1 92 6.51- 8.50 7 8 7 8 9 9 3 7 4 23 45 10 7 2 3 3 155 8.51-11.50 4 4 3 13 20 14 5 5 7 28 64 18 1 5 2 5 198 11.51-14.50 2 1 1 3 27 8 4 1 0 10 34 12 1 2 1 1 108 14.51-20.50 3 2 2 0 24 4 0 0 1 3 15 1 0 3 0 1 59

>20.50 0 0 0 0 0 0 0 0 0 0 0 1 1 3 0 0 5 TOTAL 60 45 31 38 88 48 15 23 37 102 214 88 38 48 40 38 953 STABILITY CLASS F SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 2 1.51- 2.50 8 4 7 0 2 1 1 3 1 0 4 8 6 11 9 3 68 2.51- 3.50 16 5 6 3 0 0 2 2 0 4 6 6 7 8 9 9 83 3.51- 4.50 14 6 6 4 1 0 0 0 4 4 10 10 14 13 18 13 117 4.51- 5.50 17 7 6 2 1 0 1 1 5 8 24 10 3 5 8 5 103 5.51- 6.50 6 4 1 1 1 0 1 1 1 5 13 5 4 3 4 9 59 6.51- 8.50 10 3 4 6 0 0 3 0 2 12 31 8 4 3 5 5 96 8.51-11.50 2 5 4 4 0 0 1 1 0 2 11 2 1 4 0 3 40 11.51-14.50 0 1 1 1 2 0 1 0 0 0 0 1 0 0 0 2 9 14.51-20.50 2 0 0 1 4 0 0 0 0 0 0 0 0 0 0 0 7

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 TOTAL 75 35 35 22 11 1 10 9 13 36 99 50 39 47 54 49 585 PVNGS 2016 ARERR Page 75

ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 7/01/2016 TO 12/31/2016

      • 2ND SEMI ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 4 1.51- 2.50 24 12 3 2 1 1 1 1 2 2 2 5 8 15 21 23 123 2.51- 3.50 61 22 4 5 0 1 0 3 1 1 7 4 7 26 41 63 246 3.51- 4.50 103 42 6 7 2 1 0 1 3 1 3 1 12 7 21 60 270 4.51- 5.50 65 42 6 1 0 0 0 0 1 0 2 2 1 1 7 29 157 5.51- 6.50 30 19 9 2 0 0 0 0 1 1 1 2 0 0 4 12 81 6.51- 8.50 37 25 2 2 0 0 0 0 0 1 2 0 0 0 1 15 85 8.51-11.50 9 8 5 1 0 0 0 0 0 0 0 0 0 0 0 2 25 11.51-14.50 1 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 3 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 TOTAL 330 170 35 22 3 3 1 5 8 6 17 14 30 49 96 206 995 STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 1 2 1 0 0 2 0 0 2 8 1.51- 2.50 42 23 13 7 7 4 4 8 9 5 19 21 21 44 39 35 301 2.51- 3.50 99 33 18 17 4 7 3 13 17 22 29 23 33 52 67 90 527 3.51- 4.50 137 64 25 20 9 9 7 13 40 31 35 27 39 34 55 90 635 4.51- 5.50 93 63 27 18 13 7 15 26 48 40 65 37 14 11 24 52 553 5.51- 6.50 50 34 27 16 8 11 10 26 50 50 55 35 16 9 15 26 438 6.51- 8.50 62 46 23 36 30 36 35 43 58 94 156 45 28 10 21 30 753 8.51-11.50 19 25 26 29 45 48 11 11 27 83 166 54 21 19 7 17 608 11.51-14.50 5 11 8 9 76 18 8 6 6 20 87 26 5 4 1 4 294 14.51-20.50 6 5 4 6 63 6 4 6 3 7 47 4 1 3 1 2 168

>20.50 1 0 0 0 1 1 0 1 0 0 0 1 1 3 2 0 11 TOTAL 514 304 171 158 256 147 97 154 260 353 659 273 181 189 232 348 4296 TOTAL NUMBER OF OBSERVATIONS: 4296 TOTAL NUMBER OF VALID OBSERVATIONS: 4296 TOTAL NUMBER OF MISSING OBSERVATIONS: 0 PERCENT DATA RECOVERY FOR THIS PERIOD: 100.0 %

MEAN WIND SPEED FOR THIS PERIOD: 6.7 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 8.31 6.68 6.52 19.53 22.18 13.62 23.16 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 2 3 4 7 13 38 22 39 52 44 63 31 19 9 6 5 0 B 2 4 9 19 25 16 16 27 39 38 55 19 8 3 2 5 0 C 4 9 13 12 25 10 12 22 42 41 50 10 9 4 9 8 0 D 41 38 44 38 91 31 21 29 69 86 161 61 38 29 25 37 0 E 60 45 31 38 88 48 15 23 37 102 214 88 38 48 40 38 0 F 75 35 35 22 11 1 10 9 13 36 99 50 39 47 54 49 0 G 330 170 35 22 3 3 1 5 8 6 17 14 30 49 96 206 0 TOTAL 514 304 171 158 256 147 97 154 260 353 659 273 181 189 232 348 0 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 12/31/2016

      • ANNUAL ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 4.51- 5.50 0 0 1 1 2 1 3 2 3 0 1 0 0 0 0 0 14 5.51- 6.50 0 1 0 3 4 4 6 14 28 13 5 2 0 0 0 1 81 6.51- 8.50 1 2 3 6 9 15 21 32 53 28 39 17 9 6 5 1 247 8.51-11.50 1 2 0 5 11 31 1 9 19 35 51 25 22 9 7 5 233 11.51-14.50 1 1 5 1 2 3 4 2 7 17 35 14 6 4 6 3 111 14.51-20.50 0 0 5 4 2 2 0 2 5 14 6 2 2 4 0 4 52

>20.50 1 0 1 0 0 0 0 0 0 2 6 1 0 1 1 0 13 TOTAL 4 6 16 20 30 56 35 61 115 109 143 61 39 24 19 14 752 PVNGS 2016 ARERR Page 76

STABILITY CLASS B SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.51- 4.50 0 0 0 0 0 0 1 0 1 1 1 0 0 0 0 0 4 4.51- 5.50 1 1 1 5 2 2 4 12 23 3 5 1 2 1 2 4 69 5.51- 6.50 1 4 4 4 3 2 5 11 33 18 14 9 3 3 2 0 116 6.51- 8.50 0 4 6 14 11 13 8 16 18 28 29 15 10 2 0 2 176 8.51-11.50 1 1 4 7 11 9 4 2 6 21 32 15 5 3 1 2 124 11.51-14.50 0 1 1 1 5 4 1 2 4 9 17 2 0 2 0 0 49 14.51-20.50 0 0 3 2 3 0 0 1 0 4 6 1 0 0 0 0 20

>20.50 0 0 0 0 0 1 0 0 0 2 0 0 0 1 0 0 4 TOTAL 3 11 19 33 35 31 23 44 85 86 104 43 20 12 5 8 562 STABILITY CLASS C SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51- 2.50 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2.51- 3.50 0 0 0 0 0 0 0 0 0 0 1 1 0 1 0 0 3 3.51- 4.50 0 0 1 0 0 3 4 6 9 8 3 2 4 1 2 1 44 4.51- 5.50 3 3 6 10 7 2 7 16 35 19 5 3 2 2 4 5 129 5.51- 6.50 3 3 6 3 3 2 2 7 20 23 14 11 5 2 1 4 109 6.51- 8.50 0 5 12 12 9 5 6 2 15 23 22 8 6 3 4 2 134 8.51-11.50 0 2 10 3 6 6 1 2 4 13 17 2 4 0 0 2 72 11.51-14.50 2 2 2 0 14 0 1 0 1 5 10 1 1 1 0 1 41 14.51-20.50 1 0 0 0 4 1 0 1 0 3 8 0 0 1 0 0 19

>20.50 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTAL 10 15 37 28 43 19 21 34 84 94 81 28 22 11 11 15 553 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 12/31/2016

      • ANNUAL ***

STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 1 0 1 0 0 0 1 0 0 1 0 0 0 0 0 0 4 1.51- 2.50 4 3 4 5 2 1 7 6 5 6 11 5 6 4 4 5 78 2.51- 3.50 26 8 9 10 9 6 11 18 31 34 27 17 19 18 9 18 270 3.51- 4.50 15 15 20 13 5 9 7 11 42 40 29 9 10 8 11 15 259 4.51- 5.50 9 19 18 10 9 6 13 12 21 28 29 16 10 7 1 10 218 5.51- 6.50 6 6 16 9 0 5 1 4 16 22 20 17 5 4 5 3 139 6.51- 8.50 12 10 12 16 8 7 5 3 17 17 37 15 10 3 6 4 182 8.51-11.50 3 8 14 9 19 13 5 3 6 31 41 20 15 5 4 3 199 11.51-14.50 1 7 5 5 36 7 2 3 3 11 42 11 6 3 0 2 144 14.51-20.50 1 5 2 3 35 3 6 3 6 9 37 6 5 6 3 1 131

>20.50 0 0 0 0 1 1 0 2 0 4 2 0 0 0 0 0 10 TOTAL 78 81 101 80 124 58 58 65 147 203 275 116 86 58 43 61 1634 STABILITY CLASS E SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 1 1 0 0 0 2 0 1 1 0 0 2 0 9 1.51- 2.50 12 10 1 2 5 4 1 4 5 5 9 10 8 19 8 9 112 2.51- 3.50 17 8 4 5 3 5 2 1 5 8 11 13 13 14 23 12 144 3.51- 4.50 15 12 3 5 6 2 0 2 10 11 16 19 11 10 17 11 150 4.51- 5.50 10 11 6 4 2 2 3 3 12 24 28 16 4 3 9 9 146 5.51- 6.50 13 10 14 4 1 4 2 5 8 22 23 15 9 8 7 4 149 6.51- 8.50 11 14 21 12 11 11 6 10 11 39 73 21 21 7 5 7 280 8.51-11.50 10 10 9 19 20 18 8 7 11 44 104 35 15 11 4 13 338 11.51-14.50 6 2 4 7 31 10 7 2 5 27 56 15 2 19 11 5 209 14.51-20.50 4 2 2 0 42 4 0 2 2 11 35 5 5 9 5 4 132

>20.50 0 0 0 0 2 0 0 1 3 0 2 3 1 3 0 0 15 TOTAL 98 79 65 59 124 60 29 37 74 191 358 153 89 103 91 74 1684 STABILITY CLASS F PVNGS 2016 ARERR Page 77

SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 0 1 1 0 1 0 1 0 1 0 0 0 0 0 0 5 1.51- 2.50 13 6 7 2 2 2 5 4 3 1 9 13 11 17 14 7 116 2.51- 3.50 25 12 8 10 4 3 5 4 1 7 14 10 17 17 26 22 185 3.51- 4.50 21 10 7 8 2 3 0 0 5 15 20 16 19 20 28 25 199 4.51- 5.50 22 12 12 3 2 1 5 1 6 17 36 23 9 10 14 13 186 5.51- 6.50 10 13 9 4 2 1 4 2 2 17 26 16 11 8 8 19 152 6.51- 8.50 16 11 11 10 1 2 4 2 4 32 61 22 10 10 14 13 223 8.51-11.50 5 6 6 6 0 1 1 1 1 20 31 9 5 16 9 12 129 11.51-14.50 0 1 1 1 2 0 1 0 0 1 0 1 1 0 0 4 13 14.51-20.50 2 0 0 2 5 0 0 0 0 0 1 0 0 0 0 0 10

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 TOTAL 114 71 62 47 20 14 25 15 22 111 198 110 83 98 114 115 1219 ARIZONA PUBLIC SERVICE CO. - PALO VERDE NUCLEAR GENERATING STATION JOINT FREQUENCY DISTRIBUTION FOR THE PERIOD 1/01/2016 TO 12/31/2016

      • ANNUAL ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 200.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: .75 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 0 1 0 0 0 0 1 0 0 0 0 0 2 1 2 2 9 1.51- 2.50 39 17 6 3 5 2 2 1 2 4 3 10 17 25 39 45 220 2.51- 3.50 131 34 13 13 5 11 5 7 3 6 13 6 15 54 82 119 517 3.51- 4.50 196 64 14 15 3 6 7 3 4 5 7 9 23 25 56 146 583 4.51- 5.50 160 66 10 5 1 5 7 0 2 1 8 6 4 7 28 77 387 5.51- 6.50 77 43 14 3 1 0 2 2 2 4 2 5 2 6 9 28 200 6.51- 8.50 83 37 5 4 1 0 1 1 1 4 3 2 2 0 2 31 177 8.51-11.50 25 19 6 2 0 0 0 0 0 2 0 0 0 0 1 4 59 11.51-14.50 1 0 0 2 0 1 0 0 0 0 0 0 0 0 0 0 4 14.51-20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>20.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 TOTAL 712 281 68 47 16 25 25 14 14 26 36 38 65 118 220 452 2157 STABILITY CLASS ALL SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0

.76- 1.50 1 1 3 2 1 1 2 1 2 2 1 1 2 1 4 2 27 1.51- 2.50 69 36 18 12 14 9 15 15 15 16 32 38 42 65 65 66 527 2.51- 3.50 199 62 34 38 21 25 23 30 40 55 66 47 64 104 140 171 1119 3.51- 4.50 247 101 46 41 16 23 19 22 71 80 76 55 67 64 114 198 1240 4.51- 5.50 205 112 54 38 25 19 42 46 102 92 112 65 31 30 58 118 1149 5.51- 6.50 110 80 63 30 14 18 22 45 109 119 104 75 35 31 32 59 946 6.51- 8.50 123 83 70 74 50 53 51 66 119 171 264 100 68 31 36 60 1419 8.51-11.50 45 48 49 51 67 78 20 24 47 166 276 106 66 44 26 41 1154 11.51-14.50 11 14 18 17 90 25 16 9 20 70 160 44 16 29 17 15 571 14.51-20.50 8 7 12 11 91 10 6 9 13 41 93 14 12 20 8 9 364

>20.50 1 0 1 0 3 2 0 3 3 8 11 4 1 5 3 0 45 TOTAL 1019 544 368 314 392 263 216 270 541 820 1195 549 404 424 503 739 8561 TOTAL NUMBER OF OBSERVATIONS: 8568 TOTAL NUMBER OF VALID OBSERVATIONS: 8561 TOTAL NUMBER OF MISSING OBSERVATIONS: 7 PERCENT DATA RECOVERY FOR THIS PERIOD: 99.9 %

MEAN WIND SPEED FOR THIS PERIOD: 6.7 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 8.78 6.56 6.46 19.09 19.67 14.24 25.20 DISTRIBUTION OF WIND DIRECTION VS STABILITY N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 4 6 16 20 30 56 35 61 115 109 143 61 39 24 19 14 0 B 3 11 19 33 35 31 23 44 85 86 104 43 20 12 5 8 0 C 10 15 37 28 43 19 21 34 84 94 81 28 22 11 11 15 0 D 78 81 101 80 124 58 58 65 147 203 275 116 86 58 43 61 0 E 98 79 65 59 124 60 29 37 74 191 358 153 89 103 91 74 0 F 114 71 62 47 20 14 25 15 22 111 198 110 83 98 114 115 0 G 712 281 68 47 16 25 25 14 14 26 36 38 65 118 220 452 0 TOTAL 1019 544 368 314 392 263 216 270 541 820 1195 549 404 424 503 739 0 PVNGS 2016 ARERR Page 78

APPENDIX C DOSE CALCULATIONS PVNGS 2016 ARERR Page 79

GASEOUS EFFLUENT DOSE CALCULATIONS Doses to the maximum individual and the surrounding population resulting from the release of radioactive material in gaseous effluents from the Palo Verde Nuclear Generating Station were calculated using the GASPAR computer program. The radionuclides considered in the dose calculations were tritium, iodine-131, iodine-132, iodine-133, iodine-135, all noble gases, and particulates having a half-life greater than eight days and for which dose factors are contained in NUREG-0172. Locations selected for individual dose calculations included for each sector, the site boundary, and within five miles, if present, the nearest residence, the nearest garden, and the nearest milk animal. GASPAR implements the radiological dose models of Regulatory Guide 1.109 to determine the radiation exposure to man from four principal atmospheric exposure pathways:

plume, ground deposition, inhalation, and ingestion. Doses to the maximum individual and the population were calculated as a function of age group and pathway for significant body organs.

