ML18131A353: Difference between revisions

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Reviewed by:    Approved by:
Reviewed by:    Approved by:
Director, Radiation Protection
Director, Radiation Protection
  (
(


==Reference:==
==Reference:==
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Date: 2018.04.09 13:29:33 -07'00' Moeller, Carl (Z09119)Digitally signed by Moeller, Carl (Z09119)
Date: 2018.04.09 13:29:33 -07'00' Moeller, Carl (Z09119)Digitally signed by Moeller, Carl (Z09119)
DN: cn=Moeller, Carl  (Z09119)
DN: cn=Moeller, Carl  (Z09119)
Date: 2018.04.10 06:45:05 -07'00'  
Date: 2018.04.10 06:45:05 -07'00'
: 1. Introduction ..................................................................................................................
: 1. Introduction ..................................................................................................................
........... 2 Overview ......................................................................................................................
........... 2 Overview ......................................................................................................................
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During 2017, the following categories of samples were collected by APS:  
During 2017, the following categories of samples were collected by APS:  


Broadleaf vegetation Groundwater Drinking water Surface water Airborne particulate and radioiodine  Goat milk Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmen tal gamma radiation. The Environmental TLD program is also conducted by APS. The Arizona Department of Health Services, Bureau of Radiation Control (BRC) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by BRC include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) Deep Wells. Offsite samples analyzed by BRC include two (2) local resident wells. BRC also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring locations, eighteen (18) of which are duplicates of APS locations. A comparison of pre-operational and operational data indicates no changes to environmental radiation levels.  
Broadleaf vegetation Groundwater Drinking water Surface water Airborne particulate and radioiodine  Goat milk Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmen tal gamma radiation. The Environmental TLD program is also conducted by APS. The Arizona Department of Health Services, Bureau of Radiation Control (BRC) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by BRC include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) Deep Wells. Offsite samples analyzed by BRC include two (2) local resident wells. BRC also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring locations, eighteen (18) of which are duplicates of APS locations. A comparison of pre-operational and operational data indicates no changes to environmental radiation levels.
(NOTE:  Reference to APS throughout this report refers to PVNGS personnel)  
(NOTE:  Reference to APS throughout this report refers to PVNGS personnel)
: 1. Introduction This report presents the results of the operational Radiological Environmental Monitoring Program conducted by Arizona Public Service Company (APS). The Radiological Environmental Monitoring Program (REMP) was established for the Palo Verde Nuclear                  Generating Station (PVNGS) by APS in 1979. This report contains the measurements and findings for 2017. All references are specifically identified in Section 12.
: 1. Introduction This report presents the results of the operational Radiological Environmental Monitoring Program conducted by Arizona Public Service Company (APS). The Radiological Environmental Monitoring Program (REMP) was established for the Palo Verde Nuclear                  Generating Station (PVNGS) by APS in 1979. This report contains the measurements and findings for 2017. All references are specifically identified in Section 12.
Overview  The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in exposure pathways. REMP measures radionuclides that lead to the highest potential radiation exposures to members of the public resulting from station operation. This monitoring program implements Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix I, Section IV.B.2., 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 US Nuclear Regulatory Commission (USNRC) in their Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (incorporated into NUREG 1301). Results from the REMP help to evaluate sources of elevated levels of radioactivity in the environment (i.e. atmospheric nuclear detonations or abnormal plant releases). The Land Use Census ensures that changes in the use of areas at, and beyond the site boundary, are identified and that modifications to the REMP are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part  
Overview  The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in exposure pathways. REMP measures radionuclides that lead to the highest potential radiation exposures to members of the public resulting from station operation. This monitoring program implements Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix I, Section IV.B.2., 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 US Nuclear Regulatory Commission (USNRC) in their Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (incorporated into NUREG 1301). Results from the REMP help to evaluate sources of elevated levels of radioactivity in the environment (i.e. atmospheric nuclear detonations or abnormal plant releases). The Land Use Census ensures that changes in the use of areas at, and beyond the site boundary, are identified and that modifications to the REMP are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part
: 50. The 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 10 CFR 50, Appendix I, Section IV.B.2. Results of the PVNGS pre-operational environmental monitoring program are presented in Reference 1. The initial criticality of Unit 1 occurred May 25, 1985. Initial criticality for Units 2 and 3 were April 18, 1986, and October 25, 1987, respectively. PVNGS operational findings (historical) are presented in Reference 2.   
: 50. The 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 10 CFR 50, Appendix I, Section IV.B.2. Results of the PVNGS pre-operational environmental monitoring program are presented in Reference 1. The initial criticality of Unit 1 occurred May 25, 1985. Initial criticality for Units 2 and 3 were April 18, 1986, and October 25, 1987, respectively. PVNGS operational findings (historical) are presented in Reference 2.   


Radiation and Radioactivity Atoms are the basic building blocks of matter. Unstable atoms emit radiation and material that spontaneously emits radiation is referred to as radioactive. Radioactive material is frequently categorized as either "Natural" or "Man-made" Natural sources of radiation exist naturally in the environment and include:  radon, thoron, cosmic, terrestrial, and internal. The sun and stars are a source of cosmic radiation.
Radiation and Radioactivity Atoms are the basic building blocks of matter. Unstable atoms emit radiation and material that spontaneously emits radiation is referred to as radioactive. Radioactive material is frequently categorized as either "Natural" or "Man-made" Natural sources of radiation exist naturally in the environment and include:  radon, thoron, cosmic, terrestrial, and internal. The sun and stars are a source of cosmic radiation.
Atmospheric conditions, the Earth's magnetic field, and differences in elevation can affect the amount, or dose, of cosmic radiation an individual receives. The Earth is a source of terrestrial radiation. Uranium, thorium, and radium exist naturally in rock and soil. All organic matter contains carbon and potassium, and water contains small amounts of dissolved uranium and thorium. The largest contributor of dose to Americans from natural sources is attributed to radon which is found in air. All people are a source of internal radiation. Potassium-40 and carbon-14 are radioactive nuclides and inside all people from birth, making people a source of exposure. Man-made sources of radiation include:  consumer products, nuclear medicine, and medical procedures. There are a number of occupational areas which result in exposure to individuals of varying amounts of radiation such as:  radiography, radiology, radiation oncology, power generation, and research laboratories. The Nuclear Regulatory Commission (NRC) requires licensees to monitor exposure to workers and limit occupational exposure to 5,000 millirem. Several consumer products contain radioactive material such as:  some ceramics, thorium lantern mantles, luminous watches containing tritium, smoke detectors, and tobacco. Other consumer product sources of radiation can come from building and road construction materials, combustible fuels (i.e. gas, coal), and x-ray security systems. Th e most significant contributor to radiation exposure from man-made sources is medical procedures. Diagnostic x-rays and nuclear medicine procedures, such as those that use iodine-131 or cesium-137, are examples of man-made medical sources. The average member of the public receives a total annual dose of approximately 620 millirem from ionizing radiation. Figure 1-1 illustrates the contribution of various sources of radiation to radiation exposure in the United States (NCRP Report No.160 (2009)).
Atmospheric conditions, the Earth's magnetic field, and differences in elevation can affect the amount, or dose, of cosmic radiation an individual receives. The Earth is a source of terrestrial radiation. Uranium, thorium, and radium exist naturally in rock and soil. All organic matter contains carbon and potassium, and water contains small amounts of dissolved uranium and thorium. The largest contributor of dose to Americans from natural sources is attributed to radon which is found in air. All people are a source of internal radiation. Potassium-40 and carbon-14 are radioactive nuclides and inside all people from birth, making people a source of exposure. Man-made sources of radiation include:  consumer products, nuclear medicine, and medical procedures. There are a number of occupational areas which result in exposure to individuals of varying amounts of radiation such as:  radiography, radiology, radiation oncology, power generation, and research laboratories. The Nuclear Regulatory Commission (NRC) requires licensees to monitor exposure to workers and limit occupational exposure to 5,000 millirem. Several consumer products contain radioactive material such as:  some ceramics, thorium lantern mantles, luminous watches containing tritium, smoke detectors, and tobacco. Other consumer product sources of radiation can come from building and road construction materials, combustible fuels (i.e. gas, coal), and x-ray security systems. Th e most significant contributor to radiation exposure from man-made sources is medical procedures. Diagnostic x-rays and nuclear medicine procedures, such as those that use iodine-131 or cesium-137, are examples of man-made medical sources. The average member of the public receives a total annual dose of approximately 620 millirem from ionizing radiation. Figure 1-1 illustrates the contribution of various sources of radiation to radiation exposure in the United States (NCRP Report No.160 (2009)).
Figure 1-1 Sources of Radiation Exposure in the United States Sources of Radiation Exposure in the United States
Figure 1-1 Sources of Radiation Exposure in the United States Sources of Radiation Exposure in the United States
: 2. Description of the Monitoring Program APS and vendor organizations performed the pre-operational Radiological Environmental Monitoring Program between 1979 and 1985. APS and vendors continued the program into the operational phase. 2.1 Radiological Environmental Monitoring Program The assessment program consists of routine measurements of environmental gamma radiation and of radionuclide concentrations in media such as air, groundwater, drinking water, surface water, vegetation, milk, sludge, and sediment.
: 2. Description of the Monitoring Program APS and vendor organizations performed the pre-operational Radiological Environmental Monitoring Program between 1979 and 1985. APS and vendors continued the program into the operational phase. 2.1 Radiological Environmental Monitoring Program The assessment program consists of routine measurements of environmental gamma radiation and of radionuclide concentrations in media such as air, groundwater, drinking water, surface water, vegetation, milk, sludge, and sediment.
Samples were collected by APS at the monitoring sites shown in Figures 2-1 and 2-2. The specific sample types, sampling locations, and sampling frequencies, as set forth in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2-l, 2-2 and 9-1. Additional onsite sampling (outside the scope of the ODCM) is performed to supplement the REMP. All results are included in this report. Routine sample analyses were performed at the onsite Central Chemistry Laboratory and Operating Unit laboratories. Analyses for hard-to-detect radionuclides were performed by GEL Laboratories LLC.
Samples were collected by APS at the monitoring sites shown in Figures 2-1 and 2-2. The specific sample types, sampling locations, and sampling frequencies, as set forth in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2-l, 2-2 and 9-1. Additional onsite sampling (outside the scope of the ODCM) is performed to supplement the REMP. All results are included in this report. Routine sample analyses were performed at the onsite Central Chemistry Laboratory and Operating Unit laboratories. Analyses for hard-to-detect radionuclides were performed by GEL Laboratories LLC.
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Table 2-2 Sample Collection Schedule SAMPLE SITE # AIRBORNE PARTICULATE MILK AIRBORNE RADIOIODINE VEGETATION GROUND WATER DRINKING WATER SURFACE WATER 4 W  W 6A W  W 7A W  W 14A W  W 15 W  W 17A W  W 21 W  W 29 W  W 35 W  W 40 W  W 46    W 47    M/AA  48    W 49    W 51  M/AA M/AA  53  M/AA  54  M/AA  55    W 57    Q  58    Q  59    Q 60    Q 61    Q 62    M/AA 63    Q 64    Q  W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY  
Table 2-2 Sample Collection Schedule SAMPLE SITE # AIRBORNE PARTICULATE MILK AIRBORNE RADIOIODINE VEGETATION GROUND WATER DRINKING WATER SURFACE WATER 4 W  W 6A W  W 7A W  W 14A W  W 15 W  W 17A W  W 21 W  W 29 W  W 35 W  W 40 W  W 46    W 47    M/AA  48    W 49    W 51  M/AA M/AA  53  M/AA  54  M/AA  55    W 57    Q  58    Q  59    Q 60    Q 61    Q 62    M/AA 63    Q 64    Q  W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY  