Table 43 presents the doses on a quarterly, semiannual and annual basis for the Energy Information Center. An occupancy factor of 1.0 (implying continuous occupancy over the entire year) was considered for the Energy Information Center and the exposure pathways considered to calculate its doses were plume, ground deposition, and inhalation. Dose to the special location for 2016 was 1.65 millirem. This is well within the 25 mrem/yr limit of 40 CFR 190.

Table 44 presents the population dose.

Table 45 summarizes the individual doses and compares the result to PVNGS ODCM Requirement limits. The site boundary and residence locations for which data are presented represent the highest annual doses.

Based on results obtained by placing TLDs on the site boundary in each sector, the net dose for this reporting period, from direct-radiation, (plume and ground deposition) from all three units was indistinguishable from preoperational values of 8 - 14 R/hr (17 - 30 mR/Std Qtr).

There were no liquid effluents associated with the operation of this facility.

PVNGS 2016 ARERR Page 80

Dose Calculation Models The GASPAR computer code was used to evaluate the radiological consequences of the routine release of gaseous effluents. GASPAR implements the dose calculational methodologies of Regu-latory Guide 1.109, Revision 1.

Source terms for each quarter are combined with station-specific demographic data and each quarters atmospheric diffusion estimates for gaseous dose calculations.

Atmospheric diffusion estimates are generated by the XOQDOQ computer code using onsite meteorological data as input. Additional input to GASPAR includes the following site-specific data:

0 to 5 mile nearest residence, milk animal and garden in each of the 16 compass sectors, based on the 2016 Land Use Census.

0 to 10 mile population from the PVNGS Emergency Plan, Rev 47.

The 10 to 50 mile population distribution from the PVNGS UFSAR, Figure 2.1-12.

The population distribution of metropolitan Phoenix greater than 50 miles from PVNGS, based on the 1980 federal census results, is conservatively included in the 40 to 50 mile sectors (NE=123; ENE=140,097; E=621,130; ESE=8,392).

Absolute humidity of 6.0 g/m3 from the PVNGS UFSAR, Table 2.3-16.

The fraction of the year that vegetables are grown (0.667) from the PVNGS ER-OL, Section 2.1.3.4, Table 2.1-8.

The fraction of daily feed derived from pasture while on pasture (0.35) and length of grazing season for milk animals beyond 5 miles (0.75) from the PVNGS ER-OL, Section 2.1.3.4.3.

The fraction of daily feed derived from pasture while on pasture (0.05) and length of grazing season for meat animals (0.25) from the PVNGS ER-OL, Section 2.1.3.4.4.

There were three (3) sectors containing milk animal (goat or cow) locations within five (5) miles. For calculation purposes these milk animals are assumed to be fed 100% on pasture grass during the year.

Other values used for input to GASPAR are default values from Regulatory Guide 1.109, Rev. 1.

PVNGS 2016 ARERR Page 81

Table 43:

Doses To Special Locations For 2016 ENERGY INFORMATION CENTER LOCATED ONSITE 0.45 MILE S FROM UNIT 1, 0.29 MILE SSE FROM UNIT 2 AND 0.20 MILE ESE FROM UNIT 3.

(MREM) T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN 1ST QUARTER ADULT 6.71E-01 6.71E-01 1.22E-03 6.71E-01 6.71E-01 6.71E-01 6.71E-01 6.71E-01 TEEN 6.75E-01 6.75E-01 1.22E-03 6.75E-01 6.75E-01 6.75E-01 6.75E-01 6.76E-01 CHILD 5.97E-01 5.97E-01 1.22E-03 5.97E-01 5.97E-01 5.97E-01 5.97E-01 5.98E-01 INFANT 3.44E-01 3.44E-01 1.22E-03 3.44E-01 3.44E-01 3.44E-01 3.44E-01 3.44E-01 2ND QUARTER ADULT 1.95E-01 1.95E-01 9.72E-03 1.95E-01 1.95E-01 1.95E-01 1.97E-01 1.97E-01 TEEN 1.97E-01 1.97E-01 9.72E-03 1.97E-01 1.97E-01 1.97E-01 2.01E-01 1.99E-01 CHILD 1.75E-01 1.75E-01 9.72E-03 1.75E-01 1.75E-01 1.75E-01 1.78E-01 1.77E-01 INFANT 1.05E-01 1.05E-01 9.72E-03 1.05E-01 1.05E-01 1.05E-01 1.07E-01 1.07E-01 1ST SEMI-ANNUAL ADULT 8.66E-01 8.66E-01 1.09E-02 8.66E-01 8.66E-01 8.66E-01 8.68E-01 8.69E-01 TEEN 8.72E-01 8.72E-01 1.09E-02 8.72E-01 8.72E-01 8.72E-01 8.76E-01 8.75E-01 CHILD 7.72E-01 7.72E-01 1.09E-02 7.72E-01 7.72E-01 7.72E-01 7.75E-01 7.75E-01 INFANT 4.49E-01 4.49E-01 1.09E-02 4.49E-01 4.49E-01 4.49E-01 4.50E-01 4.51E-01 3RD QUARTER ADULT 2.30E-01 2.30E-01 3.39E-04 2.30E-01 2.30E-01 2.30E-01 2.30E-01 2.31E-01 TEEN 2.32E-01 2.32E-01 3.39E-04 2.32E-01 2.32E-01 2.32E-01 2.32E-01 2.32E-01 CHILD 2.05E-01 2.05E-01 3.39E-04 2.05E-01 2.05E-01 2.05E-01 2.05E-01 2.05E-01 INFANT 1.18E-01 1.18E-01 3.39E-04 1.18E-01 1.18E-01 1.18E-01 1.18E-01 1.18E-01 4TH QUARTER ADULT 5.56E-01 5.56E-01 2.08E-03 5.56E-01 5.56E-01 5.56E-01 5.56E-01 5.56E-01 TEEN 5.60E-01 5.60E-01 2.08E-03 5.60E-01 5.60E-01 5.60E-01 5.60E-01 5.60E-01 CHILD 4.95E-01 4.95E-01 2.08E-03 4.95E-01 4.95E-01 4.96E-01 4.96E-01 4.95E-01 INFANT 2.86E-01 2.86E-01 2.08E-03 2.86E-01 2.86E-01 2.86E-01 2.86E-01 1.29E-01 2ND SEMI-ANNUAL ADULT 7.86E-01 7.86E-01 2.42E-03 7.86E-01 7.86E-01 7.86E-01 7.86E-01 7.86E-01 TEEN 7.92E-01 7.92E-01 2.42E-03 7.92E-01 7.92E-01 7.92E-01 7.92E-01 7.92E-01 CHILD 7.00E-01 7.00E-01 2.42E-03 7.00E-01 7.00E-01 7.01E-01 7.01E-01 6.99E-01 INFANT 4.04E-01 4.04E-01 2.42E-03 4.04E-01 4.04E-01 4.04E-01 4.04E-01 2.47E-01 ANNUAL ADULT 1.65E+00 1.65E+00 1.34E-02 1.65E+00 1.65E+00 1.65E+00 1.65E+00 1.65E+00 TEEN 1.66E+00 1.66E+00 1.34E-02 1.66E+00 1.66E+00 1.66E+00 1.67E+00 1.67E+00 CHILD 1.47E+00 1.47E+00 1.34E-02 1.47E+00 1.47E+00 1.47E+00 1.48E+00 1.47E+00 INFANT 8.52E-01 8.52E-01 1.34E-02 8.52E-01 8.52E-01 8.52E-01 8.54E-01 6.98E-01 PVNGS 2016 ARERR Page 82

Table 44:

Integrated Population Dose for 2016 January through March PLUME 1.20E-04 1.20E-04 1.20E-04 1.20E-04 1.20E-04 1.20E-04 1.20E-04 2.23E-04 0.00% 0.00% 90.84% 0.00% 0.00% 0.00% 0.00% 0.00%

GROUND 1.21E-05 1.21E-05 1.21E-05 1.21E-05 1.21E-05 1.21E-05 1.21E-05 1.42E-05 0.00% 0.00% 9.16% 0.00% 0.00% 0.00% 0.00% 0.00%

INHAL 2.15E+00 2.15E+00 < LLD 2.15E+00 2.15E+00 2.15E+00 2.15E+00 2.15E+00 25.83% 25.83% 0.00% 25.83% 25.83% 25.83% 25.83% 25.83%

VEGET 5.33E+00 5.33E+00 < LLD 5.33E+00 5.33E+00 5.33E+00 5.33E+00 5.33E+00 64.04% 64.04% 0.00% 64.04% 64.04% 64.04% 64.04% 64.04%

COW MILK 5.79E-01 5.79E-01 < LLD 5.79E-01 5.79E-01 5.79E-01 5.79E-01 5.79E-01 6.96% 6.96% 0.00% 6.96% 6.96% 6.96% 6.96% 6.96%

MEAT 2.64E-01 2.64E-01 < LLD 2.64E-01 2.64E-01 2.64E-01 2.64E-01 2.64E-01 3.17% 3.17% 0.00% 3.17% 3.17% 3.17% 3.17% 3.17%

  • TOTAL* 8.33E+00 8.33E+00 1.32E-04 8.33E+00 8.33E+00 8.33E+00 8.33E+00 8.33E+00 PER CAPITA DOSE (REM) 4.25E-06 4.25E-06 6.74E-11 4.25E-06 4.25E-06 4.25E-06 4.25E-06 4.25E-06 April through June PLUME 1.87E-04 1.87E-04 1.87E-04 1.87E-04 1.87E-04 1.87E-04 1.87E-04 4.23E-04 0.01% 0.01% 2.48% 0.01% 0.01% 0.01% 0.01% 0.02%

GROUND 7.29E-03 7.29E-03 7.29E-03 7.29E-03 7.29E-03 7.29E-03 7.29E-03 8.57E-03 0.26% 0.26% 96.94% 0.26% 0.26% 0.26% 0.26% 0.31%

INHAL 8.24E-01 8.24E-01 2.14E-05 8.24E-01 8.24E-01 8.24E-01 8.30E-01 8.24E-01 29.90% 29.89% 0.28% 29.90% 29.90% 29.90% 30.05% 29.88%

VEGET 1.65E+00 1.66E+00 2.11E-05 1.65E+00 1.65E+00 1.65E+00 1.65E+00 1.65E+00 60.04% 60.05% 0.28% 60.04% 60.04% 60.04% 59.91% 60.01%

COW 2.08E-01 2.08E-01 5.34E-07 2.08E-01 2.08E-01 2.08E-01 2.08E-01 2.08E-01 7.56% 7.56% 0.01% 7.56% 7.56% 7.56% 7.55% 7.56%

MEAT 6.14E-02 6.14E-02 3.47E-07 6.14E-02 6.14E-02 6.14E-02 6.14E-02 6.14E-02 2.23% 2.23% 0.00% 2.23% 2.23% 2.23% 2.22% 2.23%

  • TOTAL* 2.76E+00 2.76E+00 7.52E-03 2.76E+00 2.75E+00 2.76E+00 2.76E+00 2.76E+00 PER CAPITA DOSE (REM) 1.41E-06 1.41E-06 3.84E-09 1.41E-06 1.40E-06 1.41E-06 1.41E-06 1.41E-06 PVNGS 2016 ARERR Page 83

Table 44: (continued) Integrated Population Dose for 2016 January through June PLUME 3.07E-04 3.07E-04 3.07E-04 3.07E-04 3.07E-04 3.07E-04 3.07E-04 6.45E-04 0.00% 0.00% 4.01% 0.00% 0.00% 0.00% 0.00% 0.01%

GROUND 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 8.59E-03 0.07% 0.07% 95.42% 0.07% 0.07% 0.07% 0.07% 0.08%

INHAL 2.97E+00 2.98E+00 2.14E-05 2.97E+00 2.97E+00 2.98E+00 2.98E+00 2.97E+00 26.84% 26.84% 0.28% 26.84% 26.84% 26.84% 26.88% 26.84%

VEGET 6.99E+00 6.99E+00 2.11E-05 6.99E+00 6.99E+00 6.99E+00 6.99E+00 6.99E+00 63.04% 63.05% 0.28% 63.04% 63.04% 63.04% 63.01% 63.03%

COW 7.88E-01 7.88E-01 5.34E-07 7.88E-01 7.88E-01 7.88E-01 7.88E-01 7.88E-01 7.11% 7.10% 0.01% 7.11% 7.11% 7.11% 7.10% 7.10%

MEAT 3.26E-01 3.26E-01 3.47E-07 3.26E-01 3.26E-01 3.26E-01 3.26E-01 3.26E-01 2.94% 2.94% 0.00% 2.94% 2.94% 2.94% 2.94% 2.94%

  • TOTAL* 1.11E+01 1.11E+01 7.65E-03 1.11E+01 1.11E+01 1.11E+01 1.11E+01 1.11E+01 PER CAPITA DOSE (REM) 5.67E-06 5.67E-06 3.91E-09 5.67E-06 5.67E-06 5.67E-06 5.67E-06 5.67E-06 July through September PLUME 6.45E-05 6.45E-05 6.45E-05 6.45E-05 6.45E-05 6.45E-05 6.45E-05 1.19E-04 0.00% 0.00% 99.59% 0.00% 0.00% 0.00% 0.00% 0.00%

GROUND 2.66E-07 2.66E-07 2.66E-07 2.66E-07 2.66E-07 2.66E-07 2.66E-07 3.11E-07 0.00% 0.00% 0.41% 0.00% 0.00% 0.00% 0.00% 0.00%

INHAL 8.81E-01 8.81E-01 < LLD 8.81E-01 8.81E-01 8.81E-01 8.81E-01 8.81E-01 29.86% 29.86% 0.00% 29.86% 29.86% 29.86% 29.86% 29.86%

VEGET 1.78E+00 1.78E+00 < LLD 1.78E+00 1.78E+00 1.78E+00 1.78E+00 1.78E+00 60.44% 60.44% 0.00% 60.44% 60.44% 60.44% 60.44% 60.44%

COW 2.14E-01 2.14E-01 < LLD 2.14E-01 2.14E-01 2.14E-01 2.14E-01 2.14E-01 7.27% 7.27% 0.00% 7.27% 7.27% 7.27% 7.27% 7.27%

MEAT 7.19E-02 7.19E-02 < LLD 7.19E-02 7.19E-02 7.19E-02 7.19E-02 7.19E-02 2.44% 2.44% 0.00% 2.44% 2.44% 2.44% 2.44% 2.44%

  • TOTAL* 2.95E+00 2.95E+00 6.47E-05 2.95E+00 2.95E+00 2.95E+00 2.95E+00 2.95E+00 PER CAPITA DOSE (REM) 1.51E-06 1.51E-06 3.30E-11 1.51E-06 1.51E-06 1.51E-06 1.51E-06 1.51E-06 PVNGS 2016 ARERR Page 84

Table 44: (continued) Integrated Population Dose for 2016 October through December PLUME 1.11E-04 1.11E-04 1.11E-04 1.11E-04 1.11E-04 1.11E-04 1.11E-04 2.49E-04 0.00% 0.00% 31.22% 0.00% 0.00% 0.00% 0.00% 0.00%

GROUND 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.77E-04 0.00% 0.00% 66.34% 0.00% 0.00% 0.00% 0.00% 0.00%

INHAL 2.41E+00 2.41E+00 6.97E-06 2.41E+00 2.41E+00 2.42E+00 2.41E+00 2.41E+00 27.37% 27.37% 1.97% 27.37% 27.37% 27.37% 27.37% 27.37%

VEGET 5.48E+00 5.48E+00 1.50E-06 5.48E+00 5.48E+00 5.48E+00 5.48E+00 5.48E+00 62.11% 62.11% 0.42% 62.11% 62.11% 62.10% 62.10% 62.11%

COW MILK 6.71E-01 6.71E-01 1.59E-07 6.71E-01 6.71E-01 6.71E-01 6.71E-01 6.71E-01 7.61% 7.61% 0.04% 7.61% 7.61% 7.61% 7.61% 7.61%

MEAT 2.57E-01 2.57E-01 2.06E-09 2.57E-01 2.57E-01 2.57E-01 2.57E-01 2.57E-01 2.92% 2.92% 0.00% 2.92% 2.92% 2.92% 2.92% 2.92%

  • TOTAL* 8.82E+00 8.82E+00 3.54E-04 8.82E+00 8.82E+00 8.82E+00 8.82E+00 8.82E+00 PER CAPITA DOSE (REM) 4.50E-06 4.50E-06 1.81E-10 4.50E-06 4.50E-06 4.50E-06 4.50E-06 4.50E-06 July through December PLUME 1.75E-04 1.75E-04 1.75E-04 1.75E-04 1.75E-04 1.75E-04 1.75E-04 3.68E-04 0.00% 0.00% 41.78% 0.00% 0.00% 0.00% 0.00% 0.00%

GROUND 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.77E-04 0.00% 0.00% 56.16% 0.00% 0.00% 0.00% 0.00% 0.00%

INHAL 3.30E+00 3.30E+00 6.97E-06 3.30E+00 3.30E+00 3.30E+00 3.30E+00 3.30E+00 27.99% 27.99% 1.66% 27.99% 27.99% 27.99% 27.99% 27.99%

VEGET 7.26E+00 7.26E+00 1.50E-06 7.26E+00 7.26E+00 7.26E+00 7.26E+00 7.26E+00 61.69% 61.69% 0.36% 61.69% 61.69% 61.69% 61.69% 61.69%

COW 8.85E-01 8.85E-01 1.59E-07 8.85E-01 8.85E-01 8.86E-01 8.85E-01 8.85E-01 7.52% 7.52% 0.04% 7.52% 7.52% 7.52% 7.52% 7.52%

MEAT 3.29E-01 3.29E-01 2.06E-09 3.29E-01 3.29E-01 3.29E-01 3.29E-01 3.29E-01 2.80% 2.80% 0.00% 2.80% 2.80% 2.80% 2.80% 2.80%

  • TOTAL* 1.18E+01 1.18E+01 4.19E-04 1.18E+01 1.18E+01 1.18E+01 1.18E+01 1.18E+01 PER CAPITA DOSE (REM) 6.02E-06 6.02E-06 2.14E-10 6.02E-06 6.02E-06 6.02E-06 6.02E-06 6.02E-06 PVNGS 2016 ARERR Page 85

Table 44: (continued)

Integrated Population Dose for 2016 January through December PLUME 4.82E-04 4.82E-04 4.82E-04 4.82E-04 4.82E-04 4.82E-04 4.82E-04 1.01E-03 0.00% 0.00% 5.97% 0.00% 0.00% 0.00% 0.00% 0.00%

GROUND 7.54E-03 7.54E-03 7.54E-03 7.54E-03 7.54E-03 7.54E-03 7.54E-03 8.86E-03 0.03% 0.03% 93.39% 0.03% 0.03% 0.03% 0.03% 0.04%

6.27E+0 6.27E+0 6.27E+0 6.27E+0 6.27E+0 INHAL 0 0 2.84E-05 6.27E+00 0 0 6.28E+00 0 27.43% 27.43% 0.35% 27.43% 27.43% 27.44% 27.45% 27.43%

1.43E+0 1.43E+0 1.43E+0 1.43E+0 1.43E+0 VEGET 1 1 2.26E-05 1.43E+01 1 1 1.43E+01 1 62.35% 62.35% 0.28% 62.35% 62.35% 62.34% 62.33% 62.34%

1.67E+0 1.67E+0 1.67E+0 1.67E+0 1.67E+0 COW 0 0 6.93E-07 1.67E+00 0 0 1.67E+00 0 7.32% 7.32% 0.01% 7.32% 7.32% 7.32% 7.32% 7.32%

MEAT 6.55E-01 6.55E-01 3.49E-07 6.55E-01 6.55E-01 6.55E-01 6.55E-01 6.55E-01 2.87% 2.87% 0.00% 2.87% 2.87% 2.87% 2.86% 2.87%

2.29E+0 2.29E+0 2.29E+0 2.29E+0 2.29E+0

  • TOTAL*

1 1 8.07E-03 2.29E+01 1 1 2.29E+01 1 PER CAPITA DOSE (REM) 1.17E-05 1.17E-05 4.12E-09 1.17E-05 1.17E-05 1.17E-05 1.17E-05 1.17E-05 PVNGS 2016 ARERR Page 86

Table 45:

Summary of Individual Doses for 2016 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Air Dose mrad 5.07E-04 3.29E-04 1.23E-04 3.72E-04 1.17E-03 ODCM Req. 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit  % 1.01E-02 6.58E-03 2.46E-03 7.44E-03 1.17E-02 Beta Air Dose mrad 1.82E-04 1.41E-04 4.46E-05 1.49E-04 4.53E-04 ODCM Req. 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit  % 1.82E-03 1.41E-03 4.46E-04 1.49E-03 2.27E-03 Maximum Individual Total Body mrem 3.37E-04 2.18E-04 8.14E-05 2.47E-04 7.78E-04 Skin mrem 5.41E-04 3.57E-04 1.31E-04 3.99E-04 1.26E-03 Site Boundary Location Unit 1 miles 1.70 SSE 0.78 NW 1.40 SSW 1.70 SSE 1.70 SSE Unit 2 miles 1.88 SSE 0.74 NW 1.14 SSW 1.88 SSE 1.88 SSE Unit 3 miles 1.73 SSE 0.65 NW 1.00 SSW 1.73 SSE 1.73 SSE Age Infant Infant Infant Teen Teen Maximum Organ Dose Organ (excluding skin) Bone Bone Bone Thyroid (2) Lung mrem 1.85E-01 1.01E-01 7.94E-02 1.90E-01 4.86E-01 ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit (1)  % 2.47E+00 1.35E+00 1.06E+00 2.53E+00 3.24E+00 Location Unit 1 miles 2.84 NNE 2.84 NNE 2.84 NNE 2.74 S 2.74 S Unit 2 miles 3.05 NNE 3.05 NNE 3.05 NNE 2.56 S 2.56 S Unit 3 miles 3.28 NNE 3.28 NNE 3.28 NNE 2.35 S 2.35 S Maximum Organ Dose Age Teen Infant Teen Teen Teen excluding C-14 (3) Organ Thyroid (2) Thyroid Thyroid (2) Thyroid (2) Lung (excluding skin) mrem 1.74E-01 4.88E-02 7.41E-02 1.90E-01 4.86E-01 ODCM Req. 4.2 Limit 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit (1) 2.32E+00 6.51E-01 9.88E-01 2.53E+00 3.24E+00 Organ dose from tritium only for Unit 2 location mrem above 1.74E-01 4.72E-02 7.41E-02 1.90E-01 4.84E-01 Fraction of organ dose from tritium only for Unit 2 location  % 100.00% 96.72% 100.00% 100.00% 99.59%

above(2,3)

X/Q for Unit 2 location above sec/m3 8.75E-07 4.73E-07 3.76E-07 7.96E-06 5.16E-06 D/Q for Unit 2 location above m-2 1.31E-09 1.82E-09 1.61E-09 2.58E-09 1.86E-09 Note 1: ODCM Requirement 5.1 has higher limits than ODCM Requirement 4.2, therefore the percent of limits are more conservative based on ODCM Requirement 4.2 than on ODCM Requirement 5.1.

Note 2: All organs except bone Note 3 Refer to discussion in section 10.4 PVNGS 2016 ARERR Page 87

APPENDIX D NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING PVNGS 2016 ARERR Page 88

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APP^

AERIALPHOTO: HELICOPTER PHOTOS, F EXPLANATION PVNGS Well Locations and Aquifer Monitored A StiallowAquiferWell 85-Acre WSR Piezometer FIGURE 1 A Palo Verde Clay Aquifer Well SITE MAP Brown AND,1 A RegionalAquiferWell PVNGS Boundary PALO VERDE NUCLEAR GENERATING STATION Caldwell ARIZONA PUBLIC SERVICES PVNGS2016ARERR Page 89

Repo Det Locati Parameter Report rt ect Sample Field Sample ID on ID Sample Date Name Result Units ed Purpose PV-APP-10-0216 APP-10 02/04/2016 Tritium < 303 pCi/L N REG PV-APP-10-0216 APP-10 02/04/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-10-0216 APP-10 02/04/2016 Cobalt-60 < 2.0 pCi/L N REG PV-APP-10-0216 APP-10 02/04/2016 Cesium-134 < 2.1 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Tritium < 287 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Cesium-137 < 2.1 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-10-0516 APP-10 05/26/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Tritium < 288 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Cesium-137 < 1.5 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Cobalt-60 < 0.5 pCi/L N REG PV-APP-10-0916 APP-10 09/21/2016 Cesium-134 < 1.3 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Tritium < 308 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Cesium-137 < 1.5 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Cobalt-60 < 0.7 pCi/L N REG PV-APP-10-1116 APP-10 11/16/2016 Cesium-134 < 1.0 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Tritium < 303 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-12-0216 APP-12 02/04/2016 Cesium-134 < 1.6 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Tritium < 287 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-12-0516 APP-12 05/26/2016 Cesium-134 < 1.5 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Tritium < 288 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Cesium-137 < 0.8 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Cobalt-60 < 0.5 pCi/L N REG PV-APP-12-0916 APP-12 09/21/2016 Cesium-134 < 1.1 pCi/L N REG PV-APP-12-1116 APP-12 11/08/2016 Tritium < 289 pCi/L N PV-APP-12-1116 APP-12 11/08/2016 Cesium-137 < 1.0 pCi/L N PV-APP-12-1116 APP-12 11/08/2016 Cobalt-60 < 1.2 pCi/L N PV-APP-12-1116 APP-12 11/08/2016 Cesium-134 < 10.0 pCi/L N PV-APP-15-0216 APP-15 02/01/2016 Tritium < 242 pCi/L N REG PV-APP-15-0216 APP-15 02/01/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-15-0216 APP-15 02/01/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-15-0216 APP-15 02/01/2016 Cesium-134 < 1.4 pCi/L N REG PV-APP-15-1016 APP-15 10/04/2016 Tritium < 288.0 pCi/L N PV-APP-15-1016 APP-15 10/04/2016 Cesium-137 < 1.4 pCi/L N PV-APP-15-1016 APP-15 10/04/2016 Cobalt-60 < 1.1 pCi/L N PV-APP-15-1016 APP-15 10/04/2016 Cesium-134 < 1.0 pCi/L N PV-APP-18-0316 APP-18 03/16/2016 Tritium < 287 pCi/L N REG PVNGS 2016 ARERR Page 90