Table 2-3 Summaries of the REMP Deviations/Abnormal Events Deviation/Abnormal Event Actions Taken  
Table 2-3 Summaries of the REMP Deviations/Abnormal Events Deviation/Abnormal Event Actions Taken
: 1. Air Sample Site 35 had reduced pump runtime; sample INVALID for sample period 12/27/2016-1/3/2017  Air Sample Station, Site 35, had excessively low run time for Week 1 of 2017. Pump was running at beginning and end of sampling period, but runtime indicates a sample volume of 238 m
: 1. Air Sample Site 35 had reduced pump runtime; sample INVALID for sample period 12/27/2016-1/3/2017  Air Sample Station, Site 35, had excessively low run time for Week 1 of 2017. Pump was running at beginning and end of sampling period, but runtime indicates a sample volume of 238 m
: 3. This volume is <55% of normal volume. Sample is considered INVALID for sample period 12/27/2016-1/3/2017 due to low sample volume. Event documented through CR 18-03209 (Table 8-1 and 8-4, Note  
: 3. This volume is <55% of normal volume. Sample is considered INVALID for sample period 12/27/2016-1/3/2017 due to low sample volume. Event documented through CR 18-03209 (Table 8-1 and 8-4, Note
: 1) 2. Air Samples Site 15 Particulate Filter had small hole for sample period 1/10/2017-1/17/2017 Air Sample Site 15 particulate filter paper was found to have small hole, which is contrary from a normal intact filter. Sample volume, filter loading, and filter deposition is normal. This sample is considered VALID. Event documented through CR 17-00760 (Table 8-1 and 8-4, Note 2)  
: 1) 2. Air Samples Site 15 Particulate Filter had small hole for sample period 1/10/2017-1/17/2017 Air Sample Site 15 particulate filter paper was found to have small hole, which is contrary from a normal intact filter. Sample volume, filter loading, and filter deposition is normal. This sample is considered VALID. Event documented through CR 17-00760 (Table 8-1 and 8-4, Note 2)
: 3. Air Sample Site 6A found not running due to lack of power 4/26/2017 Air Sample Site 6A pump found not running. Troubleman corrected power issue, returning pump to service. Normal volume per sample period is approximately 433 m
: 3. Air Sample Site 6A found not running due to lack of power 4/26/2017 Air Sample Site 6A pump found not running. Troubleman corrected power issue, returning pump to service. Normal volume per sample period is approximately 433 m
: 3. Volume for this sampling period was 209 m 3. Sample determined to be INVALID for sample period 4/18/2017-4/26/2017, due to insufficient sample volume. Event documented through CR 17-06259 (Table 8-1and 8-4, Note 3).  
: 3. Volume for this sampling period was 209 m 3. Sample determined to be INVALID for sample period 4/18/2017-4/26/2017, due to insufficient sample volume. Event documented through CR 17-06259 (Table 8-1and 8-4, Note 3).
: 4. Air Sample Site 6A found with no power at the pole 7/25/2017 Air Sample Site 6A was found to have no power at the pole. Troubleman was dispatched and power was restored. Normal volume per sample period is approximately 433 m
: 4. Air Sample Site 6A found with no power at the pole 7/25/2017 Air Sample Site 6A was found to have no power at the pole. Troubleman was dispatched and power was restored. Normal volume per sample period is approximately 433 m
: 3. Volume for this sampling period was 270 m 3 for sample period 7/18/17-7/25/2017 and pump was inoperable for sample period 7/25/2017-8/1/2017. Sample was determined to be INVALID for sample periods 7/18/17-8/1/2017, due to insufficient sample volume. Event documented through CR 17-10693 (Table 8-2 and 8-5, Note 4).  
: 3. Volume for this sampling period was 270 m 3 for sample period 7/18/17-7/25/2017 and pump was inoperable for sample period 7/25/2017-8/1/2017. Sample was determined to be INVALID for sample periods 7/18/17-8/1/2017, due to insufficient sample volume. Event documented through CR 17-10693 (Table 8-2 and 8-5, Note 4).
: 5. Milk Sample Site 53 analysis did not achieve required Lower Limits of Detection for I-131 for June sample  An error in the Multi-channel Analyzer software, causing a reduced count time, resulted in a MDA of 1.05 pCi/L for I-131 in the June Milk Sample for Site 53. This is contrary to the ODCM required LLD for I-131 of 1 pCi/L. No activity was detected in this sample. Event documented through CR 17-10463 (Table 8-7, Note 1).
: 5. Milk Sample Site 53 analysis did not achieve required Lower Limits of Detection for I-131 for June sample  An error in the Multi-channel Analyzer software, causing a reduced count time, resulted in a MDA of 1.05 pCi/L for I-131 in the June Milk Sample for Site 53. This is contrary to the ODCM required LLD for I-131 of 1 pCi/L. No activity was detected in this sample. Event documented through CR 17-10463 (Table 8-7, Note 1).
: 6. Drinking Water Sample Site 48 did not achieve required Lower Limits of Detection for La-140 for April sample Drinking Water Sample for Site 48 did not reach the ODCM required LLD due to sample collection date input error into analysis software. The ODCM required LLD for La-140 is 15 pCi/L. Analysis of sample reported a MDA of 22 pCi/L for La-140. No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 1).    
: 6. Drinking Water Sample Site 48 did not achieve required Lower Limits of Detection for La-140 for April sample Drinking Water Sample for Site 48 did not reach the ODCM required LLD due to sample collection date input error into analysis software. The ODCM required LLD for La-140 is 15 pCi/L. Analysis of sample reported a MDA of 22 pCi/L for La-140. No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 1).
: 7. Drinking Water Sample Site 46, 49, and 55 did not achieve required Lower Limits of Detection for I-131 and La-140 for April sample Drinking Water Sample for Site 46, 49, and 55 did not reach the ODCM required LLD due to sample collection date input error into analysis software. The ODCM required LLD for I-131 and La-140 is 15 pCi/L. Analysis of sample reported a MDA of 17 pCi/L for I-131 and 185 pCi/L (Site 46), 17 pCi/L for I-131 and 200 pCi/L for La-140 (Site 49), and 19 pCi/L for I-131 and 22 pCi/L for La-140 (Site 55). No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 2).    
: 7. Drinking Water Sample Site 46, 49, and 55 did not achieve required Lower Limits of Detection for I-131 and La-140 for April sample Drinking Water Sample for Site 46, 49, and 55 did not reach the ODCM required LLD due to sample collection date input error into analysis software. The ODCM required LLD for I-131 and La-140 is 15 pCi/L. Analysis of sample reported a MDA of 17 pCi/L for I-131 and 185 pCi/L (Site 46), 17 pCi/L for I-131 and 200 pCi/L for La-140 (Site 49), and 19 pCi/L for I-131 and 22 pCi/L for La-140 (Site 55). No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 2).
: 8. Drinking Water Sample Site 49 did not achieve required Lower Limits of Detection for La-140 for July sample Drinking Water Sample for Site 49 did not reach the ODCM required LLD due to excessive time between sample acquisition and analysis. The ODCM required LLD for La-140 is 15 pCi/L. Analysis of sample reported a MDA of 150 pCi/L for La-140. No activity was detected in this sample. Event documented through CR 18-00109 (Table 8-8, Note 4).
: 8. Drinking Water Sample Site 49 did not achieve required Lower Limits of Detection for La-140 for July sample Drinking Water Sample for Site 49 did not reach the ODCM required LLD due to excessive time between sample acquisition and analysis. The ODCM required LLD for La-140 is 15 pCi/L. Analysis of sample reported a MDA of 150 pCi/L for La-140. No activity was detected in this sample. Event documented through CR 18-00109 (Table 8-8, Note 4).
: 9. Evaporation Pond 1C, 2 nd Quarter Tritium sample INVALID due to reporting error. Evaporation Pond 1C, 2 nd Quarter Tritium sample had abnormally low tritium results (<320 pCi/L). Investigation of this sample analysis revealed a reporting error. Sample could not be reanalyzed.
: 9. Evaporation Pond 1C, 2 nd Quarter Tritium sample INVALID due to reporting error. Evaporation Pond 1C, 2 nd Quarter Tritium sample had abnormally low tritium results (<320 pCi/L). Investigation of this sample analysis revealed a reporting error. Sample could not be reanalyzed.
Sample results determined to be INVALAD due to reporting error. Correction to the reporting file was made and the 3 rd Quarter results for this location were consistent with historical trends. Event is documented for trending with CR 18-00638 (Table 8-10, Note 1).  
Sample results determined to be INVALAD due to reporting error. Correction to the reporting file was made and the 3 rd Quarter results for this location were consistent with historical trends. Event is documented for trending with CR 18-00638 (Table 8-10, Note 1).
: 10. Water Reclamation Facility Influent sample analysis did not achieve several Lower Limits of Detection 1/24/2017  Water Reclamation Facility Influent sample volume incorrectly entered into analysis software, resulting in several missed LLDs. PVNGS receives waste water from the City of Phoenix. Water samples of the Influent are analyzed for trending purposes and do not contain plant related effluents. Event documented for trending purposes with CR 17-17823 (Table 8-10, Note 3).  
: 10. Water Reclamation Facility Influent sample analysis did not achieve several Lower Limits of Detection 1/24/2017  Water Reclamation Facility Influent sample volume incorrectly entered into analysis software, resulting in several missed LLDs. PVNGS receives waste water from the City of Phoenix. Water samples of the Influent are analyzed for trending purposes and do not contain plant related effluents. Event documented for trending purposes with CR 17-17823 (Table 8-10, Note 3).
: 11. Water Reclamation Facility Influent sample analysis did not achieve several Lower Limits of Detection 3/14/2017  Water Reclamation Facility Influent did not achieve several LLDs due to delay in sample analysis. PVNGS receives waste water from the City of Phoenix. Water samples of the Influent are analyzed for trending purposes and do not contain plant related effluents. Event documented for trending purposes with CR 17-04054 (Table 8-10, Note 4). 12. Sedimentation Basin sample analysis did not achieve several Lower Limits of Detection 1/24/2017  Sedimentation Basin sample volume incorrectly entered into analysis software, resulting in several missed LLDs. PVNGS is a zero liquid release plant; water in this basin is the result of rain water and rain runoff. Water samples of this basin are confirmatory and are analyzed for trending purposes. Event documented for trending purposes with CR 17-17823 (Table 8-10, Note 3).  
: 11. Water Reclamation Facility Influent sample analysis did not achieve several Lower Limits of Detection 3/14/2017  Water Reclamation Facility Influent did not achieve several LLDs due to delay in sample analysis. PVNGS receives waste water from the City of Phoenix. Water samples of the Influent are analyzed for trending purposes and do not contain plant related effluents. Event documented for trending purposes with CR 17-04054 (Table 8-10, Note 4). 12. Sedimentation Basin sample analysis did not achieve several Lower Limits of Detection 1/24/2017  Sedimentation Basin sample volume incorrectly entered into analysis software, resulting in several missed LLDs. PVNGS is a zero liquid release plant; water in this basin is the result of rain water and rain runoff. Water samples of this basin are confirmatory and are analyzed for trending purposes. Event documented for trending purposes with CR 17-17823 (Table 8-10, Note 3).
: 13. Site 54 Milk sample was not collected within the required frequency for July 2017  The July Site 54 Milk was not collected within required frequency, per procedural guidance. The June sample was collected on 6/9/17 and the July sample was not collected until 7/20/17 due to unavailability the week before. Per the ODCM, the sample needs to be collected monthly; procedural guidance and the ODCM directs that sample be collected within the 125% surveillance test time period of 38 days, 18 hours. All samples were collected and analyzed to the ODCM required LLD, confirming that there was no plant related impact via the milk ingestion pathway. Event documented through CR 17-10466.  
: 13. Site 54 Milk sample was not collected within the required frequency for July 2017  The July Site 54 Milk was not collected within required frequency, per procedural guidance. The June sample was collected on 6/9/17 and the July sample was not collected until 7/20/17 due to unavailability the week before. Per the ODCM, the sample needs to be collected monthly; procedural guidance and the ODCM directs that sample be collected within the 125% surveillance test time period of 38 days, 18 hours. All samples were collected and analyzed to the ODCM required LLD, confirming that there was no plant related impact via the milk ingestion pathway. Event documented through CR 17-10466.
: 14. Vegetation control locations, Site 62, did not collect procedurally required mass for each vegetation sample for October 2017. Procedural guidance directs that vegetation samples obtained be a minimum of 0.6 kg. The October 2017 samples for Site 62 (REMP Control Location) did not satisfy this requirement; 3 vegetation types of 0.519kg, 0.413kg, and 0.372kg were collected. There was no impact to the requirements of the ODCM as these are control samples with no resident samples available, as well as supplemental air samples collected weekly as a contingency. Additionally, the mass of vegetation was adequate to obtain valid analysis results, which are included in Table 8-6. Event documented through CR 17-15048.  
: 14. Vegetation control locations, Site 62, did not collect procedurally required mass for each vegetation sample for October 2017. Procedural guidance directs that vegetation samples obtained be a minimum of 0.6 kg. The October 2017 samples for Site 62 (REMP Control Location) did not satisfy this requirement; 3 vegetation types of 0.519kg, 0.413kg, and 0.372kg were collected. There was no impact to the requirements of the ODCM as these are control samples with no resident samples available, as well as supplemental air samples collected weekly as a contingency. Additionally, the mass of vegetation was adequate to obtain valid analysis results, which are included in Table 8-6. Event documented through CR 17-15048.
: 15. Site 6 Environmental Dosimetry missing for 4 th Quarter 2017. During the 4 th Quarter Environmental Dosimetry change-out, it was discovered that the Site 6 dosimetry and stanchion was missing and could not be located. The stanchion and dosimetry were replaced for the 1 st Quarter 2018 sampling period. Event documented through CR 17-18260.
: 15. Site 6 Environmental Dosimetry missing for 4 th Quarter 2017. During the 4 th Quarter Environmental Dosimetry change-out, it was discovered that the Site 6 dosimetry and stanchion was missing and could not be located. The stanchion and dosimetry were replaced for the 1 st Quarter 2018 sampling period. Event documented through CR 17-18260.
: 3. Sample Collection Program APS Personnel, using PVNGS procedures, collected all samples. 3.1 Water Weekly samples were collected from four (4) residence wells for monthly and quarterly composites. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. The samples were analyzed for gross beta, gamma-emitting radionuclides, and tritium. Quarterly grab samples were collected from the 45 and 85 acre Reservoirs, Evaporation Ponds 1A/B/C, 2A/B, and 3A/B, and onsite wells 34abb and 27ddc. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. Samples were analyzed for gamma-emitting radionuclides and tritium.
: 3. Sample Collection Program APS Personnel, using PVNGS procedures, collected all samples. 3.1 Water Weekly samples were collected from four (4) residence wells for monthly and quarterly composites. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. The samples were analyzed for gross beta, gamma-emitting radionuclides, and tritium. Quarterly grab samples were collected from the 45 and 85 acre Reservoirs, Evaporation Ponds 1A/B/C, 2A/B, and 3A/B, and onsite wells 34abb and 27ddc. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. Samples were analyzed for gamma-emitting radionuclides and tritium.
Treated sewage effluent from the City of Phoenix was sampled as a weekly composite at the onsite Water Resources (WR), and analyzed for gamma-emitting radionuclides. A monthly composite was analyzed for tritium. 3.2 Vegetation Vegetation samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides.
Treated sewage effluent from the City of Phoenix was sampled as a weekly composite at the onsite Water Resources (WR), and analyzed for gamma-emitting radionuclides. A monthly composite was analyzed for tritium. 3.2 Vegetation Vegetation samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides.
3.3 Milk  Goat milk samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides, including low level I-131.
3.3 Milk  Goat milk samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides, including low level I-131.
3.4 Air  Air particulate filters and charcoal cartridges were collected at ten (10) sites on a weekly basis. Particulate filters were analyzed for gross beta. Charcoal cartridges were analyzed for Iodine-131. Particulate filters were composited quarterly, by location, and analyzed for gamma-emitting radionuclides. 3.5 Soil, Sludge, and Sediment Sludge samples were obtained weekly from the WR waste centrifuge (during operational periods) and analyzed for gamma-emitting radionuclides. Cooling tower sludge was analyzed for gamma-emitting radionuclides prior to disposal in the WR sludge landfill.  
3.4 Air  Air particulate filters and charcoal cartridges were collected at ten (10) sites on a weekly basis. Particulate filters were analyzed for gross beta. Charcoal cartridges were analyzed for Iodine-131. Particulate filters were composited quarterly, by location, and analyzed for gamma-emitting radionuclides. 3.5 Soil, Sludge, and Sediment Sludge samples were obtained weekly from the WR waste centrifuge (during operational periods) and analyzed for gamma-emitting radionuclides. Cooling tower sludge was analyzed for gamma-emitting radionuclides prior to disposal in the WR sludge landfill.
: 4. Analytical Procedures The procedures described in this report are those used by APS to routinely analyze samples 4.1 Air Particulate 4.1.1 Gross Beta A glass fiber filter sample is placed in a stainless steel planchet and counted for gross beta activity utilizing a low background gas flow proportional counter.  
: 4. Analytical Procedures The procedures described in this report are those used by APS to routinely analyze samples 4.1 Air Particulate 4.1.1 Gross Beta A glass fiber filter sample is placed in a stainless steel planchet and counted for gross beta activity utilizing a low background gas flow proportional counter.  


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: 3) acid is added and the sample is evaporated down to about twenty (20) milliliters. The remaining sample is transferred to a stainless steel planchet. The sample is heated to dryness and counted for gross beta in a gas flow proportional counter.  
: 3) acid is added and the sample is evaporated down to about twenty (20) milliliters. The remaining sample is transferred to a stainless steel planchet. The sample is heated to dryness and counted for gross beta in a gas flow proportional counter.  


4.7 Soil 4.7.1 Gamma Spectroscopy The samples are sieved, placed in a one-liter plastic marinelli beaker, and weighed. The samples are then counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.
4.7 Soil 4.7.1 Gamma Spectroscopy The samples are sieved, placed in a one-liter plastic marinelli beaker, and weighed. The samples are then counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.
: 5. Nuclear Instrumentation  
: 5. Nuclear Instrumentation  


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===5.2 Liquid===
===5.2 Liquid===
Scintillation Spectrometer A Beckman LS-6500 Liquid Scintillation Counter is used for tritium determinations. The system background averages approximately 12-16 cpm with a counting efficiency of approximately 40% using a quenched standard. 5.3 Gas Flow Proportional Counter The Tennelec S5E is a low background gas flow proportional counter for gross beta analysis. The system contains an automatic sample changer capable of counting 50 samples in succession. Average beta background count rate is about 1-2 cpm with a beta efficiency of approximately 30% for Cs-137.
Scintillation Spectrometer A Beckman LS-6500 Liquid Scintillation Counter is used for tritium determinations. The system background averages approximately 12-16 cpm with a counting efficiency of approximately 40% using a quenched standard. 5.3 Gas Flow Proportional Counter The Tennelec S5E is a low background gas flow proportional counter for gross beta analysis. The system contains an automatic sample changer capable of counting 50 samples in succession. Average beta background count rate is about 1-2 cpm with a beta efficiency of approximately 30% for Cs-137.
: 6. Isotopic Detection Limits and Reporting Criteria 6.1 Lower Limits of Detection The lower limits of detection (LLD) and the method for calculation are specified in the PVNGS ODCM, Reference 4. The ODCM required a priori LLDs are presented in Table 6-1. 6.2 Data Reporting Criteria All results that are greater than the Minimum Detectable Activity (MDA) (a posteriori LLD) are reported as positive activity with its associated 2counting error. All results that are less than the MDA are reported as less than values at the associated MDA. For example, if the MDA is 12 pCi/liter, the value is reported as <12.
: 6. Isotopic Detection Limits and Reporting Criteria 6.1 Lower Limits of Detection The lower limits of detection (LLD) and the method for calculation are specified in the PVNGS ODCM, Reference 4. The ODCM required a priori LLDs are presented in Table 6-1. 6.2 Data Reporting Criteria All results that are greater than the Minimum Detectable Activity (MDA) (a posteriori LLD) are reported as positive activity with its associated 2counting error. All results that are less than the MDA are reported as less than values at the associated MDA. For example, if the MDA is 12 pCi/liter, the value is reported as <12.
Typical MDA values are presented in Table 6-3.
Typical MDA values are presented in Table 6-3.
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Background fluctuations  Unavoidably small sample sizes  The presence of interfering radionuclides  Self-absorption corrections  Decay corrections for short half-life radionuclides  Other uncontrollable circumstances In these instances, the contributing factors will be noted in the table where the data are presented. A summary of deviations/abnormal events is presented in Table 2-3 Summaries of  
Background fluctuations  Unavoidably small sample sizes  The presence of interfering radionuclides  Self-absorption corrections  Decay corrections for short half-life radionuclides  Other uncontrollable circumstances In these instances, the contributing factors will be noted in the table where the data are presented. A summary of deviations/abnormal events is presented in Table 2-3 Summaries of  


the REMP Deviations/Abnormal Events and includes a description of any sample results that did not meet a priori LLD requirements. 6.3 LLD and Reporting Criteria Overview Making a reasonable estimate of the limits of detection for a counting procedure or a radiochemical method is usually complicated by the presence of significant background. It must be considered that the background or blank is not a fixed value but that a series of replicates would be normally distributed. The desired net activity is the difference between the gross and background activity distributions. The interpretation of this difference becomes a problem if the two distributions intersect as indicated in the diagram.  
the REMP Deviations/Abnormal Events and includes a description of any sample results that did not meet a priori LLD requirements. 6.3 LLD and Reporting Criteria Overview Making a reasonable estimate of the limits of detection for a counting procedure or a radiochemical method is usually complicated by the presence of significant background. It must be considered that the background or blank is not a fixed value but that a series of replicates would be normally distributed. The desired net activity is the difference between the gross and background activity distributions. The interpretation of this difference becomes a problem if the two distributions intersect as indicated in the diagram.
: 3. Background Count Rate:  Any counter will show a certain counting rate without a sample in position. This background counting rate comes from several sources:  1) natural environmental radiation from the surrounding materials, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background counting rate will depend on the amounts of these types of radiation and the sensitivity of the counter to the radiation.  
: 3. Background Count Rate:  Any counter will show a certain counting rate without a sample in position. This background counting rate comes from several sources:  1) natural environmental radiation from the surrounding materials, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background counting rate will depend on the amounts of these types of radiation and the sensitivity of the counter to the radiation.
: 4. Background and Sample Counting Time:  The amount of time devoted to the counting of the background depends on the level of activity being measured. In general, with low level samples, this time should be about equal to that devoted to counting a sample.  
: 4. Background and Sample Counting Time:  The amount of time devoted to the counting of the background depends on the level of activity being measured. In general, with low level samples, this time should be about equal to that devoted to counting a sample.
: 5. Time Interval between Sample Collection and Counting:  Decay measurements are useful in identifying certain short-lived nuclides. The disintegration constant is one of the basic characteristics of a specific radionuclide and is readily determined, if the half-life is sufficiently short. To  ensure  the  required  LLDs  are  achieved,  appropriate  decay correction  values  are  used  to  account  for  radioactive  decay  during transit  time  and  sample processing.  
: 5. Time Interval between Sample Collection and Counting:  Decay measurements are useful in identifying certain short-lived nuclides. The disintegration constant is one of the basic characteristics of a specific radionuclide and is readily determined, if the half-life is sufficiently short. To  ensure  the  required  LLDs  are  achieved,  appropriate  decay correction  values  are  used  to  account  for  radioactive  decay  during transit  time  and  sample processing.  


Table 6-3 Typical MDA Values Analysis/Nuclide Water (pCi/liter) Milk (pCi/liter) Airborne Particulate or Gas (pCi/m
Table 6-3 Typical MDA Values Analysis/Nuclide Water (pCi/liter) Milk (pCi/liter) Airborne Particulate or Gas (pCi/m
: 3) Vegetation (pCi/kg, wet) Gross Beta 2.08 0.004  H-3 326  Mn-54 10 Fe-59 20 Co-58 9 Co-60 11 Zn-65 22 Zr-95 16 Nb-95 10 I-131 10 a 1 0.04 b 49 Cs-134 9 1 0.003 b 47 Cs-137 10 1 0.003 b 61 Ba-140 33 3  La-140 13 1 NOTES:  a - low level I-131 is not required since there is no drinking water pathway  b - Based on 433 m 3, the normal weekly sample volume  
: 3) Vegetation (pCi/kg, wet) Gross Beta 2.08 0.004  H-3 326  Mn-54 10 Fe-59 20 Co-58 9 Co-60 11 Zn-65 22 Zr-95 16 Nb-95 10 I-131 10 a 1 0.04 b 49 Cs-134 9 1 0.003 b 47 Cs-137 10 1 0.003 b 61 Ba-140 33 3  La-140 13 1 NOTES:  a - low level I-131 is not required since there is no drinking water pathway  b - Based on 433 m 3, the normal weekly sample volume
: 7. Interlaboratory Comparison Program  
: 7. Interlaboratory Comparison Program  


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Table 7-1 Interlaboratory Comparison Results (Continued)
Table 7-1 Interlaboratory Comparison Results (Continued)
Sample  Analysis ERA PT Nuclide Units PVNGS Assigned Value 1 Acceptance Limit 2 Results Type Type Study    Value Water Tritium RAD-111 H-3 pCi/L 5,910 6,250 5390-6880 Acceptable Water Gamma RAD-111 Ba-133 pCi/L 73.3 73.7 61.7-81.1 Acceptable Cs-134 pCi/L 45.7 53 42.8-58.3 Acceptable Cs-137 pCi/L 51.5 52.9 47.6-61.1 Acceptable Co-60 pCi/L 68.1 69.5 62.6-78.9 Acceptable Zn-65 pCi/L 374 348 313-406 Acceptable 1 The ERA assigned values are established per the guidelines contained in the National Environmental Laboratory Accreditation Conference (NELAC) program criteria as applicable.
Sample  Analysis ERA PT Nuclide Units PVNGS Assigned Value 1 Acceptance Limit 2 Results Type Type Study    Value Water Tritium RAD-111 H-3 pCi/L 5,910 6,250 5390-6880 Acceptable Water Gamma RAD-111 Ba-133 pCi/L 73.3 73.7 61.7-81.1 Acceptable Cs-134 pCi/L 45.7 53 42.8-58.3 Acceptable Cs-137 pCi/L 51.5 52.9 47.6-61.1 Acceptable Co-60 pCi/L 68.1 69.5 62.6-78.9 Acceptable Zn-65 pCi/L 374 348 313-406 Acceptable 1 The ERA assigned values are established per the guidelines contained in the National Environmental Laboratory Accreditation Conference (NELAC) program criteria as applicable.
2 "Acceptance Limits" have been calculated per ERA's Standard Operating Procedure for the Generation of Performance Acceptance Limits.  
2 "Acceptance Limits" have been calculated per ERA's Standard Operating Procedure for the Generation of Performance Acceptance Limits.
: 8. Data Interpretation and Conclusions Associated with the analytical process are potential random and systematic errors. Systematic errors can be caused by instrument malfunctions, incomplete precipitation, back scattering, and self-absorption.
: 8. Data Interpretation and Conclusions Associated with the analytical process are potential random and systematic errors. Systematic errors can be caused by instrument malfunctions, incomplete precipitation, back scattering, and self-absorption.
Efforts are made to minimize both systematic and random errors in the data reported. Systematic errors are minimized by performing reviews throughout the analysis. For example, instruments are checked routinely with radioactive sources, and recovery and self-absorption factors based on individual sample analyses are incorporated into the calculation equations where necessary. Random errors are reduced by comparing all data to historical data for the same site and performing comparisons between analytical results when available. In addition, when data do not appear to match historical results, analyses may be rerun on a separate aliquot of the sample to verify the presence of the activity. The acceptance of data is dependent upon the results of quality control samples and is part of the data review process for all analytical results.
Efforts are made to minimize both systematic and random errors in the data reported. Systematic errors are minimized by performing reviews throughout the analysis. For example, instruments are checked routinely with radioactive sources, and recovery and self-absorption factors based on individual sample analyses are incorporated into the calculation equations where necessary. Random errors are reduced by comparing all data to historical data for the same site and performing comparisons between analytical results when available. In addition, when data do not appear to match historical results, analyses may be rerun on a separate aliquot of the sample to verify the presence of the activity. The acceptance of data is dependent upon the results of quality control samples and is part of the data review process for all analytical results.
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SAMPLEDATE<15<15<30<15<30<15<30<15<15<18<60<15<3000LOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote25-Jul-17<11<9<17<9<21<9<14 1810<7<9<31<12<3721-Aug-17<10<11<18<10<17<8<15<10<9<10<33<88-Aug-17<9<8<13<7<20<9<15<13<9<7<31<1015-Aug-17<10<9<20<10<15<11<15 159<8<9<30<1522-Aug-17<12<10<18<12<24<10<1898<8<10<24<1329-Aug-17<11<11<20<11<24<12<19<12<10<12<28<9<3545-Sep-17<10<8<18<7<22<10<17<12<7<9<29<1012-Sep-17<10<10<20<7<22<10<13 3611<9<9<25<1219-Sep-17<11<12<21<9<24<9<19<13<8<9<30<1226-Sep-17<8<7<13<10<21<8<152010<7<8<28<10<3503-Oct-17<10<9<17<11<23<12<15138<7<7<29<1410-Oct-17WRF17-Oct-17 INFLUENT24-Oct-17<11<11<22<9<25<14<21 12<11<12<36<931-Oct-17<9<11<21<10<26<8<16149<8<9<33<12<3597-Nov-17<6<6<11<6<11<6<10116<5<6<18<1514-Nov-17<8<11<15<10<24<9<16<199<9<7<31<1221-Nov-17<11<11<18<8<20<9<214512<12<10<35<828-Nov-17<10<9<24<11<17<11<18<13<9<11<31<14<3505-Dec-17<12<8<18<8<22<9<16147<8<9<24<1012-Dec-17<9<5<14<8<15<7<15119<6<7<29<919-Dec-17<7<8<24<14<23<10<1599<7<7<29<1426-Dec-17<9<10<18<9<19<9<17<11<7<7<33<10<380WRF OUTAGE- No SampleSURFACE WATERODCM required samples denoted by *units are pCi/literWRF OUTAGE- No Sample Table 8-10 Surface Water (Continued)
SAMPLEDATE<15<15<30<15<30<15<30<15<15<18<60<15<3000LOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote25-Jul-17<11<9<17<9<21<9<14 1810<7<9<31<12<3721-Aug-17<10<11<18<10<17<8<15<10<9<10<33<88-Aug-17<9<8<13<7<20<9<15<13<9<7<31<1015-Aug-17<10<9<20<10<15<11<15 159<8<9<30<1522-Aug-17<12<10<18<12<24<10<1898<8<10<24<1329-Aug-17<11<11<20<11<24<12<19<12<10<12<28<9<3545-Sep-17<10<8<18<7<22<10<17<12<7<9<29<1012-Sep-17<10<10<20<7<22<10<13 3611<9<9<25<1219-Sep-17<11<12<21<9<24<9<19<13<8<9<30<1226-Sep-17<8<7<13<10<21<8<152010<7<8<28<10<3503-Oct-17<10<9<17<11<23<12<15138<7<7<29<1410-Oct-17WRF17-Oct-17 INFLUENT24-Oct-17<11<11<22<9<25<14<21 12<11<12<36<931-Oct-17<9<11<21<10<26<8<16149<8<9<33<12<3597-Nov-17<6<6<11<6<11<6<10116<5<6<18<1514-Nov-17<8<11<15<10<24<9<16<199<9<7<31<1221-Nov-17<11<11<18<8<20<9<214512<12<10<35<828-Nov-17<10<9<24<11<17<11<18<13<9<11<31<14<3505-Dec-17<12<8<18<8<22<9<16147<8<9<24<1012-Dec-17<9<5<14<8<15<7<15119<6<7<29<919-Dec-17<7<8<24<14<23<10<1599<7<7<29<1426-Dec-17<9<10<18<9<19<9<17<11<7<7<33<10<380WRF OUTAGE- No SampleSURFACE WATERODCM required samples denoted by *units are pCi/literWRF OUTAGE- No Sample Table 8-10 Surface Water (Continued)
SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote3-Jan-17<11<9<19<9<21<10<17<9<8<10
SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote3-Jan-17<11<9<19<9<21<10<17<9<8<10
<31<15<35010-Jan-1717-Jan-17 24-Jan-17<20<20<33<5<32<16<42<20<16<23<69<20<356 331-Jan-177-Feb-1714-Feb-1721-Feb-17<11<11<19<9<28<11<16<10<9<10<40<14595 21828-Feb-17<9<10<17<7<28<11<17<8<9<11<38<13<3527-Mar-1714-Mar-17 21-Mar-17 28-Mar-174-Apr-1711-Apr-1718-Apr-17 25-Apr-172-May-179-May-1716-May-1723-May-17 30-May-176-Jun-1713-Jun-1720-Jun-17 27-Jun-17SURFACE WATEREMPTY- No SampleEMPTY- No SampleEMPTY- No SampleODCM re quired sam ples denoted b y *units are pCi/literNote 3: Several LLDs not achieved due to incorrect volume entered into analysis system. CR 17-17823EMPTY- No SampleEMPTY- No Sample EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleSEDIMENTATION BASIN #2EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No Sample Table 8-10 Surface Water (Continued) SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote3-Jul-1711-Jul-1718-Jul-1725-Jul-17<6<6<12<5<13<5<11<6<6<6<20<14<3301-Aug-17 8-Aug-1715-Aug-1722-Aug-17<14<11<27<12<29<13<24<10<10<10<9<34929-Aug-175-Sep-1712-Sep-1719-Sep-17 26-Sep-173-Oct-1710-Oct-1717-Oct-1724-Oct-17 31-Oct-177-Nov-1714-Nov-1721-Nov-17 28-Nov-175-Dec-1712-Dec-1719-Dec-1726-Dec-17units are pCi/literODCM required samples denoted by *EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleSEDIMENTATION BASIN #2EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No Sample Table 8-11 Sludge/Sediment SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-111Notes3-Jan-17<68<10610-Jan-17 482163<118<16817-Jan-17 291156<80<11424-Jan-17 192138<40<13531-Jan-17<137<1687-Feb-17 788229<148<15514-Feb-17 695184<107<118 21-Feb-17 200133<127<17828-Feb-17 277163<61<1437-Mar-17<94<14114-Mar-17 469152<109<9321-Mar-17<102<17128-Mar-17 632165<117<1024-Apr-17 33191<51<8111-Apr-17 562186<128<18018-Apr-1725-Apr-17<116<1022-May-17<100<1119-May-17 724169<109<16216-May-17 891195<109<12323-May-17 919186<106<14630-May-17 467151<137<1206-Jun-17 959215<145<14813-Jun-17 654201<140<15920-Jun-17 679176<90<14427-Jun-17 348131<90<158SLUDGE/SEDIMENTWR OUTAGEWR CENTRIFUGE WASTE SLUDGEODCM required samples denoted by *units are pCi/kg, wet Table 8-11 Sludge/Sediment (Continued) SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-111Notes3-Jul-17 351147<146<16211-Jul-17 487151<35<3018-Jul-17 359144<126<14325-Jul-17 35344<23<231-Aug-17 498 191<146<1438-Aug-17 323137<106<16315-Aug-17<108<15522-Aug-17 314128<113<16929-Aug-17 364162<129<3215-Sep-17 415177<143<5112-Sep-17 481162<32<17819-Sep-17 264143<143<17726-Sep-17 427143<109<3053-Oct-17 510164<147<15510-Oct-17 423161<115<4217-Oct-1724-Oct-17 510138<81<8031-Oct-17 481141<65<307-Nov-17 375139<74<16214-Nov-17 646161<94<8221-Nov-17 523161<93<17728-Nov-17 302122<122<1165-Dec-17 363139<146<14512-Dec-17<125<15119-Dec-17 299169<139<11926-Dec-17 215120<146<169WR OUTAGEWR CENTRIFUGE WASTE SLUDGEODCM required samples denoted by *units are pCi/kg, wet Table 8-11 Sludge/Sediment (Continued) Cooling Tower Sludge Unit Cycle Approximate Volume (yd 3) Isotope Activity Range (pCi/g) Sample Type U2R20 302 All principal gamma-emitters <MDA Towers/Canal Sludge U1R20 512 All principal gamma-emitters <MDA Towers/Canal Sludge Table 8-12 Hard -To-Detect Radionuclide Results Hard-To-Detect Radionuclide (pCi/Liter) Sample Location Well number Sample Date C-14 Fe-55 Ni-63 Sr-90 Unit 1 (outside RCA) APP-12 11/9/2017 <66.7 <18.3 <2.39 <1.58 Unit 2 (inside RCA) H0A 11/3/2017 <67.1 <21.5 <2.68 <1.06 Unit 3 (inside RCA) H11 10/24/2017 <67.9 <19.9 <3.19 <1.03  
<31<15<35010-Jan-1717-Jan-17 24-Jan-17<20<20<33<5<32<16<42<20<16<23<69<20<356 331-Jan-177-Feb-1714-Feb-1721-Feb-17<11<11<19<9<28<11<16<10<9<10<40<14595 21828-Feb-17<9<10<17<7<28<11<17<8<9<11<38<13<3527-Mar-1714-Mar-17 21-Mar-17 28-Mar-174-Apr-1711-Apr-1718-Apr-17 25-Apr-172-May-179-May-1716-May-1723-May-17 30-May-176-Jun-1713-Jun-1720-Jun-17 27-Jun-17SURFACE WATEREMPTY- No SampleEMPTY- No SampleEMPTY- No SampleODCM re quired sam ples denoted b y *units are pCi/literNote 3: Several LLDs not achieved due to incorrect volume entered into analysis system. CR 17-17823EMPTY- No SampleEMPTY- No Sample EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleSEDIMENTATION BASIN #2EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No Sample Table 8-10 Surface Water (Continued) SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote3-Jul-1711-Jul-1718-Jul-1725-Jul-17<6<6<12<5<13<5<11<6<6<6<20<14<3301-Aug-17 8-Aug-1715-Aug-1722-Aug-17<14<11<27<12<29<13<24<10<10<10<9<34929-Aug-175-Sep-1712-Sep-1719-Sep-17 26-Sep-173-Oct-1710-Oct-1717-Oct-1724-Oct-17 31-Oct-177-Nov-1714-Nov-1721-Nov-17 28-Nov-175-Dec-1712-Dec-1719-Dec-1726-Dec-17units are pCi/literODCM required samples denoted by *EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleSEDIMENTATION BASIN #2EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No Sample Table 8-11 Sludge/Sediment SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-111Notes3-Jan-17<68<10610-Jan-17 482163<118<16817-Jan-17 291156<80<11424-Jan-17 192138<40<13531-Jan-17<137<1687-Feb-17 788229<148<15514-Feb-17 695184<107<118 21-Feb-17 200133<127<17828-Feb-17 277163<61<1437-Mar-17<94<14114-Mar-17 469152<109<9321-Mar-17<102<17128-Mar-17 632165<117<1024-Apr-17 33191<51<8111-Apr-17 562186<128<18018-Apr-1725-Apr-17<116<1022-May-17<100<1119-May-17 724169<109<16216-May-17 891195<109<12323-May-17 919186<106<14630-May-17 467151<137<1206-Jun-17 959215<145<14813-Jun-17 654201<140<15920-Jun-17 679176<90<14427-Jun-17 348131<90<158SLUDGE/SEDIMENTWR OUTAGEWR CENTRIFUGE WASTE SLUDGEODCM required samples denoted by *units are pCi/kg, wet Table 8-11 Sludge/Sediment (Continued) SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-111Notes3-Jul-17 351147<146<16211-Jul-17 487151<35<3018-Jul-17 359144<126<14325-Jul-17 35344<23<231-Aug-17 498 191<146<1438-Aug-17 323137<106<16315-Aug-17<108<15522-Aug-17 314128<113<16929-Aug-17 364162<129<3215-Sep-17 415177<143<5112-Sep-17 481162<32<17819-Sep-17 264143<143<17726-Sep-17 427143<109<3053-Oct-17 510164<147<15510-Oct-17 423161<115<4217-Oct-1724-Oct-17 510138<81<8031-Oct-17 481141<65<307-Nov-17 375139<74<16214-Nov-17 646161<94<8221-Nov-17 523161<93<17728-Nov-17 302122<122<1165-Dec-17 363139<146<14512-Dec-17<125<15119-Dec-17 299169<139<11926-Dec-17 215120<146<169WR OUTAGEWR CENTRIFUGE WASTE SLUDGEODCM required samples denoted by *units are pCi/kg, wet Table 8-11 Sludge/Sediment (Continued) Cooling Tower Sludge Unit Cycle Approximate Volume (yd 3) Isotope Activity Range (pCi/g) Sample Type U2R20 302 All principal gamma-emitters <MDA Towers/Canal Sludge U1R20 512 All principal gamma-emitters <MDA Towers/Canal Sludge Table 8-12 Hard -To-Detect Radionuclide Results Hard-To-Detect Radionuclide (pCi/Liter) Sample Location Well number Sample Date C-14 Fe-55 Ni-63 Sr-90 Unit 1 (outside RCA) APP-12 11/9/2017 <66.7 <18.3 <2.39 <1.58 Unit 2 (inside RCA) H0A 11/3/2017 <67.1 <21.5 <2.68 <1.06 Unit 3 (inside RCA) H11 10/24/2017 <67.9 <19.9 <3.19 <1.03
: 9. Thermoluminescent Dosimeter (TLD) Results and Data The environmental TLD used at PVNGS is the Panasonic Model 812 Dosimeter. The Model 812 is a multi-element dosimeter combining two elements of lithium borate and two elements of calcium sulfate under various filters.   
: 9. Thermoluminescent Dosimeter (TLD) Results and Data The environmental TLD used at PVNGS is the Panasonic Model 812 Dosimeter. The Model 812 is a multi-element dosimeter combining two elements of lithium borate and two elements of calcium sulfate under various filters.   