PV-APP-18-0316 APP-18 03/16/2016 Cesium-137 < 3.4 pCi/L N REG PV-APP-18-0316 APP-18 03/16/2016 Cobalt-60 < 1.3 pCi/L N REG PV-APP-18-0316 APP-18 03/16/2016 Cesium-134 < 2.8 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Tritium < 285 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Cesium-137 < 0.9 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Cobalt-60 < 0.3 pCi/L N REG PV-APP-18-1116 APP-18 11/02/2016 Cesium-134 < 1.0 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Tritium < 303 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Cesium-137 < 1.1 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-19-0216 APP-19 02/03/2016 Cesium-134 < 2.1 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Tritium < 308 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Cesium-137 < 0.5 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Cobalt-60 < 0.8 pCi/L N REG PV-APP-19-1116 APP-19 11/16/2016 Cesium-134 < 1.0 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Tritium < 303 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Cesium-137 < 1.4 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-20-0216 APP-20 02/10/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Tritium < 285 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Cesium-137 < 1.1 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Cobalt-60 < 1.0 pCi/L N REG PV-APP-20-1116 APP-20 11/02/2016 Cesium-134 < 0.8 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Tritium < 303 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Cesium-137 < 1.2 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Cobalt-60 < 1.5 pCi/L N REG PV-APP-21-0216 APP-21 02/10/2016 Cesium-134 < 1.2 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Tritium < 285 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Cesium-137 < 0.9 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Cobalt-60 < 1.0 pCi/L N REG PV-APP-21-1116 APP-21 11/02/2016 Cesium-134 < 0.9 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Tritium < 299 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Cesium-137 < 1.2 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-22-0216 APP-22 02/22/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-22-1016 APP-22 10/04/2016 Tritium < 288 pCi/L N PV-APP-22-1016 APP-22 10/04/2016 Cesium-137 < 1.4 pCi/L N PV-APP-22-1016 APP-22 10/04/2016 Cobalt-60 < 0.8 pCi/L N PV-APP-22-1016 APP-22 10/04/2016 Cesium-134 < 1.0 pCi/L N PV-APP-23-0216 APP-23 02/10/2016 Tritium < 303 pCi/L N REG PV-APP-23-0216 APP-23 02/10/2016 Cesium-137 < 1.3 pCi/L N REG PV-APP-23-0216 APP-23 02/10/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-23-0216 APP-23 02/10/2016 Cesium-134 < 1.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Tritium < 288 pCi/L N REG PVNGS 2016 ARERR Page 91

PV-APP-23-1016 APP-23 10/12/2016 Cesium-137 < 0.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Cobalt-60 < 0.8 pCi/L N REG PV-APP-23-1016 APP-23 10/12/2016 Cesium-134 < 0.7 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Tritium < 303 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-3-0216 APP-3 02/11/2016 Cesium-134 < 1.7 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Tritium < 303 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Cesium-137 < 1.1 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-4R-0216 APP-4R 02/11/2016 Cesium-134 < 2.7 pCi/L N REG PV-APP-4R-1116 APP-4R 11/01/2016 Tritium < 285 pCi/L N PV-APP-4R-1116 APP-4R 11/01/2016 Cesium-137 < 1.7 pCi/L N PV-APP-4R-1116 APP-4R 11/01/2016 Cobalt-60 < 0.3 pCi/L N PV-APP-4R-1116 APP-4R 11/01/2016 Cesium-134 < 1.4 pCi/L N PV-APP-5-0216 APP-5 02/23/2016 Tritium < 299 pCi/L N REG PV-APP-5-0216 APP-5 02/23/2016 Cesium-137 < 1.8 pCi/L N REG PV-APP-5-0216 APP-5 02/23/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-5-0216 APP-5 02/23/2016 Cesium-134 < 2.9 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Tritium < 303 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Cobalt-60 < 1.5 pCi/L N REG PV-APP-7-0216 APP-7 02/09/2016 Cesium-134 < 1.9 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Tritium < 303 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-9-0216 APP-9 02/04/2016 Cesium-134 < 2.8 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Tritium < 287 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Cesium-137 < 1.0 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Cobalt-60 < 1.4 pCi/L N REG PV-APP-9-0516 APP-9 05/26/2016 Cesium-134 < 2.4 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Tritium < 288 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Cesium-137 < 1.7 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Cobalt-60 < 0.9 pCi/L N REG PV-APP-9-0916 APP-9 09/21/2016 Cesium-134 < 1.6 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Tritium < 308 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Cesium-137 < 1.3 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Cobalt-60 < 0.7 pCi/L N REG PV-APP-9-1116 APP-9 11/18/2016 Cesium-134 < 1.7 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Tritium < 242 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cesium-137 < 1.0 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cobalt-60 < 1.4 pCi/L N REG PV-PV-14H-0216 PV-14H 02/01/2016 Cesium-134 < 1.6 pCi/L N REG PV-PV-14H-1016 PV-14H 10/04/2016 Tritium < 288 pCi/L N PVNGS 2016 ARERR Page 92

PV-PV-14H-1016 PV-14H 10/04/2016 Cesium-137 < 0.8 pCi/L N PV-PV-14H-1016 PV-14H 10/042016 Cobalt-60 < 0.8 pCi/L N PV-PV-14H-1016 PV-14H 10/04/2016 Cesium-134 < 0.8 pCi/L N PV-PV-PV-195A-0216 195A 02/01/2016 Tritium < 242 pCi/L N REG PV-PV-PV-195A-0216 195A 02/01/2016 Cesium-137 < 2.1 pCi/L N REG PV-PV-PV-195A-0216 195A 02/01/2016 Cobalt-60 < 1.4 pCi/L N REG PV-PV-PV-195A-0216 195A 02/01/2016 Cesium-134 < 1.3 pCi/L N REG PV-PV-PV-195A-1016 195A 10/04/2016 Tritium < 288 pCi/L N PV-PV-PV-195A-1016 195A 10/04/2016 Cesium-137 < 0.3 pCi/L N PV-PV-PV-195A-1016 195A 10/04/2016 Cobalt-60 < 0.7 pCi/L N PV-PV-PV-195A-1016 195A 10/04/2016 Cesium-134 < 1.0 pCi/L N PV-PV-PV-198AR-0316 198AR 03/16/2016 Tritium < 287 pCi/L N REG PV-PV-PV-198AR-0316 198AR 03/16/2016 Cesium-137 < 3.1 pCi/L N REG PV-PV-PV-198AR-0316 198AR 03/16/2016 Cobalt-60 < 1.3 pCi/L N REG PV-PV-PV-198AR-0316 198AR 03/16/2016 Cesium-134 < 1.6 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Tritium < 299 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Cesium-137 < 1.0 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Cobalt-60 < 1.4 pCi/L N REG PV-PV-34H-0216 PV-34H 02/23/2016 Cesium-134 < 1.8 pCi/L N REG PV-PV-PV-R2AR-0216 R2AR 02/03/2016 Tritium < 303 pCi/L N REG PV-PV-PV-R2AR-0216 R2AR 02/03/2016 Cesium-137 < 1.0 pCi/L N REG PV-PV-PV-R2AR-0216 R2AR 02/03/2016 Cobalt-60 < 1.4 pCi/L N REG PV-PV-PV-R2AR-0216 R2AR 02/03/2016 Cesium-134 < 1.9 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR 10/12/2016 Tritium < 288 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR 10/12/2016 Cesium-137 < 0.5 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR 10/12/2016 Cobalt-60 < 0.5 pCi/L N REG PV-PV-PV-R2AR-1016 R2AR 10/12/2016 Cesium-134 < 0.5 pCi/L N REG PV-PV-PV-193A-1116 193A 11/08/2016 Tritium < 289 pCi/L N PVNGS 2016 ARERR Page 93

PV-PV-PV-193A-1116 193A 11/08/2016 Cesium-137 < 0.8 pCi/L N PV-PV-PV-193A-1116 193A 11/08/2016 Cobalt-60 < 0.2 pCi/L N PV-PV-PV-193A-1116 193A 11/08/2016 Cesium-134 < 0.9 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Tritium < 289 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Cesium-137 < 1.7 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Cobalt-60 < 1.9 pCi/L N PV-PV-Q8-1116 PV-Q8 11/08/2016 Cesium-134 < 1.6 pCi/L N PVNGS 2016 ARERR Page 94

APPENDIX E 2015 ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT CORRECTION PVNGS 2016 ARERR Page 95

OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 REVISION 27 McDowell, Digitally signed by McDowell, Joshua (Z08270)

Joshua DN: cn=McDowell, Joshua (Z08270)

Reason: I am the author of this document Originator (Z08270) Date: 2016.03.29 13:47:09 -07'00' Digitally signed by Routolo, Robert Routolo, Robert M(Z99739)

DN: cn=Routolo, Robert M(Z99739)

M(Z99739)

Reason: I have reviewed this document Date: 2016.03.24 10:42:46 -07'00' Technical Reviewer______________________________________

Digitally signed by Moeller, Moeller, Carl Carl (Z09119)

DN: cn=Moeller, Carl Director, Radiation (Z09119)

(Z09119)

Date: 2016.03.25 06:25:14 Protection -07'00' Digitally signed by McGhee, Mark McGhee, Mark DN: A(Z65028) cn=McGhee, Mark A(Z65028)

A(Z65028) Reason: PRB Chairman Approval Date: 2016.03.24 11:39:05 -07'00' PRB ______________________________________

03/25/2016 Effective Date:

TABLE OF CONTENTS TITLE PAGE

1.0 INTRODUCTION

1 1.1 Liquid Effluent Pathways 1 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 (QSITE) 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

4.4 Requirements

Liquid Effluents 57 4.4.1 Surveillance Requirements 57 4.4.2 Implementation of the Requirements 57 i ODCM Rev. 27

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. 27

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 iii ODCM Rev. 27

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 l 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. 27

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 10 - 35 Miles 78 6-3 Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED 79 6-4 Site Exclusion Area Boundary DELETED 80 6-5 Gaseous Effluent Release Points 81 6-6 Low Population Zone DELETED 82 v ODCM Rev. 27

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.

1 ODCM Rev. 27

1.2 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.

1.3 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. 27

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 Outage Support Facility MAR 2016 3 ODCM Rev. 27

1.4 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 X/Q and D/Q are utilized for the particular units releases as applicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathways 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 units 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 units releases as applicable for gases other than noble gases at the controlling pathways 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. 27

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 FUNCTIONAL with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.0 MAR 2016 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 nonfunctional, or change the setpoint so it is acceptably conservative.

MAR 2016

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 2-1. Restore the nonfunctional instrumentation to FUNCTIONAL status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this nonfunctionality was not corrected within MAR 2016 the time specified.

2.1.1 Surveillance Requirements

a. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE MAR 2016 CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2.
b. The specified Frequency for each Surveillance Requirement is met if the Surveillance Requirement is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as Prior to each release, the above interval extension does not apply.

For Frequencies specified as Once the above interval extension does not apply.

If a Completion Time requires periodic performance on a once per . . . basis, the above Frequency extension applies to each performance after the initial performance.

MAR 2016 5 ODCM Rev. 27

TABLE 2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT FUNCTIONAL APPLICABILITY ACTION MAR 2016

1. GASEOUS RADWASTE SYSTEM
a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release #RU-12 1 # 35
b. Flow Rate Monitor 1 # 36
2. NOT USED
3. DELETED
4. PLANT VENT SYSTEM A. Low Range Monitors 6
a. Noble Gas Activity Monitor #RU-143 1
  • 37
b. Iodine Sampler 1
  • 40
c. Particulate Sampler 1
  • 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-144 1
  • 42
b. Iodine Sampler 1
  • 42
c. Particulate Sampler 1
  • 42
d. Sampler Flow Rate Measuring Device 1

TABLE 2-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT FUNCTIONAL 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 ## 40
d. Flow Rate Monitor 1 ## 36
e. Sampler Flow Rate Measuring Device 1 ## 36 B. High Range Monitors 7
a. Noble Gas Activity Monitor #RU-146 1 ## 42
b. Iodine Sampler 1 ## 42
c. Particulate Sample 1 ## 42
d. Sampler Flow Rate Measuring Device 1 ## 42 ODCM Rev. 27

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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, the contents of the tank(s) may be released to the environment MAR 2016 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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the MAR 2016 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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the MAR 2016 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 nonfunctional due to loss of communication with the minicomputer. The surveillance MAR 2016 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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via the effected pathway may continue provided MAR 2016 samples are continuously collected with auxiliary sampling equipment as required in Table 3-1 within one hour after the channel has been declared nonfunctional.

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

MAR 2016 8 ODCM Rev. 27

Table 2-1 (Continued)

TABLE NOTATION ACTION 42 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement initiate the Preplanned Alternate Sampling Program to monitor MAR 2016 the appropriate parameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

a. Either restore the nonfunctional channel(s) to FUNCTIONAL status within 7 days of the MAR 2016 event, or
b. Prepare and submit a Special Report to the Commission within 14 days following the event outlining the action(s) taken, the cause of the nonfunctionality, and the plans and schedule for restoring the system to FUNCTIONAL status.

MAR 2016 9 ODCM Rev. 27

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(1),(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) 10
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. ##
c. Particulate Sample N.A. N.A. N.A. N.A. ##
d. Flow Rate Monitor D(6) N.A. R Q ##

ODCM Rev. 27 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.

11 ODCM Rev. 27

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 Ci/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 (Ci/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. 27

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

K eq = i[ ( Ki ) ( fi ) ] (2-1)

Where:

Keq = the equivalent whole body dose factor weighted by historical radionuclide distribution in releases in mrem/yr per Ci/m3.

Ki = the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per 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 + 1.1M ) eq = i[ ( Li + 1.1Mi ) ( fi ) ] (2-2)

Where:

(L+1.1M)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 Ci/m3.

Li = the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per Ci/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 Ci/m3 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. 27

2.1.2.2 Site Release Rate Limit (QSITE)

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 (QSITE) is the lower of QWB or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded.

The QSITE is established as follows:

( D WB ) ( 0.8 )

Q SITE,WB = ---------------------------------------- (2-3)

( K eq ) ( X/Q )SITE Where:

QSITE,WB = the site release rate, in Ci/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 Ci/m3 weighted by the historical radionuclide distribution.