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Historical environmental gamma radiation results for 1985 through 2017 are presented in graphical form on Figure 9-1 (excluding transit control TLD #45). Figure 9-2 depicts the environmental TLD results from 2017 as compared to the pre-operational TLD results (excluding sites #41 and #43, as they were deleted and later assigned to a new location, and #46-50, as they had no pre-op TLD at the location for comparison). The site to site comparisons indicate a direct correlation with respect to pre-operational results. It is indicated that the offsite dose, as measured by TLDs, has not changed since Palo Verde became operational.  
Historical environmental gamma radiation results for 1985 through 2017 are presented in graphical form on Figure 9-1 (excluding transit control TLD #45). Figure 9-2 depicts the environmental TLD results from 2017 as compared to the pre-operational TLD results (excluding sites #41 and #43, as they were deleted and later assigned to a new location, and #46-50, as they had no pre-op TLD at the location for comparison). The site to site comparisons indicate a direct correlation with respect to pre-operational results. It is indicated that the offsite dose, as measured by TLDs, has not changed since Palo Verde became operational.  


Table 9-2 Environmental TLD Results B Q M QQ1M QQ2M QQ3M QQ4L QQ1L QQ2L QQ3L QQ4B A M A L A125.125.925.125.825.5NDNDNDND100.4102.3ND222.523.222.422.421.4NDNDNDND89.989.4ND324.325.124.723.223.3NDNDNDND97.296.3ND424.826.923.625.524.4NDNDNDND99.3100.5ND522.220.419.620.119.6NDNDNDND89.079.8ND627.028.328.027.8-NDNDND-107.884.0ND725.826.526.625.226.8NDNDNDND103.3105.1ND824.124.824.924.624.6NDNDNDND96.598.9ND928.629.227.928.628.9NDNDNDND114.5114.5ND1024.225.224.524.723.6NDNDNDND96.697.9ND1125.325.424.924.826.3NDNDNDND101.3101.4ND 1223.723.224.624.024.1NDNDNDND94.895.9ND1326.026.225.726.025.5NDNDNDND104.1103.5ND1425.325.425.725.725.0NDNDNDND101.3101.8ND1523.924.223.723.324.5NDNDNDND95.695.7ND1622.723.723.423.523.2NDNDNDND91.093.8ND1725.026.125.524.525.0NDNDNDND100.2101.1ND1823.724.423.222.623.4NDNDNDND94.793.6ND1925.826.024.924.925.3NDNDNDND103.4101.1ND 2024.625.525.024.424.8NDNDNDND98.599.6ND2126.126.027.726.025.3NDNDNDND104.3105.0ND2226.526.925.525.926.3NDNDNDND106.1104.7ND2323.623.824.023.022.9NDNDNDND94.393.7ND2423.123.922.422.022.7NDNDNDND92.391.1ND2523.824.423.123.823.5NDNDNDND95.194.8ND2627.928.528.328.828.0NDNDNDND111.6113.6ND2727.328.228.727.426.7NDNDNDND109.0111.0ND 2826.227.826.725.725.2NDNDNDND104.7105.4ND2924.724.824.125.125.2NDNDNDND98.699.2ND3026.126.726.926.026.3NDNDNDND104.5106.0ND 3123.724.323.823.123.5NDNDNDND94.694.6ND3225.925.426.025.925.4NDNDNDND103.5102.8ND3326.326.226.326.325.7NDNDNDND105.3104.4ND3428.129.028.527.528.3NDNDNDND112.5113.4ND3531.432.533.930.930.8NDNDNDND125.6128.2ND3626.626.627.625.625.4NDNDNDND106.3105.1ND3724.325.324.423.623.7NDNDNDND97.296.9ND3827.828.927.028.028.4NDNDNDND111.1112.2ND3924.725.824.824.023.7NDNDNDND98.698.2ND4025.426.125.025.624.6NDNDNDND101.5101.4ND 4126.927.426.727.826.0NDNDNDND107.7107.9ND4227.829.027.627.426.5NDNDNDND111.2110.5ND4327.929.028.628.827.0NDNDNDND111.5113.4ND4423.824.425.223.723.6NDNDNDND95.396.9ND455.96.25.95.95.3NDNDNDND23.523.3ND 4624.424.524.424.524.3NDNDNDND97.597.8ND4724.224.124.724.023.3NDNDNDND96.796.1ND4824.725.424.124.523.6NDNDNDND98.797.6ND4923.123.223.223.322.0NDNDNDND92.491.8ND5019.920.419.219.619.6NDNDNDND79.778.9NDQuarterly (mrem)SiteAnnual (mrem)Palo Verde 2017 MDD Q:  5 mrem                        Palo Verde 2017 MDDA:  10 mrem  
Table 9-2 Environmental TLD Results B Q M QQ1M QQ2M QQ3M QQ4L QQ1L QQ2L QQ3L QQ4B A M A L A125.125.925.125.825.5NDNDNDND100.4102.3ND222.523.222.422.421.4NDNDNDND89.989.4ND324.325.124.723.223.3NDNDNDND97.296.3ND424.826.923.625.524.4NDNDNDND99.3100.5ND522.220.419.620.119.6NDNDNDND89.079.8ND627.028.328.027.8-NDNDND-107.884.0ND725.826.526.625.226.8NDNDNDND103.3105.1ND824.124.824.924.624.6NDNDNDND96.598.9ND928.629.227.928.628.9NDNDNDND114.5114.5ND1024.225.224.524.723.6NDNDNDND96.697.9ND1125.325.424.924.826.3NDNDNDND101.3101.4ND 1223.723.224.624.024.1NDNDNDND94.895.9ND1326.026.225.726.025.5NDNDNDND104.1103.5ND1425.325.425.725.725.0NDNDNDND101.3101.8ND1523.924.223.723.324.5NDNDNDND95.695.7ND1622.723.723.423.523.2NDNDNDND91.093.8ND1725.026.125.524.525.0NDNDNDND100.2101.1ND1823.724.423.222.623.4NDNDNDND94.793.6ND1925.826.024.924.925.3NDNDNDND103.4101.1ND 2024.625.525.024.424.8NDNDNDND98.599.6ND2126.126.027.726.025.3NDNDNDND104.3105.0ND2226.526.925.525.926.3NDNDNDND106.1104.7ND2323.623.824.023.022.9NDNDNDND94.393.7ND2423.123.922.422.022.7NDNDNDND92.391.1ND2523.824.423.123.823.5NDNDNDND95.194.8ND2627.928.528.328.828.0NDNDNDND111.6113.6ND2727.328.228.727.426.7NDNDNDND109.0111.0ND 2826.227.826.725.725.2NDNDNDND104.7105.4ND2924.724.824.125.125.2NDNDNDND98.699.2ND3026.126.726.926.026.3NDNDNDND104.5106.0ND 3123.724.323.823.123.5NDNDNDND94.694.6ND3225.925.426.025.925.4NDNDNDND103.5102.8ND3326.326.226.326.325.7NDNDNDND105.3104.4ND3428.129.028.527.528.3NDNDNDND112.5113.4ND3531.432.533.930.930.8NDNDNDND125.6128.2ND3626.626.627.625.625.4NDNDNDND106.3105.1ND3724.325.324.423.623.7NDNDNDND97.296.9ND3827.828.927.028.028.4NDNDNDND111.1112.2ND3924.725.824.824.023.7NDNDNDND98.698.2ND4025.426.125.025.624.6NDNDNDND101.5101.4ND 4126.927.426.727.826.0NDNDNDND107.7107.9ND4227.829.027.627.426.5NDNDNDND111.2110.5ND4327.929.028.628.827.0NDNDNDND111.5113.4ND4423.824.425.223.723.6NDNDNDND95.396.9ND455.96.25.95.95.3NDNDNDND23.523.3ND 4624.424.524.424.524.3NDNDNDND97.597.8ND4724.224.124.724.023.3NDNDNDND96.796.1ND4824.725.424.124.523.6NDNDNDND98.797.6ND4923.123.223.223.322.0NDNDNDND92.491.8ND5019.920.419.219.619.6NDNDNDND79.778.9NDQuarterly (mrem)SiteAnnual (mrem)Palo Verde 2017 MDD Q:  5 mrem                        Palo Verde 2017 MDDA:  10 mrem
: 10. Land Use Census 10.1 Introduction In accordance with the PVNGS ODCM, Section 6.2, the field portion of the annual Land Use Census was performed by June 2017. Observations were made in each of the 16 meteorological sectors to determine the nearest milking animals, residences, and gardens of greater than 500 square feet. This census was completed by driving the roads and speaking with residents. The results of the Land Use Census are presented in Table 10-1 and discussed below. The directions and distances listed are in sectors and miles from the Unit 2 containment.
: 10. Land Use Census 10.1 Introduction In accordance with the PVNGS ODCM, Section 6.2, the field portion of the annual Land Use Census was performed by June 2017. Observations were made in each of the 16 meteorological sectors to determine the nearest milking animals, residences, and gardens of greater than 500 square feet. This census was completed by driving the roads and speaking with residents. The results of the Land Use Census are presented in Table 10-1 and discussed below. The directions and distances listed are in sectors and miles from the Unit 2 containment.
10.2 Census Results The 2017 Land Use Census results have identified a new potential Radiological Effluent Release Report dose receptor location. Condition Report 18-04530 was generated to document the changes identified since the 2016 Land Use Census. Each location was evaluated. Below describes the changes identified and the evaluation results. Nearest Resident There was one (1) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.590 mrem. Milk Animal There were three (3) changes in milk animal status from the previous year. The locations were visited by the REMP manager to evaluate program particip ation potential. As of December 2017, none of the locations had goats. Dose calculations indicated the highest dose to be 0.660 mrem. Vegetable Gardens There were three (3) changes in nearest garden status from the previous year. One garden had a calculated dose lower than gardens currently in REMP. One garden location was removed due to absence of garden. One garden was evaluated and found to not currently meet the ODCM required size of 500 square feet, nor growing broadleaf vegetation; however, this location is being monitored for possible future inclusion in REMP. Dose calculations indicated the highest dose to be 0.590 mrem. See Table 10-1 for a summary of the specific results and Table 2-1 for current sample locations. Figure 10-1through Figure 10-3 provide graphs depicting historical calculated doses for nearest residents, nearest milk receptor, and nearest garden receptor locations in each sector. Differences in calculated doses are the result of many variables, including;  Changes in receptor locations from year to year (proximity to the power plant)
10.2 Census Results The 2017 Land Use Census results have identified a new potential Radiological Effluent Release Report dose receptor location. Condition Report 18-04530 was generated to document the changes identified since the 2016 Land Use Census. Each location was evaluated. Below describes the changes identified and the evaluation results. Nearest Resident There was one (1) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.590 mrem. Milk Animal There were three (3) changes in milk animal status from the previous year. The locations were visited by the REMP manager to evaluate program particip ation potential. As of December 2017, none of the locations had goats. Dose calculations indicated the highest dose to be 0.660 mrem. Vegetable Gardens There were three (3) changes in nearest garden status from the previous year. One garden had a calculated dose lower than gardens currently in REMP. One garden location was removed due to absence of garden. One garden was evaluated and found to not currently meet the ODCM required size of 500 square feet, nor growing broadleaf vegetation; however, this location is being monitored for possible future inclusion in REMP. Dose calculations indicated the highest dose to be 0.590 mrem. See Table 10-1 for a summary of the specific results and Table 2-1 for current sample locations. Figure 10-1through Figure 10-3 provide graphs depicting historical calculated doses for nearest residents, nearest milk receptor, and nearest garden receptor locations in each sector. Differences in calculated doses are the result of many variables, including;  Changes in receptor locations from year to year (proximity to the power plant)
Changes in local meteorology (wind direction, wind speed, precipitation, and temperature)  Concurrent meteorology at the time of effluent releases  Exposure pathways Table 10-1 Land Use Census (Distance and direction are relative to Unit 2 in miles) Sector Nearest Resident Nearest Garden Nearest Milk Animal (Cow/Goat) Calculated Dose (mrem) Change from 2016 N 1.55 1.71 1.94 Resident Garden Milk 5.50E-2 2.77E-1 2.49E-1 Garden Milk NNE 1.52 NONE 3.05 Resident Milk 7.87E-2 2.86E-1 Garden NE 2.16 2.16 4.40 Resident Garden Milk 5.90E-1 5.90E-1 2.53E-1 Garden Milk ENE 2.05 4.84 4.84 Resident Garden Milk 1.03E-1 1.85E-1 1.85E-1  E 2.81 NONE NONE Resident 7.68E-2  ESE 1.95 NONE NONE Resident 1.85E-1  SE 3.40 NONE 3.99 Resident Milk 1.22E-1 6.60E-1 Resident Milk SSE NONE NONE NONE NA  S NONE NONE NONE NA  SSW NONE NONE NONE NA  SW 1.39 NONE NONE Resident 1.37E-1  WSW 0.75 NONE NONE Resident 1.43E-1  W 0.70 NONE NONE Resident 8.48E-2  WNW NONE NONE NONE NA  NW 0.93 NONE NONE Resident 7.02E-2  NNW 1.30 4.34 NONE Resident Garden 6.93E-2 8.03E-2  Comments: Dose calculations were performed using GASPAR code and 2016 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual critical organ dose identified.  
Changes in local meteorology (wind direction, wind speed, precipitation, and temperature)  Concurrent meteorology at the time of effluent releases  Exposure pathways Table 10-1 Land Use Census (Distance and direction are relative to Unit 2 in miles) Sector Nearest Resident Nearest Garden Nearest Milk Animal (Cow/Goat) Calculated Dose (mrem) Change from 2016 N 1.55 1.71 1.94 Resident Garden Milk 5.50E-2 2.77E-1 2.49E-1 Garden Milk NNE 1.52 NONE 3.05 Resident Milk 7.87E-2 2.86E-1 Garden NE 2.16 2.16 4.40 Resident Garden Milk 5.90E-1 5.90E-1 2.53E-1 Garden Milk ENE 2.05 4.84 4.84 Resident Garden Milk 1.03E-1 1.85E-1 1.85E-1  E 2.81 NONE NONE Resident 7.68E-2  ESE 1.95 NONE NONE Resident 1.85E-1  SE 3.40 NONE 3.99 Resident Milk 1.22E-1 6.60E-1 Resident Milk SSE NONE NONE NONE NA  S NONE NONE NONE NA  SSW NONE NONE NONE NA  SW 1.39 NONE NONE Resident 1.37E-1  WSW 0.75 NONE NONE Resident 1.43E-1  W 0.70 NONE NONE Resident 8.48E-2  WNW NONE NONE NONE NA  NW 0.93 NONE NONE Resident 7.02E-2  NNW 1.30 4.34 NONE Resident Garden 6.93E-2 8.03E-2  Comments: Dose calculations were performed using GASPAR code and 2016 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual critical organ dose identified.
: 11. Summary and Conclusions Summary The conclusions are based on a review of the radioassay results and environmental gamma radiation measurements for the 2017 calendar year. Where possible, the data were compared to pre-operational sample data. All sample results for 2017 are presented in Table 8-1 through Table 8-12 and do not include observations of naturally occurring radionuclides, with the exception of gross beta in air and gross beta in drinking water. Table 11-1  summarizes the ODCM required samples and is in the format required by the NRC BTP on Environmental Monitoring.
: 11. Summary and Conclusions Summary The conclusions are based on a review of the radioassay results and environmental gamma radiation measurements for the 2017 calendar year. Where possible, the data were compared to pre-operational sample data. All sample results for 2017 are presented in Table 8-1 through Table 8-12 and do not include observations of naturally occurring radionuclides, with the exception of gross beta in air and gross beta in drinking water. Table 11-1  summarizes the ODCM required samples and is in the format required by the NRC BTP on Environmental Monitoring.
I-131 identified in the evaporation ponds, Water Resources influent, Water Resources centrifuge sludge, and reservoirs is the result of offsite sources and appears in the effluent sewage from Phoenix. The levels of I-131 detected in these locations are consistent with levels identified in previous years. Tritium concentrations identified in surface water onsite have been attributed to PVNGS permitted gaseous effluent releases and secondary plant releases. These concentrations are consistent with historical values.
I-131 identified in the evaporation ponds, Water Resources influent, Water Resources centrifuge sludge, and reservoirs is the result of offsite sources and appears in the effluent sewage from Phoenix. The levels of I-131 detected in these locations are consistent with levels identified in previous years. Tritium concentrations identified in surface water onsite have been attributed to PVNGS permitted gaseous effluent releases and secondary plant releases. These concentrations are consistent with historical values.
Line 395: Line 395:
&deg; 3.87 -6.26          H 16 2000 <LLD NA <LLD NA 0  Gamma Spec. - 48      Drinking Water (pCi/liter) Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 I-131 15 <LLD NA <LLD NA 3 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 5  
&deg; 3.87 -6.26          H 16 2000 <LLD NA <LLD NA 0  Gamma Spec. - 48      Drinking Water (pCi/liter) Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 I-131 15 <LLD NA <LLD NA 3 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 5  


Gamma Spec. - 27 Milk I-131 1 <LLD NA <LLD <LLD 1 (pCi/liter)  <LLD NA <LLD <LLD        Cs-134 15 <LLD NA <LLD <LLD 0  <LLD NA <LLD <LLD        Cs-137 18 <LLD NA <LLD <LLD 0  <LLD NA <LLD <LLD        Ba-140 60 <LLD NA <LLD <LLD 0 La-140 15 <LLD NA <LLD <LLD 0                          Gamma Spec. - 24        Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0  Co-58 15 <LLD NA <LLD NA 0  Co-60 15 <LLD NA <LLD NA 0  Zn-65 30 <LLD NA <LLD NA 0  Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0        Surface Water (pCi/liter) I-131 15 10 (3/36) Site #61 13 (1/4) NA 0  8-13 Onsite 67&deg; 13-13          Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 H 25 3000 913  (13/36) Site #59 1374 (4/4) NA 1 402 - 1680 Onsite 180&deg; 1212-1680 (a) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses.  (f) NOTE:  Miscellaneous samples that are not listed on Tables 2.1 and 9.1 (not ODCM required) are not included on this table.
Gamma Spec. - 27 Milk I-131 1 <LLD NA <LLD <LLD 1 (pCi/liter)  <LLD NA <LLD <LLD        Cs-134 15 <LLD NA <LLD <LLD 0  <LLD NA <LLD <LLD        Cs-137 18 <LLD NA <LLD <LLD 0  <LLD NA <LLD <LLD        Ba-140 60 <LLD NA <LLD <LLD 0 La-140 15 <LLD NA <LLD <LLD 0                          Gamma Spec. - 24        Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0  Co-58 15 <LLD NA <LLD NA 0  Co-60 15 <LLD NA <LLD NA 0  Zn-65 30 <LLD NA <LLD NA 0  Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0        Surface Water (pCi/liter) I-131 15 10 (3/36) Site #61 13 (1/4) NA 0  8-13 Onsite 67&deg; 13-13          Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 H 25 3000 913  (13/36) Site #59 1374 (4/4) NA 1 402 - 1680 Onsite 180&deg; 1212-1680 (a) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses.  (f) NOTE:  Miscellaneous samples that are not listed on Tables 2.1 and 9.1 (not ODCM required) are not included on this table.
: 12. References  
: 12. References
: 1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985  
: 1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985
: 2. 1985-2016  Annual Radiological Environmental Operating Reports, Palo Verde Nuclear Generating Station  
: 2. 1985-2016  Annual Radiological Environmental Operating Reports, Palo Verde Nuclear Generating Station
: 3. Palo Verde Nuclear Generating Station Technical Specifications and Technical Reference Manual 4. Offsite Dose Calculation Manual, Revision 27, PVNGS Units 1, 2, and 3  
: 3. Palo Verde Nuclear Generating Station Technical Specifications and Technical Reference Manual 4. Offsite Dose Calculation Manual, Revision 27, PVNGS Units 1, 2, and 3
: 5. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants  
: 5. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants
: 6. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants  
: 6. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants
: 7. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG-1301)  
: 7. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG-1301)
: 8. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007  
: 8. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007
: 9. "Sources of Radiation." NRC: Sources of Radiation. Nuclear Regulatory Commission, 2 Oct. 2017. Web. 21 Feb. 2018.  
: 9. "Sources of Radiation." NRC: Sources of Radiation. Nuclear Regulatory Commission, 2 Oct. 2017. Web. 21 Feb. 2018.
: 10. "NCRP Report No. 160: Ionizing Radiation Exposure of the Population of the United States." Journal of Radiological Pr otection J. Radiol. Prot. 29.3 (2009): 465. Web.}}
: 10. "NCRP Report No. 160: Ionizing Radiation Exposure of the Population of the United States." Journal of Radiological Pr otection J. Radiol. Prot. 29.3 (2009): 465. Web.}}

Revision as of 11:42, 25 April 2019

(Pvngs), Units 1, 2, and 3 -Annual Radiological Environmental Operating Report
ML18131A353
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 05/10/2018
From: DiLorenzo M D
Arizona Public Service Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
102-07693-MDD/MSC
Download: ML18131A353 (80)
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Technical Specification 5.6.2 5.6.2A member of the STARS Alliance LLC Callaway Diablo Canyon Palo Verde Wolf Creek Palo Verde Nuclear Generating Station PO Box 52034 Phoenix, Arizona 85072-2034 Mail Station 7636 102-07693-MDD/MSC May 10, 2018

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, and 3 Docket Nos. STN 50-528/529/530 Annual Radiological Environmental Operating Report 2017 In accordance with PVNGS Technical Specification 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2017.

No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Matthew S. Cox, Licensing Section Leader, at (623) 393-5753.

Sincerely, Michael D. DiLorenzo Department Leader, Regulatory Affairs

MDD/MSC/sma

Enclosure:

Palo Verde Nuclear Generating Station Annual Radiological Environmental Operating Report 2017

cc: K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. D. Orneak NRC NRR Project Manager for PVNGS M. M. O'Banion NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS T. Morales Arizona Department of Health Se rvices - Bureau of Radiation Controls (ADHS)

Dilorenzo, Michael D(Z99838)Digitally signed by Dilorenzo, Michael

D(Z99838)

DN: cn=Dilorenzo, Michael D(Z99838)

Date: 2018.05.10 16:56:34 -07'00' Enclosure Palo Verde Nuclear Generating Station Annual Radiological Environmental Operating Report 2017

Prepared by:

Reviewed by: Approved by:

Director, Radiation Protection

(

Reference:

RCTSAI 1643, Legacy Item No. 036843.01)

Comolli, Michelle (Z09567)Digitally signed by Comolli, Michelle (Z09567)

DN: cn=Comolli, Michelle (Z09567)

Reason: I am the author of this document Date: 2018.04.09 08:48:34 -07'00' Hogue, Nathan (Z14113)Digitally signed by Hogue, Nathan (Z14113)DN: cn=Hogue, Nathan (Z14113)

Date: 2018.04.09 13:29:33 -07'00' Moeller, Carl (Z09119)Digitally signed by Moeller, Carl (Z09119)

DN: cn=Moeller, Carl (Z09119)

Date: 2018.04.10 06:45:05 -07'00'

1. Introduction ..................................................................................................................

........... 2 Overview ......................................................................................................................

............... 2 Radiation and Radioactivity ...................................................................................................

..... 3 2. Description of the Monitoring Program .................................................................................. 4

2.1 Radiological

Environmental Monitoring Program ............................................................... 4

2.2 Radiological

Environmental Monitoring Program Changes for 2017 .................................. 4 2.3 REMP Deviations/Abnormal Events Summary.................................................................... 4

2.4 Groundwater

Protection ....................................................................................................

.... 6 3. Sample Collection Program .................................................................................................. 14

3.1 Water

.....................................................................................................................

.............. 14

3.2 Vegetation

................................................................................................................

........... 14 3.3 Milk ......................................................................................................................

............... 14 3.4 Air .......................................................................................................................

................ 14 3.5 Soil, Sludge, and Sediment ................................................................................................. 14 4. Analytical Procedures .........................................................................................................

.. 15 4.1 Air Particulate ...........................................................................................................

.......... 15

4.1.1 Gross

Beta ..............................................................................................................

...... 15 4.1.2 Gamma Spectroscopy .................................................................................................. 15

4.2 Airborne

Radioiodine ......................................................................................................

.... 15 4.2.1 Gamma Spectroscopy .................................................................................................. 15 4.3 Milk ......................................................................................................................

............... 15

4.3.1 Gamma

Spectroscopy .................................................................................................. 15

4.3.2 Radiochemical

I-131 Separation .................................................................................. 15

4.4 Vegetation

................................................................................................................

........... 15

4.4.1 Gamma

Spectroscopy .................................................................................................. 15 4.5 Sludge/Sediment ...........................................................................................................

...... 16 4.5.1 Gamma Spectroscopy .................................................................................................. 16

4.6 Water

.....................................................................................................................

.............. 16

4.6.1 Gamma

Spectroscopy .................................................................................................. 16

4.6.2 Tritium

.................................................................................................................

........ 16

4.6.3 Gross

Beta ..............................................................................................................

...... 16 4.7 Soil ......................................................................................................................

................ 16

4.7.1 Gamma

Spectroscopy .................................................................................................. 16

5. Nuclear Instrumentation........................................................................................................

17 5.1 Gamma Spectrometer ........................................................................................................

.. 17 5.2 Liquid Scintillation Spectrometer ....................................................................................... 1 7 5.3 Gas Flow Proportional Counter .......................................................................................... 17

6. Isotopic Detection Limits and Reporting Criteria ................................................................. 18

6.1 Lower

Limits of Detection .................................................................................................. 18 6.2 Data Reporting Criteria ...................................................................................................

.... 18 6.3 LLD and Reporting Criteria Overview ............................................................................... 18

7. Interlaboratory Comparison Program ................................................................................... 24

7.1 Quality

Control Program..................................................................................................... 24 7.2 Intercomparison Results ...................................................................................................

... 24 8. Data Interpretation and Conclusions ..................................................................................... 28 8.1 Air Particulates ............................................................................................................... 28 8.2 Airborne Radioiodine ......................................................................................................

.... 28 8.3 Vegetation ................................................................................................................

........... 29 8.4 Milk ......................................................................................................................

............... 29

8.5 Drinking

Water ............................................................................................................

....... 29

8.6 Groundwater

...............................................................................................................

........ 29

8.7 Surface

Water..............................................................................................................

........ 29

8.8 Sludge

and Sediment........................................................................................................

... 30 8.8.1 WR Centrifuge Waste Sludge ...................................................................................... 30

8.8.2 Cooling

Tower Sludge ................................................................................................. 30 8.9 Data Trends ...............................................................................................................

.......... 30 8.10 Hard-To-Detect Radionuclide Results .............................................................................. 30

9. Thermoluminescent Dosimeter (TLD) Results and Data ..................................................... 57
10. Land Use Census................................................................................................................

62 10.1 Introduction .............................................................................................................

.......... 62 10.2 Census Results ...........................................................................................................

....... 62

11. Summary and Conclusions ................................................................................................ 67
12. References ....................................................................................................................