(X/Q)SITE = 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.

( D SK ) ( 0.8 )

Q SITE,SK = ----------------------------------------------------------- (2-4)

( L + 1.1M ) eq ( X/Q ) SITE Where:

QSITE,SK = the site release rate limit, in Ci/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+1.1M)eq = equivalent skin dose factor, in mrem/yr per Ci/m3, weighted by the radionuclide distribution.

(X/Q)SITE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, 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 QSITE 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. 27

2.1.2.3 Unit Release Rate Limits (QUNIT)

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

QUNIT = (fUNIT) (QSITE) (2-5)

Where:

QUNIT = unit release rate limit, in Ci/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.

QSITE = the site release rate limit, in Ci/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 (QUNIT) 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 ( Q UNIT ) ( a )

- (2-6)

Setpoint ( 472 ) ( Flow Rate )

Where:

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

QUNIT = unit release rate limit, in Ci/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 QUNIT allocated for a specific release point. The sum of these administrative values shall be less than or equal to one.

15 ODCM Rev. 27

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

Monitor [ ( Q UNIT ) ( a ) ( 0.9 ) - ( H ) ( PF ) ( 472 ) ]

(2-7) setpoint ( Flow Rate ) ( 472 )

Where:

Monitor Setpoint = the setpoint for the monitor, in Ci/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 Ci/sec, 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 Ci/cc.

a = fraction of QUNIT 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 feet/minute.

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. 27

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 I-131 and I-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. 27

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:

D WB = i[ ( Ki ) ( X/Q )SITE ( Qi ) ] (3-1)

For skin dose rate:

D SK = i[ ( Li + 1.1Mi ) ( X/Q )SITE ( 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 Ci/m3 from Table 3-3.

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

(X/Q)SITE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, 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 Ci/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 Ci/m3 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. 27

I-131, I-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 = i[ ( Pi ) ( X/Q )SITE ( Qi ) ] (3-3)

Where:

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

(X/Q)SITE = 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, at the Site Boundary, for any of the three units, Qi = the release rate of radionuclide i, in Ci/sec Do = the total organ dose rate (mrem/yr).

19 ODCM Rev. 27

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) (Ci/ml)a A. Waste Gas Storage P P Principal Gamma 1.0E-04 Each Tank Grab Each Tank Emittersg Sample B. Containment Purge P P Principal Gamma 1.0E-04 Each Purgeb,c Each Purgeb,c Emittersg Grab Sample H-3 1.0E-06 C. 1. DELETED Mb,e Mb Principal Gamma 1.0E-04

2. Plant Vent Grab Sample Emittersg
3. Fuel Bldg. Exhaust H-3 1.0E-06 Continuousf 4/Md I-131 1.0E-12 Charcoal Sample I-133 1.0E-10 Continuousf 4/Md Principal Gamma 1.0E-11 Particulate Emittersg Sample (I-131, Others)

Continuousf M Gross Alpha 1.0E-11 Composite Particulate Sample Continuousf Q Sr-89, Sr-90 1.0E-11 Composite Particulate Sample D. All Radwaste Types as Continuousf Noble Gas Noble Gases Gross Beta 1.0E-06 listed in A., B., and C., Monitor or Gamma above.

20 ODCM Rev. 27

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):

4.66 s b LLD = -------------------------------------------------------------------------------

E

  • V
  • 2.22E6
  • Y
  • exp ( - t )

Where:

LLD is the a priori lower limit of detection as defined above (as Ci 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 radiochemical yield (when applicable),

is the radioactive decay constant for the particular radionuclide, and t 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 t 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. 27

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 nonfunctional, samples must be obtained as MAR 2016 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. 27

TABLE 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY UNIT 1 UNIT 2 UNIT 3 DISTANCE X/Q D/Q DISTANCE X/Q D/Q DISTANCE X/Q D/Q DIRECTION (METERS) (SEC/m3) (m-2) (METERS) (SEC/m3) (m-2) (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.l4E-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 23 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 l607 8.9lE-06 5.73E-09 SW 1487 7.47E-06 5.65E-09 1208 7.72E-06 6.88E-09 l057 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 l045 4.l7E-06 7.98E-09 NNW 1069 3.70E-06 7.26E-09 1342 2.85E-06 4.87E-09 l56l 2.93E-06 4.58E-09

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.

ODCM Rev. 27

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 mrem-m3 mrem-m3 mrad-m3 mrad-m3 Radionuclide yr-Ci yr-Ci yr-Ci yr-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 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-13lm 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+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 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109, Table B-1.

24 ODCM Rev. 27

TABLE 3-4 Pi VALUES FOR THE INHALATION PATHWAY (mrem/yr/Ci/m3)

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 I-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. 27

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:

5.0E-07 Ci/ml for the principal gamma emitters (except Ce-144) 3.0E-06 Ci/ml for Ce-144 1.0E-06 Ci/ml for I-131 1.0E-03 Ci/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 Ci/ml for Cs-134 2.0E-06 Ci/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. 27

TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling & Type Of (LLD)a Pathway Destination Analysis Frequency Notes Activity Analysis (Ci/ml)

1. Chemical Waste Neutralizer Retention Tank P Each Batch Principal Gamma Emittersc 5.0E-07 Tank (CWNT)b liquid radwaste N. A. I-131 1.0E-06 H-3 1.0E-05
2. Steam Generator Blowdown circ. water P Each Batch 1 Principal Gamma Emittersc 5.0E-07 Low TDS Sumpb CWNT N. A. I-131 1.0E-06 H-3 1.0E-05
3. Condensate
a. Condensate Polishing Low circ. water P Each Batch 3 Principal Gamma Emittersc 5.0E-07 b

TDS Sump CWNT N. A. I-131 1.0E-06 H-3 1.0E-05 27

b. Initial Backwash (low TDS sump) to P Each Discharge Principal Gamma Emittersc 5.0E-07 circ. water I-131 1.0E-06 (low TDS sump) to N. A. H-3 1.0E-05 CWNT
c. Pre-service rinse effluent Retention Tank P Each Discharge 2 Principal Gamma Emittersc 5.0E-07 through SC-N-V069 I-131 1.0E-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 5.0E-07 CD-N-V194 I-131 1.0E-06 Retention Tank P Each Discharge 2 H-3 1.0E-05 through SC-N-V079
4. Turbine Building Sumpd Retention Tank D Grab Sample 3 Principal Gamma Emittersc 5.0E-07 CWNT N. A. I-131 1.0E-06 H-3 1.0E-05 ODCM Rev. 27

TABLE 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling & Type Of (LLD)a Pathway Destination Analysis Frequency Notes Activity Analysis (Ci/ml)

5. North & South Condenser Area Retention Tank D Grab Sample 3 Principal Gamma Emittersc 5.0E-07 Sumpsd CWNT N. A. I-131 1.0E-06 H-3 1.0E-05
6. Steam Generator Blowdown to Retention Tank P Each Discharge 2 Principal Gamma Emittersc 5.0E-07 Retention Tank through SC-N-V064 I-131 1.0E-06 H-3 1.0E-05
7. Retention Tank to Evaporation evaporation pond P Each Batch Principal Gamma Emittersc 5.0E-07 Pond I-131 1.0E-06 H-3 1.0E-05 28 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 FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and MAR 2016 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 Tanks 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 ODCM Rev. 27

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 s b LLD = -------------------------------------------------------------------------------

E

  • V
  • 2.22E6
  • Y
  • exp ( - t )

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, is the radioactive decay constant for the particular radionuclide, and t is the elapsed time between midpoint of sample collection and time of counting.

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

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

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 3.0E-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. 27

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 nonfunctional MAR 2016 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 Tanks 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 Tanks 1-4 with section 3.2 Modes 1-4: Suspend the release Steam Generator Blowdown/Drain to Retention Modes 5,6 & defueled: Obtain grab At All Times Tanks 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. 27

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 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 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. 27

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 u = (3.17E-08) i [(Mi) (X/Q)UNIT(Qi)] (4-1)

For beta radiation:

D u = (3.17E-08) i [(Ni) (X/Q)UNIT(Qi)] (4-2)

Where:

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per Ci/m3 from Table 3-3.

Ni = the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per Ci/m3 from Table 3-3.

(X/Q)UNIT = the highest calculated annual average dispersion parameter, in sec/m3, 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 l

=7.90E-06 from Unit 2

=8.91E-06 from Unit 3 D u = 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 u = 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 Ci, 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. 27

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

Applicability: At all times.

Action:

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. 27

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) i [k (Rik Wk) (Qi)] (4-3)

Where:

Dou = 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 Ci, 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 mrem/yr per Ci/m3 and for the food and ground plane pathways in m2 - mrem/yr per Ci/sec, except H-3, which has units of mrem/yr per Ci/m3) at the controlling location. The Riks 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)UNIT, 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 1

=7.90E-06 from Unit 2

=8.91E-06 from Unit 3

= (X/Q)UNIT, 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)UNIT, 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. 27

= (D/Q)UNIT, 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 1

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

Value The length of the grazing season for milk animals (fs).

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

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. 27

4.3 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 nonfunctional equipment or subsystems and the reason for nonfunctionality,
b. Action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status, and MAR 2016
c. Summary description of action(s) taken to prevent a recurrence.

4.3.1 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. 27

4.3.2 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 = D + CD (4-4)

For beta radiation:

31 day = D + CD (4-5)

Where:

D = 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.

CD = 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 .

CD = 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 .

When performing the 31 day dose projection using the Gaseous Radioactive Effluent Tracking System (GRETS), D and D 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. 27

Dose Projection - I-131, I-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:

31dayo = Do + CDo (4-6)

Where:

Do = the total organ dose due to I-131, I-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 dayo.

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. 27

TABLE 4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY NUCLIDE T. BODY SKIN H-3 0.00E+00 0.00E+00 CR-51 4.66E+06 5.51E+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 0.00E+00 0.00E+00 ZR-95 2.45E+08 2.84E+08 SB-124 5.98E+08 6.90E+08 I-131 1.72E+07 2.09E+07 I-133 2.45E+06 2.98E+06 CS-134 6.86E+09 8.00E+09 CS-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. 27

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 0.00E+00 2.87E+03 2.87E+03 2.87E+03 2.87E+03 2.87E+03 2.87E+03 CR-51 0.00E+00 0.00E+00 4.00E+04 2.39E+04 8.82E+03 5.31E+04 1.01E+07 MN-54 0.00E+00 2.97E+08 5.66E+07 0.00E+00 8.83E+07 0.00E+00 9.09E+08 FE-59 1.14E+08 2.68E+08 1.03E+08 0.00E+00 0.00E+00 7.49E+07 8.93E+08 CO-58 0.00E+00 2.84E+07 6.38E+07 0.00E+00 0.00E+00 0.00E+00 5.76E+08 CO-60 0.00E+00 1.59E+08 3.51E+08 0.00E+00 0.00E+00 0.00E+00 2.99E+09 ZN-65 3.00E+08 9.56E+08 4.32E+08 0.00E+00 6.39E+08 0.00E+00 6.02E+08 SR-89 9.08E+09 0.00E+00 2.61E+08 0.00E+00 0.00E+00 0.00E+00 1.46E+09 SR-90 5.76E+11 0.00E+00 1.41E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 ZR-95 1.08E+06 3.47E+05 2.35E+05 0.00E+00 5.45E+05 0.00E+00 1.10E+09 SB-124 9.53E+07 1.80E+06 3.78E+07 2.31E+05 0.00E+00 7.42E+07 2.71E+09 I-131 5.49E+07 7.85E+07 4.50E+07 2.57E+10 1.35E+08 0.00E+00 2.07E+07 I-133 1.39E+06 2.42E+06 7.38E+05 3.56E+08 4.22E+06 0.00E+00 2.17E+06 CS-134 4.44E+09 1.06E+10 8.64E+09 0.00E+00 3.42E+09 1.13E+09 1.85E+08 CS-137 6.06E+09 8.29E+09 5.43E+09 0.00E+00 2.81E+09 9.36E+08 1.60E+08 BA-140 9.43E+07 1.19E+05 6.18E+06 0.00E+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 0.00E+00 4.48E+08 CE-144 3.12E+07 1.30E+07 1.67E+06 0.00E+00 7.73E+06 0.00E+00 1.05E+10 40 ODCM Rev. 27

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 0.00E+00 3.36E+03 3.36E+03 3.36E+03 3.36E+03 3.36E+03 3.36E+03 CR-51 0.00E+00 0.00E+00 5.60E+04 3.11E+04 1.23E+04 7.99E+04 9.41E+06 MN-54 0.00E+00 4.41E+08 8.74E+07 0.00E+00 1.31E+08 0.00E+00 9.04E+08 FE-59 1.69E+08 3.94E+08 1.52E+08 0.00E+00 0.00E+00 1.24E+08 9.31E+08 CO-58 0.00E+00 4.16E+07 9.59E+07 0.00E+00 0.00E+00 0.00E+00 5.74E+08 CO-60 0.00E+00 2.42E+08 5.45E+08 0.00E+00 0.00E+00 0.00E+00 3.15E+09 ZN-65 4.11E+08 1.43E+09 6.65E+08 0.00E+00 9.12E+08 0.00E+00 6.04E+08 SR-89 1.43E+10 0.00E+00 4.10E+08 0.00E+00 0.00E+00 0.00E+00 1.70E+09 SR-90 7.30E+11 0.00E+00 1.80E+11 0.00E+00 0.00E+00 0.00E+00 2.05E+10 ZR-95 1.64E+06 5.17E+05 3.56E+05 0.00E+00 7.60E+05 0.00E+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 0.00E+00 1.47E+07 I-133 1.29E+06 2.19E+06 6.68E+05 3.06E+08 3.84E+06 0.00E+00 1.66E+06 CS-134 6.90E+09 1.62E+10 7.53E+09 0.00E+00 5.16E+09 1.97E+09 2.02E+08 CS-137 9.86E+09 1.31E+10 4.57E+09 0.00E+00 4.46E+09 1.73E+09 1.87E+08 BA-140 1.07E+08 1.31E+05 6.88E+06 0.00E+00 4.44E+04 8.80E+04 1.65E+08 CE-141 2.61E+05 1.74E+05 2.00E+04 0.00E+00 8.19E+04 0.00E+00 4.98E+08 CE-144 5.11E+07 2.12E+07 2.75E+06 0.00E+00 1.26E+07 0.00E+00 1.29E+10 41 ODCM Rev. 27