...... 71 Table 2-1 Sample Collection Locations .......................................................................................... 7 Table 2-2 Sample Collection Schedule ........................................................................................... 8 Table 2-3 Summaries of the REMP Deviations/Abnormal Events ................................................ 9 Table 6-1 ODCM Required Lower Limits of Detection (a priori) ............................................... 21 Table 6-2 ODCM Required Reporting Levels .............................................................................. 22 Table 6-3 Typical MDA Values ................................................................................................... 23 Table 7-1 Interlaboratory Comparison Results ............................................................................. 25 Table 8-1 Particulate Gross Beta in Air 1st-2nd Quarter .............................................................. 31 Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter .............................................................. 32 Table 8-3 Gamma in Air Filter Composites ................................................................................. 33 Table 8-4 Radioiodine in Air 1st-2nd Quarter .............................................................................. 34 Table 8-5 Radioiodine in Air 3rd-4th Quarter .............................................................................. 35 Table 8-6 Vegetation...........................................................................................................

.......... 36 Table 8-7 Milk ................................................................................................................

.............. 37 Table 8-8 Drinking Water ......................................................................................................

....... 38 Table 8-9 Groundwater .........................................................................................................

........ 40 Table 8-10 Surface Water ......................................................................................................

....... 41 Table 8-11 Sludge/Sediment ....................................................................................................

..... 46 Table 8-12 Hard -To-Detect Radionuclide Results ...................................................................... 48 Table 9-1 TLD Site Locations ..................................................................................................

.... 58 Table 9-2 Environmental TLD Results ......................................................................................... 5 9 Table 10-1 Land Use Census ....................................................................................................

.... 63 Table 11-1 Environmental Radiological Monitoring Program Annual Summary ........................ 68

Figure 1-1 Sources of Radiation Exposure in the United States ..................................................... 3 Figure 2-1 REMP Sample Sites- Map (0-10 miles) ...................................................................... 12 Figure 2-2 REMP Sample Sites- Map (10-35 Miles) ................................................................... 13 Figure 8-1 Gross Beta in Air, 1st-2nd Quarter ............................................................................. 49 Figure 8-2 Gross Beta in Air, 3rd-4th Quarter .............................................................................. 50 Figure 8-3 Historical Gross Beta in Air (Weekly System Average) ............................................ 51 Figure 8-4 Historical Gross Beta in Air (Annual Site to Site Comparisons) Compared to Pre-Op

...............................................................................................................................

........................ 52 Figure 8-5 Gross Beta in Drinking Water ..................................................................................... 5 3 Figure 8-6 Evaporation Pond Tritium Activity (Pre-Op- 2008) ................................................... 54 Figure 8-7 Evaporation Pond Tritium Activity (2009-2017) ........................................................ 55 Figure 8-8 Sedimentation Basin 2 Cs-137 .................................................................................... 56 Figure 9-1 Network Environmental TLD Exposure Rates ........................................................... 60 Figure 9-2 Environmental TLD Comparison: Pre-Operational versus 2017 ................................ 61 Figure 10-1 Historical Comparison of Nearest Resident Dose ..................................................... 64 Figure 10-2 Historical Comparison of Nearest Milk Animal Dose .............................................. 65 Figure 10-3 Historical Comparison of Nearest Garden Dose ....................................................... 66

Appendix A ....................................................................................................................

............... 72

The Radiological Environmental Monitoring Program (REMP) is an ongoing program conducted by Arizona Public Service Company (APS) for the Palo Verde Nuclear Generating Station (PVNGS). Various types of environmental samples are collected near PVNGS and analyzed for plant-related radionuclide concentrations.

During 2017, the following categories of samples were collected by APS:

Broadleaf vegetation Groundwater Drinking water Surface water Airborne particulate and radioiodine Goat milk Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmen tal gamma radiation. The Environmental TLD program is also conducted by APS. The Arizona Department of Health Services, Bureau of Radiation Control (BRC) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by BRC include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) Deep Wells. Offsite samples analyzed by BRC include two (2) local resident wells. BRC also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring locations, eighteen (18) of which are duplicates of APS locations. A comparison of pre-operational and operational data indicates no changes to environmental radiation levels.

(NOTE: Reference to APS throughout this report refers to PVNGS personnel)

1. Introduction This report presents the results of the operational Radiological Environmental Monitoring Program conducted by Arizona Public Service Company (APS). The Radiological Environmental Monitoring Program (REMP) was established for the Palo Verde Nuclear Generating Station (PVNGS) by APS in 1979. This report contains the measurements and findings for 2017. All references are specifically identified in Section 12.

Overview The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in exposure pathways. REMP measures radionuclides that lead to the highest potential radiation exposures to members of the public resulting from station operation. This monitoring program implements Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix I,Section IV.B.2., 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 US Nuclear Regulatory Commission (USNRC) in their Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (incorporated into NUREG 1301). Results from the REMP help to evaluate sources of elevated levels of radioactivity in the environment (i.e. atmospheric nuclear detonations or abnormal plant releases). The Land Use Census ensures that changes in the use of areas at, and beyond the site boundary, are identified and that modifications to the REMP are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part

50. The 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 10 CFR 50, Appendix I, Section IV.B.2. Results of the PVNGS pre-operational environmental monitoring program are presented in Reference 1. The initial criticality of Unit 1 occurred May 25, 1985. Initial criticality for Units 2 and 3 were April 18, 1986, and October 25, 1987, respectively. PVNGS operational findings (historical) are presented in Reference 2.

Radiation and Radioactivity Atoms are the basic building blocks of matter. Unstable atoms emit radiation and material that spontaneously emits radiation is referred to as radioactive. Radioactive material is frequently categorized as either "Natural" or "Man-made" Natural sources of radiation exist naturally in the environment and include: radon, thoron, cosmic, terrestrial, and internal. The sun and stars are a source of cosmic radiation.

Atmospheric conditions, the Earth's magnetic field, and differences in elevation can affect the amount, or dose, of cosmic radiation an individual receives. The Earth is a source of terrestrial radiation. Uranium, thorium, and radium exist naturally in rock and soil. All organic matter contains carbon and potassium, and water contains small amounts of dissolved uranium and thorium. The largest contributor of dose to Americans from natural sources is attributed to radon which is found in air. All people are a source of internal radiation. Potassium-40 and carbon-14 are radioactive nuclides and inside all people from birth, making people a source of exposure. Man-made sources of radiation include: consumer products, nuclear medicine, and medical procedures. There are a number of occupational areas which result in exposure to individuals of varying amounts of radiation such as: radiography, radiology, radiation oncology, power generation, and research laboratories. The Nuclear Regulatory Commission (NRC) requires licensees to monitor exposure to workers and limit occupational exposure to 5,000 millirem. Several consumer products contain radioactive material such as: some ceramics, thorium lantern mantles, luminous watches containing tritium, smoke detectors, and tobacco. Other consumer product sources of radiation can come from building and road construction materials, combustible fuels (i.e. gas, coal), and x-ray security systems. Th e most significant contributor to radiation exposure from man-made sources is medical procedures. Diagnostic x-rays and nuclear medicine procedures, such as those that use iodine-131 or cesium-137, are examples of man-made medical sources. The average member of the public receives a total annual dose of approximately 620 millirem from ionizing radiation. Figure 1-1 illustrates the contribution of various sources of radiation to radiation exposure in the United States (NCRP Report No.160 (2009)).

Figure 1-1 Sources of Radiation Exposure in the United States Sources of Radiation Exposure in the United States

2. Description of the Monitoring Program APS and vendor organizations performed the pre-operational Radiological Environmental Monitoring Program between 1979 and 1985. APS and vendors continued the program into the operational phase. 2.1 Radiological Environmental Monitoring Program The assessment program consists of routine measurements of environmental gamma radiation and of radionuclide concentrations in media such as air, groundwater, drinking water, surface water, vegetation, milk, sludge, and sediment.

Samples were collected by APS at the monitoring sites shown in Figures 2-1 and 2-2. The specific sample types, sampling locations, and sampling frequencies, as set forth in the PVNGS Offsite Dose Calculation Manual (ODCM), Reference 4, are presented in Tables 2-l, 2-2 and 9-1. Additional onsite sampling (outside the scope of the ODCM) is performed to supplement the REMP. All results are included in this report. Routine sample analyses were performed at the onsite Central Chemistry Laboratory and Operating Unit laboratories. Analyses for hard-to-detect radionuclides were performed by GEL Laboratories LLC.

Environmental gamma radiation measurements were performed by APS using TLDs at fifty (50) locations near PVNGS. The PVNGS Dosimetry Department is accredited by the National Voluntary Laboratory Accreditation Program (NVLAP) to process personnel ionizing radiation dosimeters.

In addition to monitoring environmental media, a Land Use Census is performed annually to identify the nearest milk animals, residents, and gardens. This information is used to evaluate the potential dose to members of the public for those exposure pathways that are indicated. 2.2 Radiological Environmental Monitoring Program Changes for 2017 There were no changes to the Radiological Environmental Monitoring Program that impacted the Offsite Dose Calculation Manual (ODCM) Revision 27. 2.3 REMP Deviations/Abnormal Events Summary During calendar year 2017, there were fifteen (15) deviations/abnormal events with regards to the monitoring program. Refer to Table 2-3 for more detail and corrective actions taken. There were four (4) events involving Air sample stations. Palo Verde Nuclear Generating Station has ten (10) Air sample sites: one (1) control, four (4) ODCM required, and five (5) supplemental sites. Supplemental sampling locations were available and produced valid data for any sampling period involving invalid samples from control or required sample locations. Three (3) events were due to reduced sample volume, two (2) of which were confirmed to be the result of power interruption to the sample station. The reduced sample volume was significant enough over the course of four (4) sample periods that the samples in question were determined to be

invalid. One (1) event was attributed to a small hole in the particulate filter. The filter was found to still have normal loading and deposition; therefore this sample is considered to be valid. Seven (7) events were due to an inability to meet a LLD. One (1) of the seven (7) events involved the control Milk sample location, Site 53, which did not meet the LLD for I-131 (1 pCi/L); the achieved MDA was 1.05 pCi/L. This ev ent was attributed to a software malfunction. There was no detectable activity in this sample and the LLD that was achieved was below the action level. Two (2) of the seven (7) events were due to samples not meeting the LLD for La-140 (15 pCi/L). The event for Site 48 was attributed to input error of the sample date. The event for Site 49 was attributed to excessive time between sample acquisition and sample analysis.

The Drinking Water samples from Site 48 and Site 49 had no detectable activity, and the MDA achieved was below the action level. One (1) event of the seven (7) involves 3 samples not achieving the LLD for I-131 and La-140. Sites 46, 49, and 55 did not meet the LLD for I-131and La-140 (15 pCi/L) . There was no detectable activity in these samples and the MDAs achieved were below the action levels. Three (3) events of the seven (7) involved missing several LLDs for two (2) Water Reclamation Facility Influent samples and one (1)

Sedimentation Basin sample. Two (2) of these events were attributed to incorrect volume input into the analysis software and one (1) was attributed to excessive time between sample acquisition and analysis. The two (2) Influent Water Reclamation Facility Surface Water samples achieved an MDA below the action level, with the exception of I-131, and had no detectable plant-related radioactivity. PVNGS receives waste water from the City of Phoenix and is known to contain the radiopharmaceutical I-131. The influent contains no plant related influent; influent samples are obtained for tr ending purposes. The Sedimentation Basin had no detectable activity and all MDAs were below action levels. One (1) event was an abnormally low tritium level for Evaporation Pond 1C. The analysis reported <320 pCi/L. This value was investigated, revealing a reporting error. Due to the inability to reanalyze, this sample was determined to be invalid. Correction to the reporting file was made. The following sample results were within historically normal values. Two (2) events involved deviation from procedural guidance. One (1) of the two (2) events was a failure to collect the sample within the procedurally directed sampling frequency for Milk sample site 54. The sample was taken 40 days following the previous sample collection. The procedure directs that samples be collected within a 125% surveillance period; samples should be collected no more than 37 days apart. The sample was collected within the current applicable month and analysis confirmed that there was no plant related impact via the milk ingestion pathway. One (1) event of the two (2) was a failure to collect the procedurally required mass for the October vegetation samples collected at the control location, Site 62. The procedural requirement is to collect a minimum of 0.6 kg of each vegetation sample. Three vegetation types were collected of 0.519 kg, 0.413 kg, and 0.372 kg. There was no impact to the requirements of the ODCM as these are control samples with no resident samples available, as well as supplemental air samples collected weekly as a contingency. Additionally, the mass of the vegetation collected was adequate to obtain valid analysis results, which have been included in Table 8-6. The last event involved environmental dosimeter Site 6. Upon 4th Quarter change-out, it was discovered that the environmental dosimetry and stanchion were missing at Site 6. Site 6 stanchion and dosimetry were replaced for the 1 st Quarter 2018 sampling period.

2.4 Groundwater

Protection PVNGS has implemented a groundwater protection initiative developed by the Nuclear Energy Institute (NEI). The implementation of this initiative, NEI 07-07 (Industry Ground Water Protection Initiative - Final Guidance Document, August 2007), provides added assurance that groundwater will not be adversely affected by PVNGS operations. Several monitoring wells have been installed to monitor the subsurface water and shallow aquifer at Units 1, 2, and 3. These wells are sampled monthly and quarterly for chemical and radiological parameters. The State of Arizona Aquifer Protection Permit (Area-Wide) No. P-100388 (APP) provides agreed upon monitoring parameters and reporting thresholds. Sample results for the shallow aquifer wells are reported in the PVNGS Annual Radioactive Effluent Release Report (ARERR). The State of Arizona APP provides specific regulatory criteria for groundwater protection. Three subsurface samples were obtained, one each from Units 2 and 3 tritium monitoring wells, and one from the shallow aquifer outside of the Unit 1 Radiologically Controlled Area (RCA). These samples were analyzed for hard-to-detect radionuclides (e.g. C-14, Fe-55, Ni-63, Sr-90) as verification that there are no underground leaks from plant systems that may affect groundwater. All results were <MDA. Refer to Table 8-12 for sample results.

Table 2-1 Sample Collection Locations SAMPLE SITE # SAMPLE TYPE LOCATION (a) LOCATION DESCRIPTION 4 Air E16 APS Office 6A* Air SSE13 Old US 80 7A Air ESE3 Arlin gton School 14A Air NNE2 371st Ave. and Buckeye-Salome Rd.

15 Air NE2 NE Site Boundary 17A Air E3 351st Ave. 21 Air S3 S Site Boundary 29 Air W1 W Site Boundary 35 Air NNW8 Tonopah 40 Air N2 Transmission Rd 46 Drinking Water NNW8 Local resident 47 Vegetation N3 Local resident 48 Drinking Water SW1 Local resident 49 Drinking Water N2 Local resident 51 Milk NNE3 Local resident-goats Vegetation NNE3 Local resident 53* Milk NE30 Local resident- goats 54 Milk NNE4 Local resident- goats 55 Drinking Water (Supplemental) SW3 Local resident 57 Groundwater ONSITE Well 27ddc 58 Groundwater ONSITE Well 34abb 59 Surface Water ONSITE Evaporation Pond 1 60 Surface Water ONSITE 85 Acre Reservoir 61 Surface Water ONSITE 45 Acre Reservoir 62* Vegetation ENE26 Commercial Farm 63 Surface Water ONSITE Evaporation Pond 2 64 Surface Water ONSITE Evaporation Pond 3 NOTES:

  • Designates a control site (a) Distances and direction are from the center-line of Unit 2 containment and rounded to the nearest mile Air sample sites designated with the letter 'A' are sites that have the same site number as a TLD location, but are not in the same location (e.g. site #

6 TLD location is different from site

  1. 6A air sample location; site #

4 TLD location is the same as site #

4 air sample location)

Table 2-2 Sample Collection Schedule SAMPLE SITE # AIRBORNE PARTICULATE MILK AIRBORNE RADIOIODINE VEGETATION GROUND WATER DRINKING WATER SURFACE WATER 4 W W 6A W W 7A W W 14A W W 15 W W 17A W W 21 W W 29 W W 35 W W 40 W W 46 W 47 M/AA 48 W 49 W 51 M/AA M/AA 53 M/AA 54 M/AA 55 W 57 Q 58 Q 59 Q 60 Q 61 Q 62 M/AA 63 Q 64 Q W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY

Table 2-3 Summaries of the REMP Deviations/Abnormal Events Deviation/Abnormal Event Actions Taken

1. Air Sample Site 35 had reduced pump runtime; sample INVALID for sample period 12/27/2016-1/3/2017 Air Sample Station, Site 35, had excessively low run time for Week 1 of 2017. Pump was running at beginning and end of sampling period, but runtime indicates a sample volume of 238 m
3. This volume is <55% of normal volume. Sample is considered INVALID for sample period 12/27/2016-1/3/2017 due to low sample volume. Event documented through CR 18-03209 (Table 8-1 and 8-4, Note
1) 2. Air Samples Site 15 Particulate Filter had small hole for sample period 1/10/2017-1/17/2017 Air Sample Site 15 particulate filter paper was found to have small hole, which is contrary from a normal intact filter. Sample volume, filter loading, and filter deposition is normal. This sample is considered VALID. Event documented through CR 17-00760 (Table 8-1 and 8-4, Note 2)
3. Air Sample Site 6A found not running due to lack of power 4/26/2017 Air Sample Site 6A pump found not running. Troubleman corrected power issue, returning pump to service. Normal volume per sample period is approximately 433 m
3. Volume for this sampling period was 209 m 3. Sample determined to be INVALID for sample period 4/18/2017-4/26/2017, due to insufficient sample volume. Event documented through CR 17-06259 (Table 8-1and 8-4, Note 3).
4. Air Sample Site 6A found with no power at the pole 7/25/2017 Air Sample Site 6A was found to have no power at the pole. Troubleman was dispatched and power was restored. Normal volume per sample period is approximately 433 m
3. Volume for this sampling period was 270 m 3 for sample period 7/18/17-7/25/2017 and pump was inoperable for sample period 7/25/2017-8/1/2017. Sample was determined to be INVALID for sample periods 7/18/17-8/1/2017, due to insufficient sample volume. Event documented through CR 17-10693 (Table 8-2 and 8-5, Note 4).
5. Milk Sample Site 53 analysis did not achieve required Lower Limits of Detection for I-131 for June sample An error in the Multi-channel Analyzer software, causing a reduced count time, resulted in a MDA of 1.05 pCi/L for I-131 in the June Milk Sample for Site 53. This is contrary to the ODCM required LLD for I-131 of 1 pCi/L. No activity was detected in this sample. Event documented through CR 17-10463 (Table 8-7, Note 1).
6. Drinking Water Sample Site 48 did not achieve required Lower Limits of Detection for La-140 for April sample Drinking Water Sample for Site 48 did not reach the ODCM required LLD due to sample collection date input error into analysis software. The ODCM required LLD for La-140 is 15 pCi/L. Analysis of sample reported a MDA of 22 pCi/L for La-140. No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 1).
7. Drinking Water Sample Site 46, 49, and 55 did not achieve required Lower Limits of Detection for I-131 and La-140 for April sample Drinking Water Sample for Site 46, 49, and 55 did not reach the ODCM required LLD due to sample collection date input error into analysis software. The ODCM required LLD for I-131 and La-140 is 15 pCi/L. Analysis of sample reported a MDA of 17 pCi/L for I-131 and 185 pCi/L (Site 46), 17 pCi/L for I-131 and 200 pCi/L for La-140 (Site 49), and 19 pCi/L for I-131 and 22 pCi/L for La-140 (Site 55). No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 2).
8. Drinking Water Sample Site 49 did not achieve required Lower Limits of Detection for La-140 for July sample Drinking Water Sample for Site 49 did not reach the ODCM required LLD due to excessive time between sample acquisition and analysis. The ODCM required LLD for La-140 is 15 pCi/L. Analysis of sample reported a MDA of 150 pCi/L for La-140. No activity was detected in this sample. Event documented through CR 18-00109 (Table 8-8, Note 4).
9. Evaporation Pond 1C, 2 nd Quarter Tritium sample INVALID due to reporting error. Evaporation Pond 1C, 2 nd Quarter Tritium sample had abnormally low tritium results (<320 pCi/L). Investigation of this sample analysis revealed a reporting error. Sample could not be reanalyzed.

Sample results determined to be INVALAD due to reporting error. Correction to the reporting file was made and the 3 rd Quarter results for this location were consistent with historical trends. Event is documented for trending with CR 18-00638 (Table 8-10, Note 1).

10. Water Reclamation Facility Influent sample analysis did not achieve several Lower Limits of Detection 1/24/2017 Water Reclamation Facility Influent sample volume incorrectly entered into analysis software, resulting in several missed LLDs. PVNGS receives waste water from the City of Phoenix. Water samples of the Influent are analyzed for trending purposes and do not contain plant related effluents. Event documented for trending purposes with CR 17-17823 (Table 8-10, Note 3).
11. Water Reclamation Facility Influent sample analysis did not achieve several Lower Limits of Detection 3/14/2017 Water Reclamation Facility Influent did not achieve several LLDs due to delay in sample analysis. PVNGS receives waste water from the City of Phoenix. Water samples of the Influent are analyzed for trending purposes and do not contain plant related effluents. Event documented for trending purposes with CR 17-04054 (Table 8-10, Note 4). 12. Sedimentation Basin sample analysis did not achieve several Lower Limits of Detection 1/24/2017 Sedimentation Basin sample volume incorrectly entered into analysis software, resulting in several missed LLDs. PVNGS is a zero liquid release plant; water in this basin is the result of rain water and rain runoff. Water samples of this basin are confirmatory and are analyzed for trending purposes. Event documented for trending purposes with CR 17-17823 (Table 8-10, Note 3).
13. Site 54 Milk sample was not collected within the required frequency for July 2017 The July Site 54 Milk was not collected within required frequency, per procedural guidance. The June sample was collected on 6/9/17 and the July sample was not collected until 7/20/17 due to unavailability the week before. Per the ODCM, the sample needs to be collected monthly; procedural guidance and the ODCM directs that sample be collected within the 125% surveillance test time period of 38 days, 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. All samples were collected and analyzed to the ODCM required LLD, confirming that there was no plant related impact via the milk ingestion pathway. Event documented through CR 17-10466.
14. Vegetation control locations, Site 62, did not collect procedurally required mass for each vegetation sample for October 2017. Procedural guidance directs that vegetation samples obtained be a minimum of 0.6 kg. The October 2017 samples for Site 62 (REMP Control Location) did not satisfy this requirement; 3 vegetation types of 0.519kg, 0.413kg, and 0.372kg were collected. There was no impact to the requirements of the ODCM as these are control samples with no resident samples available, as well as supplemental air samples collected weekly as a contingency. Additionally, the mass of vegetation was adequate to obtain valid analysis results, which are included in Table 8-6. Event documented through CR 17-15048.
15. Site 6 Environmental Dosimetry missing for 4 th Quarter 2017. During the 4 th Quarter Environmental Dosimetry change-out, it was discovered that the Site 6 dosimetry and stanchion was missing and could not be located. The stanchion and dosimetry were replaced for the 1 st Quarter 2018 sampling period. Event documented through CR 17-18260.
3. Sample Collection Program APS Personnel, using PVNGS procedures, collected all samples. 3.1 Water Weekly samples were collected from four (4) residence wells for monthly and quarterly composites. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. The samples were analyzed for gross beta, gamma-emitting radionuclides, and tritium. Quarterly grab samples were collected from the 45 and 85 acre Reservoirs, Evaporation Ponds 1A/B/C, 2A/B, and 3A/B, and onsite wells 34abb and 27ddc. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. Samples were analyzed for gamma-emitting radionuclides and tritium.

Treated sewage effluent from the City of Phoenix was sampled as a weekly composite at the onsite Water Resources (WR), and analyzed for gamma-emitting radionuclides. A monthly composite was analyzed for tritium. 3.2 Vegetation Vegetation samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides.

3.3 Milk Goat milk samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides, including low level I-131.

3.4 Air Air particulate filters and charcoal cartridges were collected at ten (10) sites on a weekly basis. Particulate filters were analyzed for gross beta. Charcoal cartridges were analyzed for Iodine-131. Particulate filters were composited quarterly, by location, and analyzed for gamma-emitting radionuclides. 3.5 Soil, Sludge, and Sediment Sludge samples were obtained weekly from the WR waste centrifuge (during operational periods) and analyzed for gamma-emitting radionuclides. Cooling tower sludge was analyzed for gamma-emitting radionuclides prior to disposal in the WR sludge landfill.

4. Analytical Procedures The procedures described in this report are those used by APS to routinely analyze samples 4.1 Air Particulate 4.1.1 Gross Beta A glass fiber filter sample is placed in a stainless steel planchet and counted for gross beta activity utilizing a low background gas flow proportional counter.

4.1.2 Gamma

Spectroscopy The glass fiber filters are counted on a multichannel analyzer equipped with a High-purity Germanium (HPGe) detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians. 4.2 Airborne Radioiodine 4.2.1 Gamma Spectroscopy The charcoal cartridge is counted on a multichannel analyzer equipped with a HPGe detector. The resulting spectrum is analyzed by a computer for Iodine-131.

4.3 Milk 4.3.1 Gamma Spectroscopy The sample is placed in a plastic marinelli beaker and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

4.3.2 Radiochemical

I-131 Separation Iodine in milk sample is reduced with sodium bisulfite and iodine is absorbed by the anion exchange resin. The iodine is eluted with NaOCl. Iodine is extracted from the sample with carbon tetrachloride. The iodine is back extracted from the organic with water containing sodium bisulfate and then precipitated as CuI. The precipitate is mounted in a planchet and counted for gross beta. 4.4 Vegetation

4.4.1 Gamma

Spectroscopy The sample is pureed in a food processor, placed in a one liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians. 4.5 Sludge/Sediment

4.5.1 Gamma

Spectroscopy The wet/dry sample is placed in a one-liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

4.6 Water

4.6.1 Gamma

Spectroscopy The sample is placed in a one-liter plastic marinelli beaker and counted on a multichannel analyzer equipped with a HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

4.6.2 Tritium

The sample is evaluated to determine the appropriate method of preparation prior to counting. If the sample contains suspended solids or is turbid, it may be filtered, distilled, and/or de-ionized, as appropriate. Eight (8) milliliters of sample are mixed with fifteen (15) milliliters of liquid scintillation cocktail. The mixture is dark adapted and counted for tritium activity using a liquid scintillation counting system.

4.6.3 Gross

Beta A 200-250 milliliter sample is placed in a beaker. Five (5) milliliters of concentrated nitric (HNO

3) acid is added and the sample is evaporated down to about twenty (20) milliliters. The remaining sample is transferred to a stainless steel planchet. The sample is heated to dryness and counted for gross beta in a gas flow proportional counter.

4.7 Soil 4.7.1 Gamma Spectroscopy The samples are sieved, placed in a one-liter plastic marinelli beaker, and weighed. The samples are then counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

5. Nuclear Instrumentation

5.1 Gamma

Spectrometer The Canberra Gamma Spectrometer consists of a Canberra System equipped with HPGe detectors, having resolutions of 1.73 keV and 1.88 keV (as determined by full width half max with an energy of 0.5 keV per channel) and respective efficiencies of 21.5% and 38.4% (as determined by the manufacturer with Co-60). The Canberra System is used for all gamma counting. The system uses Canberra developed software to search, identify, and quantify the peaks of interest.

5.2 Liquid

Scintillation Spectrometer A Beckman LS-6500 Liquid Scintillation Counter is used for tritium determinations. The system background averages approximately 12-16 cpm with a counting efficiency of approximately 40% using a quenched standard. 5.3 Gas Flow Proportional Counter The Tennelec S5E is a low background gas flow proportional counter for gross beta analysis. The system contains an automatic sample changer capable of counting 50 samples in succession. Average beta background count rate is about 1-2 cpm with a beta efficiency of approximately 30% for Cs-137.

6. Isotopic Detection Limits and Reporting Criteria 6.1 Lower Limits of Detection The lower limits of detection (LLD) and the method for calculation are specified in the PVNGS ODCM, Reference 4. The ODCM required a priori LLDs are presented in Table 6-1. 6.2 Data Reporting Criteria All results that are greater than the Minimum Detectable Activity (MDA) (a posteriori LLD) are reported as positive activity with its associated 2counting error. All results that are less than the MDA are reported as less than values at the associated MDA. For example, if the MDA is 12 pCi/liter, the value is reported as <12.

Typical MDA values are presented in Table 6-3.

Occasionally, the PVNGS ODCM a priori LLDs may not be achieved as a result of:

Background fluctuations Unavoidably small sample sizes The presence of interfering radionuclides Self-absorption corrections Decay corrections for short half-life radionuclides Other uncontrollable circumstances In these instances, the contributing factors will be noted in the table where the data are presented. A summary of deviations/abnormal events is presented in Table 2-3 Summaries of

the REMP Deviations/Abnormal Events and includes a description of any sample results that did not meet a priori LLD requirements. 6.3 LLD and Reporting Criteria Overview Making a reasonable estimate of the limits of detection for a counting procedure or a radiochemical method is usually complicated by the presence of significant background. It must be considered that the background or blank is not a fixed value but that a series of replicates would be normally distributed. The desired net activity is the difference between the gross and background activity distributions. The interpretation of this difference becomes a problem if the two distributions intersect as indicated in the diagram.

3. Background Count Rate: Any counter will show a certain counting rate without a sample in position. This background counting rate comes from several sources: 1) natural environmental radiation from the surrounding materials, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background counting rate will depend on the amounts of these types of radiation and the sensitivity of the counter to the radiation.
4. Background and Sample Counting Time: The amount of time devoted to the counting of the background depends on the level of activity being measured. In general, with low level samples, this time should be about equal to that devoted to counting a sample.
5. Time Interval between Sample Collection and Counting: Decay measurements are useful in identifying certain short-lived nuclides. The disintegration constant is one of the basic characteristics of a specific radionuclide and is readily determined, if the half-life is sufficiently short. To ensure the required LLDs are achieved, appropriate decay correction values are used to account for radioactive decay during transit time and sample processing.

Table 6-3 Typical MDA Values Analysis/Nuclide Water (pCi/liter) Milk (pCi/liter) Airborne Particulate or Gas (pCi/m

3) Vegetation (pCi/kg, wet) Gross Beta 2.08 0.004 H-3 326 Mn-54 10 Fe-59 20 Co-58 9 Co-60 11 Zn-65 22 Zr-95 16 Nb-95 10 I-131 10 a 1 0.04 b 49 Cs-134 9 1 0.003 b 47 Cs-137 10 1 0.003 b 61 Ba-140 33 3 La-140 13 1 NOTES: a - low level I-131 is not required since there is no drinking water pathway b - Based on 433 m 3, the normal weekly sample volume
7. Interlaboratory Comparison Program

7.1 Quality

Control Program APS maintains an extensive QA/QC Program to provide assurance that samples are collected, handled, tracked, and analyzed to specified requirements. This program includes appropriate elements of USNRC Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, Revision 1. Included in the program are procedures for sample collection, preparation and tracking, sample analysis, equipment calibration and checks, and ongoing participation in an interlaboratory comparison program. Duplicate/replicate samples are analyzed to verify analytical precision and sample methodology. Comprehensive data reviews are performed including trending of data where appropriate.

During 2017, APS analyzed the following sample types under the interlaboratory comparison program:

Beta/Gamma/ in Air Filter I-131 in Air Beta in Water Gamma in Water Tritium in Water Gamma in Milk 7.2 Intercomparison Results APS participates in a crosscheck program using vendor supplied blind radionuclide samples. Results for the interlaboratory comparison program are presented in Table 7-1.