TABLE 4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 5.23E+03 5.23E+03 5.23E+03 5.23E+03 5.23E+03 5.23E+03 CR-51 0.00E+00 0.00E+00 1.08E+05 6.02E+04 1.64E+04 1.10E+05 5.75E+06 MN-54 0.00E+00 6.49E+08 1.73E+08 0.00E+00 1.82E+08 0.00E+00 5.45E+08 FE-59 3.79E+08 6.13E+08 3.05E+08 0.00E+00 0.00E+00 1.78E+08 6.38E+08 CO-58 0.00E+00 6.21E+07 1.90E+08 0.00E+00 0.00E+00 0.00E+00 3.62E+08 CO-60 0.00E+00 3.70E+08 1.09E+09 0.00E+00 0.00E+00 0.00E+00 2.05E+09 ZN-65 7.93E+08 2.11E+09 1.31E+09 0.00E+00 1.33E+09 0.00E+00 3.71E+08 SR-89 3.44E+10 0.00E+00 9.83E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+09 SR-90 1.22E+12 0.00E+00 3.09E+11 0.00E+00 0.00E+00 0.00E+00 1.64E+10 ZR-95 3.72E+06 8.17E+05 7.27E+05 0.00E+00 1.17E+06 0.00E+00 8.52E+08 SB-124 3.38E+08 4.39E+06 1.19E+08 7.47E+05 0.00E+00 1.88E+08 2.12E+09 I-131 9.95E+07 1.00E+08 5.68E+07 3.31E+10 1.64E+08 0.00E+00 8.90E+06 I-133 2.36E+06 2.91E+06 1.10E+06 5.41E+08 4.85E+06 0.00E+00 1.17E+06 CS-134 1.57E+10 2.57E+10 5.43E+09 0.00E+00 7.98E+09 2.86E+09 1.39E+08 CS-137 2.34E+10 2.24E+10 3.31E+09 0.00E+00 7.31E+09 2.63E+09 1.40E+08 BA-140 2.20E+08 1.93E+05 1.28E+07 0.00E+00 6.27E+04 1.15E+05 1.11E+08 CE-141 6.15E+05 3.07E+05 4.55E+04 0.00E+00 1.34E+05 0.00E+00 3.83E+08 CE-144 1.24E+08 3.89E+07 6.62E+06 0.00E+00 2.15E+07 0.00E+00 1.01E+10 42 ODCM Rev. 27

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 0.00E+00 4.33E+02 4.33E+02 4.33E+02 4.33E+02 4.33E+02 4.33E+02 CR-51 0.00E+00 0.00E+00 3.44E+02 2.06E+02 7.58E+01 4.57E+02 8.65E+04 MN-54 0.00E+00 2.71E+06 5.18E+05 0.00E+00 8.08E+05 0.00E+00 8.31E+06 FE-59 2.60E+07 6.11E+07 2.34E+07 0.00E+00 0.00E+00 1.71E+07 2.04E+08 CO-58 0.00E+00 2.84E+06 6.36E+06 0.00E+00 0.00E+00 0.00E+00 5.75E+07 CO-60 0.00E+00 2.61E+07 5.76E+07 0.00E+00 0.00E+00 0.00E+00 4.90E+08 ZN-65 9.97E+07 3.17E+08 1.43E+08 0.00E+00 2.12E+08 0.00E+00 2.00E+08 SR-89 3.41E+07 0.00E+00 9.79E+05 0.00E+00 0.00E+00 0.00E+00 5.47E+06 SR-90 4.43E+09 0.00E+00 1.09E+09 0.00E+00 0.00E+00 0.00E+00 1.28E+08 ZR-95 2.68E+05 8.58E+04 5.81E+04 0.00E+00 1.35E+05 0.00E+00 2.72E+08 SB-124 2.67E+06 5.05E+04 1.06E+06 6.48E+03 0.00E+00 2.08E+06 7.59E+07 I-131 1.36E+05 1.94E+05 1.11E+05 6.37E+07 3.33E+05 0.00E+00 5.13E+04 I-133 4.56E-03 7.94E-03 2.42E-03 1.17E+00 1.39E-02 0.00E+00 7.14E-03 CS-134 2.17E+08 5.17E+08 4.23E+08 0.00E+00 1.67E+08 5.56E+07 9.05E+06 CS-137 3.11E+08 4.25E+08 2.78E+08 0.00E+00 1.44E+08 4.79E+07 8.22E+06 BA-140 4.35E+05 5.46E+02 2.85E+04 0.00E+00 1.86E+02 3.13E+02 8.95E+05 CE-141 8.87E+02 6.00E+02 6.80E+01 0.00E+00 2.79E+02 0.00E+00 2.29E+06 CE-144 4.23E+05 1.77E+05 2.27E+04 0.00E+00 1.05E+05 0.00E+00 1.43E+08 43 ODCM Rev. 27

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 0.00E+00 2.58E+02 2.58E+02 2.58E+02 2.58E+02 2.58E+02 2.58E+02 CR-51 0.00E+00 0.00E+00 2.75E+02 1.53E+02 6.03E+01 3.93E+02 4.62E+04 MN-54 0.00E+00 2.07E+06 4.11E+05 0.00E+00 6.18E+05 0.00E+00 4.25E+06 FE-59 2.08E+07 4.85E+07 1.87E+07 0.00E+00 0.00E+00 1.53E+07 1.15E+08 CO-58 0.00E+00 2.19E+06 5.04E+06 0.00E+00 0.00E+00 0.00E+00 3.02E+07 CO-60 0.00E+00 2.03E+07 4.56E+07 0.00E+00 0.00E+00 0.00E+00 2.64E+08 ZN-65 7.01E+07 2.43E+08 1.14E+08 0.00E+00 1.56E+08 0.00E+00 1.03E+08 SR-89 2.88E+07 0.00E+00 8.24E+05 0.00E+00 0.00E+00 0.00E+00 3.43E+06 SR-90 2.87E+09 0.00E+00 7.08E+08 0.00E+00 0.00E+00 0.00E+00 8.05E+07 ZR-95 2.14E+05 6.76E+04 4.65E+04 0.00E+00 9.93E+04 0.00E+00 1.56E+08 SB-124 2.18E+06 4.02E+04 8.52E+05 4.95E+03 0.00E+00 1.91E+06 4.40E+07 I-131 1.13E+05 1.58E+05 8.49E+04 4.61E+07 2.72E+05 0.00E+00 3.13E+04 I-133 3.82E-03 6.48E-03 1.98E-03 9.04E-01 1.14E-02 0.00E+00 4.90E-03 CS-134 1.73E+08 4.07E+08 1.89E+08 0.00E+00 1.29E+08 4.94E+07 5.06E+06 CS-137 2.58E+08 3.43E+08 1.20E+08 0.00E+00 1.17E+08 4.54E+07 4.88E+06 BA-140 3.59E+05 4.40E+02 2.31E+04 0.00E+00 1.49E+02 2.96E+02 5.54E+05 CE-141 7.45E+02 4.97E+02 5.71E+01 0.00E+00 2.34E+02 0.00E+00 1.42E+06 CE-144 3.56E+05 1.47E+05 1.91E+04 0.00E+00 8.80E+04 0.00E+00 8.96E+07 44 ODCM Rev. 27

TABLE 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 3.12E+02 3.12E+02 3.12E+02 3.12E+02 3.12E+02 3.12E+02 CR-51 0.00E+00 0.00E+00 4.29E+02 2.38E+02 6.51E+01 4.35E+02 2.28E+04 MN-54 0.00E+00 2.37E+06 6.31E+05 0.00E+00 6.64E+05 0.00E+00 1.99E+06 FE-59 3.68E+07 5.96E+07 2.97E+07 0.00E+00 0.00E+00 1.73E+07 6.20E+07 CO-58 0.00E+00 2.55E+06 7.82E+06 0.00E+00 0.00E+00 0.00E+00 1.49E+07 CO-60 0.00E+00 2.40E+07 7.09E+07 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN-65 1.05E+08 2.80E+08 1.74E+08 0.00E+00 1.77E+08 0.00E+00 4.92E+07 SR-89 5.45E+07 0.00E+00 1.56E+06 0.00E+00 0.00E+00 0.00E+00 2.11E+06 SR-90 3.70E+09 0.00E+00 9.39E+08 0.00E+00 0.00E+00 0.00E+00 4.99E+07 ZR-95 3.81E+05 8.36E+04 7.45E+04 0.00E+00 1.20E+05 0.00E+00 8.73E+07 SB-124 3.95E+06 5.12E+04 1.38E+06 8.72E+03 0.00E+00 2.19E+06 2.47E+07 I-131 2.09E+05 2.11E+05 1.20E+05 6.96E+07 3.46E+05 0.00E+00 1.87E+04 I-133 7.09E-03 8.77E-03 3.32E-03 1.63E+00 1.46E-02 0.00E+00 3.53E-03 CS-134 3.05E+08 5.00E+08 1.06E+08 0.00E+00 1.55E+08 5.56E+07 2.70E+06 CS-137 4.75E+08 4.55E+08 6.71E+07 0.00E+00 1.48E+08 5.33E+07 2.85E+06 BA-140 6.63E+05 5.81E+02 3.87E+04 0.00E+00 1.89E+02 3.46E+02 3.36E+05 CE-141 1.40E+03 6.99E+02 1.04E+02 0.00E+00 3.07E+02 0.00E+00 8.72E+05 CE-144 6.72E+05 2.11E+05 3.58E+04 0.00E+00 1.17E+05 0.00E+00 5.49E+07 45 ODCM Rev. 27

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 0.00E+00 1.02E+03 1.02E+03 1.02E+03 1.02E+03 1.02E+03 1.02E+03 CR-51 0.00E+00 0.00E+00 8.28E+03 4.95E+03 1.82E+03 1.10E+04 2.08E+06 MN-54 0.00E+00 3.99E+06 7.61E+05 0.00E+00 1.19E+06 0.00E+00 1.22E+07 FE-59 9.69E+06 2.28E+07 8.73E+06 0.00E+00 0.00E+00 6.36E+06 7.59E+07 CO-58 0.00E+00 1.74E+06 3.90E+06 0.00E+00 0.00E+00 0.00E+00 3.53E+07 CO-60 0.00E+00 8.41E+06 1.85E+07 0.00E+00 0.00E+00 0.00E+00 1.58E+08 ZN-65 6.34E+08 2.02E+09 9.12E+08 0.00E+00 1.35E+09 0.00E+00 1.27E+09 SR-89 4.90E+08 0.00E+00 1.41E+07 0.00E+00 0.00E+00 0.00E+00 7.86E+07 SR-90 2.43E+10 0.00E+00 5.96E+09 0.00E+00 0.00E+00 0.00E+00 7.02E+08 ZR-95 3.39E+02 1.09E+02 7.37E+01 0.00E+00 1.71E+02 0.00E+00 3.45E+05 SB-124 9.11E+06 1.72E+05 3.61E+06 2.21E+04 0.00E+00 7.09E+06 2.59E+08 I-131 7.77E+07 1.11E+08 6.37E+07 3.64E+10 1.91E+08 0.00E+00 2.93E+07 I-133 1.02E+06 1.77E+06 5.39E+05 2.60E+08 3.08E+06 0.00E+00 1.59E+06 CS-134 2.83E+09 6.73E+09 5.50E+09 0.00E+00 2.18E+09 7.23E+08 1.18E+08 CS-137 3.83E+09 5.24E+09 3.43E+09 0.00E+00 1.78E+09 5.91E+08 1.01E+08 BA-140 7.11E+06 8.93E+03 4.66E+05 0.00E+00 3.04E+03 5.11E+03 1.46E+07 CE-141 8.73E+03 5.90E+03 6.70E+02 0.00E+00 2.74E+03 0.00E+00 2.26E+07 CE-144 1.01E+06 4.21E+05 5.41E+04 0.00E+00 2.50E+05 0.00E+00 3.41E+08 46 ODCM Rev. 27

TABLE 4-9 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 CR-51 0.00E+00 0.00E+00 1.45E+04 8.03E+03 3.17E+03 2.06E+04 2.43E+06 MN-54 0.00E+00 6.64E+06 1.32E+06 0.00E+00 1.98E+06 0.00E+00 1.36E+07 FE-59 1.69E+07 3.95E+07 1.52E+07 0.00E+00 0.00E+00 1.24E+07 9.33E+07 CO-58 0.00E+00 2.93E+06 6.76E+06 0.00E+00 0.00E+00 0.00E+00 4.04E+07 CO-60 0.00E+00 1.42E+07 3.21E+07 0.00E+00 0.00E+00 0.00E+00 1.86E+08 ZN-65 9.74E+08 3.38E+09 1.58E+09 0.00E+00 2.17E+09 0.00E+00 1.43E+09 SR-89 9.03E+08 0.00E+00 2.59E+07 0.00E+00 0.00E+00 0.00E+00 1.08E+08 SR-90 3.43E+10 0.00E+00 8.48E+09 0.00E+00 0.00E+00 0.00E+00 9.64E+08 ZR-95 5.94E+02 1.87E+02 1.29E+02 0.00E+00 2.75E+02 0.00E+00 4.32E+05 SB-124 1.62E+07 2.99E+05 6.34E+06 3.69E+04 0.00E+00 1.42E+07 3.27E+08 I-131 1.41E+08 1.98E+08 1.06E+08 5.76E+10 3.40E+08 0.00E+00 3.91E+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 1.16E+10 5.36E+09 0.00E+00 3.67E+09 1.40E+09 1.44E+08 CS-137 6.95E+09 9.24E+09 3.22E+09 0.00E+00 3.15E+09 1.22E+09 1.32E+08 BA-140 1.28E+07 1.57E+04 8.27E+05 0.00E+00 5.33E+03 1.06E+04 1.98E+07 CE-141 1.60E+04 1.07E+04 1.23E+03 0.00E+00 5.03E+03 0.00E+00 3.06E+07 CE-144 1.86E+06 7.68E+05 9.97E+04 0.00E+00 4.59E+05 0.00E+00 4.67E+08 47 ODCM Rev. 27

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 0.00E+00 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 CR-51 0.00E+00 0.00E+00 2.95E+04 1.64E+04 4.47E+03 2.99E+04 1.56E+06 MN-54 0.00E+00 9.94E+06 2.65E+06 0.00E+00 2.79E+06 0.00E+00 8.34E+06 FE-59 3.92E+07 6.35E+07 3.16E+07 0.00E+00 0.00E+00 1.84E+07 6.61E+07 CO-58 0.00E+00 4.48E+06 1.37E+07 0.00E+00 0.00E+00 0.00E+00 2.61E+07 CO-60 0.00E+00 2.21E+07 6.52E+07 0.00E+00 0.00E+00 0.00E+00 1.23E+08 ZN-65 1.91E+09 5.09E+09 3.17E+09 0.00E+00 3.21E+09 0.00E+00 8.95E+08 SR-89 2.23E+09 0.00E+00 6.38E+07 0.00E+00 0.00E+00 0.00E+00 8.65E+07 SR-90 5.80E+10 0.00E+00 1.47E+10 0.00E+00 0.00E+00 0.00E+00 7.81E+08 ZR-95 1.38E+03 3.03E+02 2.70E+02 0.00E+00 4.34E+02 0.00E+00 3.16E+05 SB-124 3.84E+07 4.99E+05 1.35E+07 8.49E+04 0.00E+00 2.13E+07 2.41E+08 I-131 3.42E+08 3.44E+08 1.96E+08 1.14E+11 5.65E+08 0.00E+00 3.06E+07 I-133 4.51E+06 5.57E+06 2.11E+06 1.04E+09 9.29E+06 0.00E+00 2.25E+06 CS-134 1.13E+10 1.86E+10 3.92E+09 0.00E+00 5.76E+09 2.07E+09 1.00E+08 CS-137 1.67E+10 1.60E+10 2.36E+09 0.00E+00 5.22E+09 1.88E+09 1.00E+08 BA-140 3.10E+07 2.71E+04 1.81E+06 0.00E+00 8.83E+03 1.62E+04 1.57E+07 CE-141 3.94E+04 1.97E+04 2.92E+03 0.00E+00 8.62E+03 0.00E+00 2.45E+07 CE-144 4.57E+06 1.43E+06 2.44E+05 0.00E+00 7.94E+05 0.00E+00 3.74E+08 48 ODCM Rev. 27

TABLE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 3.18E+03 3.18E+03 3.18E+03 3.18E+03 3.18E+03 3.18E+03 CR-51 0.00E+00 0.00E+00 4.67E+04 3.05E+04 6.66E+03 5.93E+04 1.36E+06 MN-54 0.00E+00 1.85E+07 4.19E+06 0.00E+00 4.10E+06 0.00E+00 6.79E+06 FE-59 7.32E+07 1.28E+08 5.04E+07 0.00E+00 0.00E+00 3.78E+07 6.11E+07 CO-58 0.00E+00 8.96E+06 2.23E+07 0.00E+00 0.00E+00 0.00E+00 2.23E+07 CO-60 0.00E+00 4.52E+07 1.07E+08 0.00E+00 0.00E+00 0.00E+00 1.07E+08 ZN-65 2.57E+09 8.81E+09 4.06E+09 0.00E+00 4.27E+09 0.00E+00 7.44E+09 SR-89 4.25E+09 0.00E+00 1.22E+08 0.00E+00 0.00E+00 0.00E+00 8.74E+07 SR-90 6.31E+10 0.00E+00 1.61E+10 0.00E+00 0.00E+00 0.00E+00 7.88E+08 ZR-95 2.45E+03 5.97E+02 4.23E+02 0.00E+00 6.43E+02 0.00E+00 2.97E+05 SB-124 7.41E+07 1.09E+06 2.30E+07 1.97E+05 0.00E+00 4.64E+07 2.29E+08 I-131 7.14E+08 8.42E+08 3.70E+08 2.77E+11 9.83E+08 0.00E+00 3.00E+07 I-133 9.52E+06 1.39E+07 4.06E+06 2.52E+09 1.63E+07 0.00E+00 2.35E+06 CS-134 1.82E+10 3.40E+10 3.44E+09 0.00E+00 8.76E+09 3.59E+09 9.24E+07 CS-137 2.67E+10 3.13E+10 2.22E+09 0.00E+00 8.39E+09 3.40E+09 9.78E+07 BA-140 6.37E+07 6.37E+04 3.28E+06 0.00E+00 1.51E+04 3.91E+04 1.57E+07 CE-141 7.81E+04 4.77E+04 5.61E+03 0.00E+00 1.47E+04 0.00E+00 2.46E+07 CE-144 6.55E+06 2.68E+06 3.67E+05 0.00E+00 1.08E+06 0.00E+00 3.76E+08 49 ODCM Rev. 27

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 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 CR-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 CO-58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 CO-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 ZN-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 SR-90 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 SB-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 0.00E+00 2.48E+06 4.06E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 50 ODCM Rev. 27

TABLE 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 MN-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 CO-58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 CO-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 SR-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 SB-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 0.00E+00 3.85E+06 3.98E+05 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 CS-137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 51 ODCM Rev. 27

TABLE 4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILD RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 CO-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 CO-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 SB-124 5.74E+04 7.40E+02 2.00E+04 1.26E+02 0.00E+00 3.24E+06 1.64E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 52 ODCM Rev. 27

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 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 CO-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CO-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 ZN-65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 SR-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 SB-124 3.79E+04 5.56E+02 1.20E+04 1.01E+02 0.00E+00 2.65E+06 5.91E+04 I-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 53 ODCM Rev. 27

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

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 54 SSE 1.27E-06 4.7 2.61E-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 (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.

ODCM Rev. 27

References:

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

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 X/Q GARDEN(b) D/Q X/Q MILK(b) D/Q DIRECTION (Sec/m3) Dist. Miles (m-2) (Sec/m3) Dist. Miles (m-2) (Sec/m3) Dist. Miles (m-2)

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 1.51E-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 55 SSE 1.34E-06 4.5 2.81E-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) 3.56E-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 (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.

ODCM Rev. 27

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/m3) Dist. Miles (m-2) (Sec/m3) Dist. Miles (m-2) (Sec/m3) Dist. Miles (m-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 3.00E-09 1.48E-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 56 SSE 1.36E-06 4.4 2.88E-10 1.09E-06 (a) 2.15E-10 1.09E-06 (a) 2.15E-10 S 2.65E-06 4.2 5.25E-10 2.25E-06 4.9 4.06E-10 2.31E-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 1.11E-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 (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.

ODCM Rev. 27

References:

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

4.4 Requirements

Liquid Effluents 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, 4.1b, 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) i [(Ki) (X/Q)UNIT (Qi)] (5-1)

Where:

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

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

(X/Q)UNIT = 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-131, 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) i [k(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 Ci, 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 Ci/m3 and for the food and ground plane pathways in m2-mrem/yr per Ci/sec) at the controlling location. The Riks 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)UNIT, 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 1

=2.19E-06 from Unit 2

=2.31E-06 from Unit 3

= (D/Q)UNIT, 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 1

=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)

+ ---------------------------------------------- + . . . 1.0 reporting level (1) 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. 27

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 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 Samples Sampling and Type and Frequency and/or Sample and Sample Locationsa Collection Frequencya of Analysisd Airborne Samples from 5 locations: 4 samples Continuous sampling Gross beta weeklyc, at or near the SITE BOUNDARIES collected weekly, or I-131 weekly; gamma Radioiodine and (#14A, 15, 29, 40) including 3 more frequently if isotopic analysis of particulates different sectors of the highest required by dust composite (by calculated annual average ground loading. location) quarterly.

level D/Q.*

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

1 sample (#6A) from a control location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.e 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. 27

TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples Sampling and Type and Frequency and/or Sample and Sample Locationsa Collection Frequency a of Analysisd Waterborne Surface 85 acre Water storagereservoir (#60) Quarterlyh grab sample Tritium and gamma MAR 2016 45 acre Water storage reservoir (#61) isotopic analysis Evaporation pond #1 (#59) quarterly.

Evaporation pond #2 (#63)

Evaporation pond #3 (#64)

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

Drinking (well) 3 wells from surrounding residences Composite sample of I-131 analysis on each

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

Ingestion Samples from milking animals in Semimonthly for Gamma isotopic and 3 locations within 5 km (3 mi) distant animals on pasture; I-131 analysis Milk having the highest dose potential. If otherwise, monthly. semimonthly when 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.g 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.e 65 ODCM Rev. 27

TABLE 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples Sampling and Type and Frequency and/or Sample and Sample Locationsa Collection Frequency a of Analysisd Food Products

  • 2 samples (#47, #51) of 3 types of Monthly during Gamma isotopic MAR 2016 broad leaf vegetation (as available) growing season. analysis.

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

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

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. 27

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 6-1or 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.

h Quarterly grab samples are not required from the onsite evaporation pond if the evaporation pond has not received any influent since the last sample was taken.

MAR 2016 67 ODCM Rev. 27

TABLE 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/l) or Gas (pCi/m3) (pCi/l) (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/l may be used.
    • If no drinking water pathway exists, a reporting level of 20 pCi/l may be used.

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TABLE 6-3 a

DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS Lower Limit of Detection (LLD)b Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/l) or Gas (pCi/m3) (pCi/l) (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/l may be used.
    • If no drinking water pathway exists, a value of 15 pCi/l 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):

4.66s b LLD = ------------------------------------------------------------------------

E

  • V
  • 2.22
  • Y
  • exp ( - t )

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),

is the radioactive decay constant for the particular radionuclide, and t 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 t 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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6.3 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.

6.3.1 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.

6.3.2 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.

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TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE NOTE DESIGNATION SITE SAMPLE 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 5 TLD (b) SP ESE11 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) IR 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. 27

TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE NOTE DESIGNATION SITE SAMPLE 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 SW1 SW site boundary 28 TLD (b) IR WSW1 WSW site boundary 29 TLD (b) IR W1 W site boundary 29 Air (b) W1 Same as TLD 30 TLD (b) IR WNW1 WNW site boundary 31 TLD (b) IR NW1 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 43 TLD SUP NE5 Winters Well School 74 ODCM Rev. 27

TABLE 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE NOTE DESIGNATION SITE SAMPLE TYPE (d) (a) LOCATION DESCRIPTION (c) 44 TLD (b) Control ENE35 El Mirage SUP Transit 45 TLD Control ONSITE Central lab, lead pig 46 TLD (b) SP ENE30 Litchfield Park School 46 Water (b) WD NNW8 Local residence 47 TLD SUP E35 Littleton School 47 Vegetation (b) N3 Local residence 48 TLD SUP E24 Jackrabbit Trail 48 Water (b) WD SW1 Local residence 49 TLD SUP ENE11 Palo Verde Rd.

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

51 Milk (b) ENE5 Local residence (goats) 51 Vegetation (b) ENE5 Local residence MAR 2016 53 Milk (b) Control NE30 Local residence (goats) 54 Milk (b) NNE4 Local residence (goats)

WD 55 Water SUP SW3 Local residence 57 Ground Water (b) WG onsite Well 27ddc 58 Ground Water (b) WG onsite Well 34abb 59 Surface Water (b) WS onsite Evaporation Pond #1 60 Surface Water (b) WS onsite 85 acre Water storage reservoir 61 Surface Water (b) WS onsite 45 acre Water storage reservoir 62 Vegetation (b) Control ENE26 Commercial produce company 63 Surface Water (b) WS onsite Evaporation Pond #2 64 Surface Water (b) WS onsite Evaporation Pond #3 75 ODCM Rev. 27

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. 27

Figure 6-1 Radiological Environmental Monitoring Program Sample Sites 0 - 10 miles 77 ODCM Rev. 27

78 Figure 6-2 Radiological Environmental Monitoring Program Sample Sites ODCM Rev. 27 10 - 35 Miles

Figure 6-3 Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED 79 ODCM Rev. 27

Figure 6-4 Site Exclusion Area Boundary DELETED Refer to UFSAR Figure 2.1-4 80 ODCM Rev. 27

81 Figure 6-5 Gaseous Effluent Release Points ODCM Rev. 27

Figure 6-6 Low Population Zone DELETED Refer to UFSAR Figure 2.1-15 82 ODCM Rev. 27

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.

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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.

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7.2 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 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.

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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 10CFR50 for radioiodines and particulates is known to be a function of:

(1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptors 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.

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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 10 CFR 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 II.A and II.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 mrems/year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year. This 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).

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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 ponds 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 II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement implements the guides set forth in Section II.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.

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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 II.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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 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 II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This 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.

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B-4.4 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 II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to 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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 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.

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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 posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD and other detection limits can be found in Currie, L. A., Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (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/m2.

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.

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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 CHECK See the Technical Specification definition.

CHANNEL FUNCTIONAL TEST See the Technical Specification definition.

DOSE EQUIVALENT I-131 See the Technical Specification definition.

FUNCTIONAL-FUNCTIONALITY Functionality is an attribute of a structure, system, or component SSC(s) that is not controlled by the Technical Specifications (TSs). An SSC not controlled by Tss is functional or has functionality when it is capable of performing its function(s) as set forth in the current licensing basis (CLB). These CLB function(s) may include the capability to perform a necessary and related support function for an SSC(s) controlled by TSs.

MAR 2016 FREQUENCY 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.

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APPENDIX C DEFINITIONS (Continued)

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.

OPERABLE-OPERABILITY 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.

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

RATED 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).

93 ODCM Rev. 27

APPENDIX C DEFINITIONS (Continued)

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

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

UNRESTRICTED AREA An UNRESTRICTED AREA 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.

94 ODCM Rev. 27

TABLE C-1 FREQUENCY NOTATION NOTATION FREQUENCY*

MAR 2016 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.

  • The specified Frequency for each Surveillance Requirement and Sampling Requirement is met if the Surveillance Requirement or Sampling Requirement is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

MAR 2016 95 ODCM Rev. 27

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. 27

Appendix F Correction to the 2013 and 2015 PVNGS Annual Radiological Effluent Release Reports

Osps A subsidiary of Pinnacle West Capital Corporation ID #: 218-04128 DATE: 04/14/2017 Company Correspondence TO: File Sta. #

Ext. #

Digitally signed by McDowell, Joshua FROM: Joshua McDowell Sta. #

McDowell, (Z08270)

DN; cn=McDowell, Joshua (Z08270) 7397 Ext. # 82-5482 Joshua (Z08270)

Date: 2017.04.14 03:52:25 -07'00'

SUBJECT:

Correction to Annual Radioactive Effluent Release Reports for 2015 and 2013 Palo Verde Nuclear Generating Station - Units 1,2, and 3

REFERENCES:

1. PVNGS Annual Radioactive Effluent Release Report for 2015
2. PVNGS Annual Radioactive Effluent Release Report for 2016

Dear Sir or Madam:

In accordance with Palo Verde Nuclear Generating Station (PVNGS) Technical Specification (TS) 5.6.2, PVNGS submitted the Annual Radioactive Effluent Release Report (ARERR) for 2015 via Reference 1. It was discovered that a refueling purge permit had been revised after data was gathered for this report. This led to particulate activity not being accounted for in the annual report.

The following 2015 ARERR tables were impacted and therefore revised in this submittal:

  • 2 Batch Release Data
  • 12 Unit 2 Gaseous Effluents - Summation of All Releases
  • 15 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines
  • 16 Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates
  • 17 Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines
  • 18 Unit 2 Gaseous Effluents - Continuous and Batch - Particulates
  • 30 Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total By Quarter
  • 31 Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total By Quarter
  • 32 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -

Total By Quarter

  • 33 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Quarter
  • 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total ByUnit
  • 37 Units 1, 2 and 3 Gaseous Effluents- Batch - Particulates - Total By Unit
  • 38 Units 1,2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -

Total By Unit

  • 39 Units 1, 2 and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total By Unit
  • 43 Doses To Special Locations For 2014
  • 44 Integrated Population Dose for 2014
  • 45 Summary of Individual Doses for 2014 These deviations were documented through Corrective Action program document Condition Report (CR) 17-01056.

The Nuclear Regulatory Commission questioned a 2013 release of Xenon-133 as documented on the 2013 PVNGS ARERR. In response to this question, it was discovered that an overly conservative value had been applied to a release permit. This is documented through CR 17-05289.

The following 2013 ARERR tables were impacted and therefore revised in this submittal:

  • 20 Unit 3 Gaseous Effluents - Summation Of All Releases
  • 25 Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines
  • 27 Unit 3 Radiation Doses At And Beyond The Site Boundary
  • 30 Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total By Quarter
  • 32 Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -

Total By Quarter

  • 36 Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine - Total By Unit
  • 38 Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -

Total By Unit

Table 20:

Unit 3 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year  % (1)

A. Fission & activation gases

1. Total release Ci 5.83E-02 6.98E-02 2.05E-01 2.46E+01 2.49E+01 3.54E+01
2. Average release rate for period Ci/sec 7.42E-03 8.88E-03 2.58E-02 3.09E+00 7.87E-01
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

B. Iodine 131

1. Total Iodine 131 Ci 0.00E+00 0.00E+00 0.00E+00 6.58E-06 6.58E-06 3.32E+01
2. Average release rate for period Ci/sec 0.00E+00 0.00E+00 0.00E+00 8.28E-07 2.08E-07 35
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

C. Particulates

1. Particulates with half- lives > 8 days Ci 1.51E-06 1.27E-06 2.72E-06 3.50E-04 3.56E-04 3.43E+01
2. Average release rate for period Ci/sec 1.92E-07 1.61E-07 3.42E-07 4.40E-05 1.12E-05
3. Percent of ODCM Requirement limit  %

NA (2) NA (2) NA (2) NA (2) NA (2)

4. Gross Alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD PVNGS ARERR 2014 D. Tritium
1. Total release Ci 7.03E+01 1.35E+02 5.17E+02 2.13E+02 9.36E+02 3.85E+01
2. Average release rate for period Ci/sec 8.94E+00 1.72E+01 6.50E+01 2.68E+01 2.96E+01
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 27 for percent of ODCM Requirement limits.

Table 25:

Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 5.21E-02 6.17E-02 1.84E-01 4.93E-01 7.90E-01 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 3.95E-08 0.00E+00 3.95E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.25E-03 8.00E-03 2.15E-02 1.06E+00 1.10E+00 Xe-133m Ci 0.00E+00 0.00E+00 3.41E-07 8.13E+00 8.13E+00 Xe-135 Ci 0.00E+00 5.03E-05 1.67E-06 1.49E+01 1.49E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 5.83E-02 6.98E-02 2.05E-01 2.46E+01 2.49E+01
2. Iodines I-131 Ci 0.00E+00 0.00E+00 0.00E+00 6.58E-06 6.58E-06 I-132 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 0.00E+00 0.00E+00 0.00E+00 6.58E-06 6.58E-06 40 PVNGS ARERR 2014

Table 27:

Unit 3 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Air Dose mrad 1.37E-04 1.63E-04 4.84E-04 1.02E-02 1.10E-02 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit  % 2.74E-03 3.26E-03 9.68E-03 2.04E-01 1.10E-01 Beta Air Dose mrad 5.01E-05 5.96E-05 1.76E-04 1.45E-02 1.48E-02 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit  % 5.01E-04 5.96E-04 1.76E-03 1.45E-01 7.40E-02 Maximum Organ Dose mrem 2.52E-02 4.86E-02 1.85E-01 7.67E-02 3.36E-01 (excluding skin)

Age Teen Teen Teen Teen Teen Organ Thyroid 4.86E-02 Thyroid Lung 3.36E-01 ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit  % 3.36E-01 6.48E-01 2.47E+00 1.02E+00 2.24E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.

3 PVNGS ARERR 2014

Table 30:

Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 2.08E+00 3.33E-01 3.56E-01 6.22E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 0.00E+00 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.21E-01 3.57E-02 3.52E-02 1.09E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 3.41E-07 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 5.03E-05 1.67E-06 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.83E+00 3.68E-01 3.92E-01 2.48E+01 2.84E+01
2. Iodines I-131 Ci 0.00E+00 9.92E-07 0.00E+00 0.00E+00 9.92E-07 I-132 Ci 0.00E+00 1.50E-05 0.00E+00 0.00E+00 1.50E-05 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 0.00E+00 1.60E-05 0.00E+00 0.00E+00 1.60E-05 4 PVNGS ARERR 2014

Table 32:

Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines -

Total By Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 2.08E+00 3.33E-01 3.56E-01 6.22E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 0.00E+00 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.21E-01 3.57E-02 3.52E-02 1.09E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 3.41E-07 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 5.03E-05 1.67E-06 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.83E+00 3.68E-01 3.92E-01 2.48E+01 2.84E+01
2. Iodines I-131 Ci 5.35E-06 5.61E-05 0.00E+00 6.58E-06 6.80E-05 I-132 Ci 1.39E-04 4.29E-04 0.00E+00 0.00E+00 5.68E-04 I-133 Ci 6.29E-06 0.00E+00 0.00E+00 0.00E+00 6.29E-06 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 1.51E-04 4.85E-04 0.00E+00 6.58E-06 6.42E-04 5 PVNGS ARERR 2014

Table 36:

Units 1, 2 and 3 Gaseous Effluents- Batch - Fission Gases and Iodine -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

1. Fission gases Ar-41 Ci 2.07E+00 5.31E-01 7.90E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.09E-01 7.37E-02 1.10E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 0.00E+00 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.80E+00 6.05E-01 2.49E+01 2.84E+01
2. Iodines I-131 Ci 9.92E-07 0.00E+00 0.00E+00 9.92E-07 I-132 Ci 1.50E-05 0.00E+00 0.00E+00 1.50E-05 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 1.60E-05 0.00E+00 0.00E+00 1.60E-05 51 PVNGS ARERR 2014

Table 38:

Units 1, 2 and 3 Gaseous Effluents- Continuous and Batch - Fission Gases and Iodine -

Total By Unit Total Units Nuclides Released Unit Unit 1 Unit 2 Unit 3 1, 2 and 3

1. Fission gases Ar-41 Ci 2.07E+00 5.31E-01 7.90E-01 3.39E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 3.20E-08 0.00E+00 3.95E-08 7.15E-08 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 6.09E-01 7.37E-02 1.10E+00 1.78E+00 Xe-133m Ci 4.53E-07 0.00E+00 8.13E+00 8.13E+00 Xe-135 Ci 1.29E-01 0.00E+00 1.49E+01 1.51E+01 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 2.80E+00 6.05E-01 2.49E+01 2.84E+01
2. Iodines I-131 Ci 6.14E-05 0.00E+00 6.58E-06 6.80E-05 I-132 Ci 5.68E-04 0.00E+00 0.00E+00 5.68E-04 I-133 Ci 6.29E-06 0.00E+00 0.00E+00 6.29E-06 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci 6.36E-04 0.00E+00 6.58E-06 6.42E-04 52 PVNGS ARERR 2014

Table 1: Evaporation Pond Data Deleted Evaporation Pond 1(1A, 1B, 1C) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Deleted Historical volume of water evaporated Deleted 3.22E+11 8.85E+11 8.85E+11 3.22E+11 (ml) Deleted Tritium Concentration (uCi/cc) 4.85E-06 3.34E-06 3.65E-06 2.98E-06 Deleted Tritium Curies 1.83E-01 1.16E+00 1.21E+00 3.52E-01 2.91E+00 Deleted Evaporation Pond 2 (2A and 2B) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Deleted Historical volume of water evaporated 2.40E+11 7.97E+11 7.97E+11 2.90E+11 Deleted (ml)

Deleted Tritium Concentration (uCi/cc) 1.45E-06 1.46E-06 1.75E-06 1.12E-06 Tritium curies Deleted 1.80E-01 4.91E-01 6.04E-01 1.45E-01 1.42E+00 Evaporation Pond 3 (3A and 3B) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Deleted Historical volume of water evaporated Deleted 2.22E+11 3.05E+11 3.05E+11 1.11E+11 (ml) Deleted 3B Tritium Concentration (uCi/cc) 1.65E-06 1.08E-06 1.24E-06 8.76E-07 Deleted 3B Tritium curies 1.81E-01 3.25E-01 3.73E-01 9.62E-02 9.76E-01 Deleted Dose (mRem) Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Deleted Pond 1 7.61E-03 1.43E-02 1.50E-02 4.16E-03 4.12E-02 Deleted Pond 2 2.50E-03 6.81E-03 8.38E-03 2.01E-03 1.97E-02 Deleted Pond 3 2.51E-03 4.51E-03 5.18E-03 1.33E-03 1.35E-02 Deleted Total 6.71E-03 2.57E-02 2.86E-02 7.51E-03 7.44E-02 Deleted Deleted Deleted Table 2: Batch Release Data Deleted All times are in hours Unit 1 Unit 2 Unit 3 Deleted January - June Number of batch releases 20 24 43 Deleted Total time period for batch releases 114.54 366.34 1275.06 Deleted Maximum time period for a batch release 92.00 105.90 168.00 Deleted Average time period for a batch release 5.73 15.26 29.65 Minimum time period for a batch release Deleted 0.53 0.51 0.10 July - December Deleted Number of batch releases 21 42 19 Deleted Total time period for batch releases 161.18 1501.48 198.17 Deleted Maximum time period for a batch release 103.80 168.00 123.75 Average time period for a batch release 7.68 35.75 10.43 Deleted Minimum time period for a batch release 0.52 0.18 0.50 Deleted January - December Deleted Number of batch releases 41 66 62 Deleted Total time period for batch releases 275.72 1867.82 1473.23 Maximum time period for a batch release 103.80 168.00 168.00 Deleted Average time period for a batch release 6.72 28.30 23.76 Deleted Minimum time period for a batch release 0.52 0.18 0.10 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted

Table 12:

Unit 2 Gaseous Effluents - Summation Of All Releases Total For Est. Total Error Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year  % (1)

A. Fission & activation gases

1. Total release Ci 8.53E-02 9.98E-02 1.12E-01 9.63E+00 9.93E+00 3.54E+01 Deleted
2. Average release rate for period Ci/sec 1.10E-02 1.27E-02 1.41E-02 1.21E+00 3.15E-01 Deleted
3. Percent of ODCM Requirement limit  % Deleted NA (2) NA (2) NA (2) NA (2) NA (2)

Deleted B. Iodine 131 Deleted

1. Total Iodine 131 Ci 0.00E+00 0.00E+00 0.00E+00 2.38E-05 2.38E-05 Deleted 3.32E+01
2. Average release rate for period Ci/sec Deleted 0.00E+00 0.00E+00 0.00E+00 2.99E-06 7.55E-07 Deleted
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2) Deleted C. Particulates Deleted
1. Particulates with half- lives > 8 days Ci Deleted 0.00E+00 0.00E+00 0.00E+00 8.97E-04 8.97E-04 3.43E+01 Deleted
2. Average release rate for period Ci/sec 0.00E+00 0.00E+00 0.00E+00 1.13E-04 2.85E-05 Deleted
3. Percent of ODCM Requirement limit  % NA (2) NA (2) NA (2) NA (2) NA (2) Deleted
4. Gross Alpha radioactivity Ci Deleted

< LLD < LLD < LLD < LLD < LLD Deleted D. Tritium Deleted

1. Total release Ci 3.18E+02 1.04E+02 1.76E+02 3.22E+02 9.20E+02 3.85E+01 Deleted
2. Average release rate for period Ci/sec 4.09E+01 1.32E+01 2.21E+01 4.05E+01 2.92E+01 Deleted Deleted
3. Percent of ODCM Requirement limit  %

NA (2) NA (2) NA (2) NA (2) NA (2) Deleted (1) Estimated total error methodology is presented in Table 40. Deleted (2) See Table 19 for percent of ODCM Requirement limits. Deleted Deleted Deleted

Table 15:

Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total

1. Fission gases Ar-41 Ci 7.29E-02 8.42E-02 9.39E-02 7.60E+00 7.86E+00 Kr-83m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 9.77E-04 9.77E-04 Xe-133 Ci 1.24E-02 1.56E-02 1.79E-02 1.73E+00 1.77E+00 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 1.38E-03 1.38E-03 Xe-135 Ci 0.00E+00 0.00E+00 9.12E-05 0.00E+00 9.12E-05 Deleted Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Ci Deleted 8.53E-02 9.98E-02 1.12E-01 9.34E+00 9.63E+00
2. Iodines Deleted I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted I-132 Ci 0.00E+00 0.00E+00 0.00E+00 7.30E-05 7.30E-05 Deleted I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted Total Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 30 PVNGS ARERR 2014
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