Table 7-1 Interlaboratory Comparison Results Sample Analysis Nuclide Units Known PVNGS 1 sigma Resolution* Ratio NRC Results ID Type Value Value Error Range E11759 Gamma Water I-131 pCi/L 9.78E+01 1.05E+02 1.10E+01 10 1.07 0.60 - 1.66 Acceptable Ce-141 pCi/L 1.45E+02 1.51E+02 6.00E+00 25 1.04 0.75 - 1.33 Acceptable Cr-51 pCi/L 2.91E+02 2.65E+02 2.50E+01 11 0.91 0.60 - 1.66 Acceptable Cs-134 pCi/L 1.20E+02 1.14E+02 3.10E+00 37 0.95 0.75 - 1.33 Acceptable Cs-137 pCi/L 1.40E+02 1.46E+02 5.30E+00 28 1.04 0.75 - 1.33 Acceptable Co-58 pCi/L 1.50E+02 1.56E+02 6.60E+00 24 1.04 0.75 - 1.33 Acceptable Mn-54 pCi/L 1.65E+02 1.68E+02 6.30E+00 27 1.02 0.75 - 1.33 Acceptable Fe-59 pCi/L 1.29E+02 1.37E+02 5.50E+00 25 1.06 0.75 - 1.33 Acceptable Zn-65 pCi/L 2.00E+02 2.12E+02 8.80E+00 24 1.06 0.75 - 1.33 Acceptable Co-60 pCi/L 1.83E+02 1.90E+02 4.50E+00 42 1.04 0.75 - 1.33 Acceptable E11760 Beta Filter G. Beta pCi/ea 9.71E+01 1.00E+02 2.30E+00 43 1.03 0.75 - 1.33 Acceptable E11761 I-131 Cartridge I-131 pCi/ea 9.80E+01 9.91E+01 5.10E+00 19 1.01 0.75 - 1.33 Acceptable E11762 Gamma Filter Ce-141 pCi/ea 9.81E+01 1.04E+02 2.40E+00 43 1.06 0.75 - 1.33 Acceptable Cr-51 pCi/ea 1.96E+02 2.02E+02 9.30E+00 22 1.03 0.75 - 1.33 Acceptable Cs-134 pCi/ea 8.11E+01 7.50E+01 1.20E+00 63 0.92 0.80 - 1.25 Acceptable Cs-137 pCi/ea 9.46E+01 1.04E+02 2.90E+00 36 1.10 0.75 - 1.33 Acceptable Co-58 pCi/ea 1.01E+02 1.07E+02 2.80E+00 38 1.06 0.75 - 1.33 Acceptable Mn-54 pCi/ea 1.11E+02 1.25E+02 3.00E+00 42 1.13 0.75 - 1.33 Acceptable Fe-59 pCi/ea 8.71E+01 9.74E+01 2.30E+00 42 1.12 0.75 - 1.33 Acceptable Zn-65 pCi/ea 1.35E+02 1.52E+02 3.80E+00 40 1.13 0.75 - 1.33 Acceptable Co-60 pCi/ea 1.24E+02 1.31E+02 2.10E+00 62 1.06 0.80 - 1.25 Acceptable E11763 Gamma Milk I-131 pCi/L 4.06E+01 4.13E+01 2.80E+00 15 1.02 0.60 - 1.66 Acceptable Ce-141 pCi/L 2.04E+01 2.31E+01 1.40E+00 17 1.13 0.75 - 1.33 Acceptable Cr-51 pCi/L 4.08E+01 3.28E+01 4.60E+00 7 0.80 0.50 - 2.00 Acceptable Cs-134 pCi/L 1.69E+01 1.65E+01 5.00E-01 33 0.98 0.75 - 1.33 Acceptable Cs-137 pCi/L 1.97E+01 2.04E+01 1.10E+00 19 1.04 0.75 - 1.33 Acceptable Co-58 pCi/L 2.10E+01 2.26E+01 1.30E+00 17 1.08 0.75 - 1.33 Acceptable Mn-54 pCi/L 2.31E+01 2.40E+01 1.40E+00 17 1.04 0.75 - 1.33 Acceptable Fe-59 pCi/L 1.81E+01 2.02E+01 1.40E+00 14 1.12 0.60 - 1.66 Acceptable Zn-65 pCi/L 2.80E+01 3.11E+01 1.50E+00 21 1.11 0.75 - 1.33 Acceptable Co-60 pCi/L 2.57E+01 2.26E+01 9.00E-01 25 0.88 0.75 - 1.33 Acceptable

Table 7-1 Interlaboratory Comp arison Results (Continued)

E11764 H-3 Water H-3 pCi/L 9.98E+03 9.36E+03 3.26E+02 29 0.94 0.75 - 1.33 Acceptable E11981 Beta Water G. Beta pCi/L 2.71E+02 2.95E+02 6.30E+00 47 1.09 0.75 - 1.33 Acceptable E11982 Beta Filter G. Beta pCi 8.83E+01 8.86E+01 2.13E+00 42 1.00 0.75 - 1.33 Acceptable E11983 I-131 Cartridge I-131 pCi 6.43E+01 6.59E+01 4.40E+00 15 1.02 0.60 - 1.66 Acceptable E11984 Gamma Filter Ce-141 pCi 7.06E+01 7.28E+01 8.20E+00 9 1.03 0.60 - 1.66 Acceptable Cr-51 pCi 1.76E+02 1.85E+02 4.43E+01 4 1.05 0.50 - 2.00 Acceptable Cs-134 pCi 1.63E+02 1.32E+02 7.40E+00 18 0.81 0.75 - 1.33 Acceptable Cs-137 pCi 1.39E+02 1.58E+02 1.97E+01 8 1.14 0.60 - 1.66 Acceptable Co-58 pCi 9.49E+01 1.05E+02 1.18E+01 9 1.11 0.60 - 1.66 Acceptable Mn-54 pCi 9.96E+01 1.19E+02 1.23E+01 10 1.19 0.60 - 1.66 Acceptable Fe-59 pCi 1.02E+02 1.25E+02 1.10E+01 11 1.23 0.60 - 1.66 Acceptable Zn-65 pCi 1.49E+02 1.78E+02 1.66E+01 11 1.19 0.60 - 1.66 Acceptable Co-60 pCi 2.13E+02 2.25E+02 1.32E+01 17 1.06 0.75 - 1.33 Acceptable

  • calculated from PVNGS value/1 sigma error value
    • Eckert & Ziegler Analytics, Inc. NIST-traceable known value NRC Acceptance Criteria 1 Resolution Ratio 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.80-1.25 >200 0.85-1.18 1 From NRC Inspection Manual, procedure #84750, "Radioactive Waste Treatment, and Effluent and Environmental Monitoring"

Table 7-1 Interlaboratory Comparison Results (Continued)

Sample Analysis ERA PT Nuclide Units PVNGS Assigned Value 1 Acceptance Limit 2 Results Type Type Study Value Water Tritium RAD-111 H-3 pCi/L 5,910 6,250 5390-6880 Acceptable Water Gamma RAD-111 Ba-133 pCi/L 73.3 73.7 61.7-81.1 Acceptable Cs-134 pCi/L 45.7 53 42.8-58.3 Acceptable Cs-137 pCi/L 51.5 52.9 47.6-61.1 Acceptable Co-60 pCi/L 68.1 69.5 62.6-78.9 Acceptable Zn-65 pCi/L 374 348 313-406 Acceptable 1 The ERA assigned values are established per the guidelines contained in the National Environmental Laboratory Accreditation Conference (NELAC) program criteria as applicable.

2 "Acceptance Limits" have been calculated per ERA's Standard Operating Procedure for the Generation of Performance Acceptance Limits.

8. Data Interpretation and Conclusions Associated with the analytical process are potential random and systematic errors. Systematic errors can be caused by instrument malfunctions, incomplete precipitation, back scattering, and self-absorption.

Efforts are made to minimize both systematic and random errors in the data reported. Systematic errors are minimized by performing reviews throughout the analysis. For example, instruments are checked routinely with radioactive sources, and recovery and self-absorption factors based on individual sample analyses are incorporated into the calculation equations where necessary. Random errors are reduced by comparing all data to historical data for the same site and performing comparisons between analytical results when available. In addition, when data do not appear to match historical results, analyses may be rerun on a separate aliquot of the sample to verify the presence of the activity. The acceptance of data is dependent upon the results of quality control samples and is part of the data review process for all analytical results.

The "plus or minus value" reported with each analytical result represents the counting error associated with the result and gives the 95% confidence (2) interval around the data.

Most samples contain radioactivity associated with natural background/cosmic radioactivity (e.g. K-40, Th-234, Be-7). Gross beta results for drinking water and air are due to natural background. Gamma-emitting radionuclides, which can be attributed to natural background sources, are not indicated in this report. Results and interpretation of the data for all of the samples analyzed during 2017 are presented in the following sections.

8.1 Air Particulates Weekly gross beta results, in quarterly format, are presented in Table 8-1 and Table 8-2. Gross beta activity at indicator locations ranged from 0.014 to 0.057 pCi/m

3. Mean quarterly activity is normally calculated using weekly activity over a thirteen (13) week period. Also presented in the tables are the weekly mean values of all the sites as well as the percent relative standard deviation (RSD %) for the data.

Table 8-3 displays the results of gamma spectroscopy on the quarterly composites of the weekly samples. No plant-related activity was identified 8.2 Airborne Radioiodine Table 8-4 and Table 8-5 present the quarterly radioi odine results. Radioiodine was not observed in any samples.

8.3 Vegetation

Table 8-6 presents gamma isotopic data for the vegetation samples. No gamma-emitting radionuclides were observed in any of the samples.

8.4 Milk Table 8-7 presents gamma isotopic data for the goat milk samples. No gamma-emitting radionuclides were observed in any of the samples.

8.5 Drinking

Water Samples were analyzed for gross beta, tritium, and gamma-emitting ra dionuclides. Results of these analyses are presented in Table 8-8. No tritium or gamma-emitting radionuclides were detected in any samples. Gross beta activity ranged from less than detectable to a high of 6.84 pCi/liter. The gross beta activity is attributable to natural (background) radioactive materials. 8.6 Groundwater Groundwater samples were analyzed from two onsite wells (regional aquifer) for tritium and gamma-emitting radionuclides. Results obtained from the analysis of the samples are presented in Table 8-9.

No tritium or gamma-emitting radionuclides were observed in any of the samples. 8.7 Surface Water Surface water samples from the Reservoirs and Evaporation Ponds were analyzed for tritium and gamma-emitting radionuclides. The two Reservoirs contain processed sewage water from the City of Phoenix and are approximately 45 and 85 acres in size. The three Evaporation Ponds receive mostly circulating water from main turbine condenser cooling and are about 200-250 acres each.

Sample results are presented in Table 8-10. I-131 was observed in both reservoirs and Evaporation Pond 1A. The I-131 levels ranged from 8 pCi/L - 13 pCi/L. I-131 in these surface water locations is a result of radiopharmaceutical I-131 in the Phoenix sewage effluent and is not attributable to plant effluents.

Tritium was routinely observed in the Evaporation Ponds. The highest concentration was 1680 pCi/liter.

Tritium was not detected in the Reservoirs. The tritium identified in the Evaporation Ponds has been attributed to permitted plant gaseous effluent releases and secondary plant liquid discharges (e.g.

condensate overboard discharge, secondary side steam generator drains, secondary plant sumps, demineralizer regeneration waste). The tritium concentrations were compared to historical values and are considered typical for the Evaporation Ponds.

8.8 Sludge

and Sediment 8.8.1 WR Centrifuge Waste Sludge

Sludge samples were obtained from the WR centrifuge and analyzed by gamma spectroscopy. I-131 activity in the sludge is consistent with historical values and, as previously discussed, is due to radiopharmaceuticals in the WR Influent. The concentration of I-131 ranged from "no detectable" to 959 pCi/kg.

Results for WR centrifuge waste sludge can be found in Table 8-11. 8.8.2 Cooling Tower Sludge

Sludge/sediment originating from the Unit 1 and Unit 2 Cooling Towers and Circulating Water canals was disposed of in the WR sludge landfill during 2017. Sample results can be found in Table 8-11.

8.9 Data Trends Figure 8-1 through Figure 8-8 present data in graphical format. Historical data are displayed for comparison where practical. 8.10 Hard-To-Detect Radionuclide Results Table 8-12 shows the results of the three subsurface samples obtained from 3 tritium monitoring points. These samples were analyzed for hard-to-detect radionuclides (e.g. C-14, Fe-55, Ni-63, Sr-90) and all results were <MDA. These results indicate that no leaks from plant systems have affected groundwater.

Table 8-1 Particulate Gross Beta in Air 1st-2nd Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note127-Dec-163-Jan-170.0260.0230.0290.0270.0290.0260.0280.0270.03630.0280.0276.41 23-Jan-1710-Jan-170.0330.0320.0340.0290.0240.0330.0330.0290.0270.0270.03011.0310-Jan-1717-Jan-170.0270.0230.0270.0250.0250.0260.0280.0260.0240.0260.0256.02417-Jan-1724-Jan-170.0240.0220.0230.0240.0230.0250.0260.0200.0200.0220.0238.7 524-Jan-1731-Jan-170.0170.0200.0210.0190.0190.0220.0190.0190.0190.0180.0197.7631-Jan-177-Feb-170.0350.0340.0310.0410.0280.0290.0380.0230.0340.0370.03315.8 77-Feb-1714-Feb-170.0240.0240.0230.0210.0200.0250.0230.0210.0210.0220.0227.1 814-Feb-1721-Feb-170.0190.0200.0220.0210.0210.0230.0230.0230.0250.0230.0227.9921-Feb-1728-Feb-170.0190.0170.0140.0180.0170.0180.0160.0170.0150.0170.0178.81028-Feb-177-Mar-170.0260.0260.0230.0250.0230.0290.0250.0240.0230.0250.0256.9117-Mar-1714-Mar-170.0270.0280.0290.0280.0250.0330.0300.0270.0280.0270.0286.81214-Mar-1721-Mar-170.0400.0450.0420.0360.0400.0450.0410.0390.0420.0390.0416.91321-Mar-1727-Mar-170.0210.0200.0200.0220.0190.0220.0190.0230.0220.0210.0216.1Mean0.0260.0260.0260.0260.0240.0270.0270.0240.0250.0260.0263.8Note 1: CR 18-03209 Site 35 had reduced pump runtime. Volume was 238 m^3. Sample INVALID due to insufficient sample volumeNote 2: CR 17-00760 Site 15 Particulate Filter had small hole. Sample volume, filter loading, and filter deposition normal. Sample VALID. (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note1427-Mar-174-Apr-170.0160.0180.0190.0170.0160.0200.0200.0180.0170.0190.0188.2154-Apr-1711-Apr-170.0240.0290.0200.0200.0180.0210.0220.0290.0190.0240.02316.91611-Apr-1718-Apr-170.0330.0300.0310.0300.0320.0340.0310.0310.0320.0300.0314.41718-Apr-1726-Apr-170.0270.01810.0220.0250.0240.0280.0210.0240.0230.0240.0249.131826-Apr-172-May-170.0260.0220.0240.0230.0220.0240.0210.0200.0240.0200.0237.9 192-May-179-May-170.0290.0220.0260.0270.0270.0250.0270.0270.0270.0260.0266.4209-May-1716-May-170.0270.0270.0280.0290.0290.0310.0280.0270.0280.0230.0287.42116-May-1723-May-170.0230.0230.0230.0220.0220.0250.0230.0240.0230.0240.0233.82223-May-1730-May-170.0230.0260.0270.0260.0260.0310.0310.0290.0290.0300.0289.22330-May-176-Jun-170.0370.0370.0370.0360.0370.0340.0360.0340.0360.0380.0363.8246-Jun-1713-Jun-170.0260.0240.0250.0250.0260.0300.0280.0270.0260.0270.0266.12513-Jun-1720-Jun-170.0350.0350.0350.0310.0330.0330.0360.0330.0330.0310.0344.82620-Jun-1727-Jun-170.0400.0370.0400.0370.0390.0450.0410.0400.0420.0430.0406.3Mean0.0280.0280.0270.0270.0270.0290.0280.0280.0280.0280.0282.6Note 3: CR 17-06259 Site 6 pump found not running due to power supply to pole severed. Runtime 81.2 hrs of typical 168 hrs. Sample INVALID due to insufficient runtime.PARTICULATE GROSS BETA IN AIR 1st QUARTERODCM required samples denoted by *units are pCi/m 3PARTICULATE GROSS BETA IN AIR 2nd QUARTERODCM re quired sam ples denoted b y *units are pCi/m 3 Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note 2727-Jun-173-Jul-170.0400.0300.0370.0350.0320.035 0.0340.0340.0370.0370.0358.1283-Jul-1711-Jul-170.0320.0360.0350.0370.0340.0370.0370.0370.0370.0360.0365.0 2911-Jul-1718-Jul-170.0280.0270.0300.0300.0290.0310.0310.0300.0310.0340.0306.53018-Jul-1725-Jul-170.0290.0270.0320.0290.0270.0320.0280.0250.0290.0260.0288.743125-Jul-171-Aug-170.0310.0300.0300.0280.0310.0270.0280.0290.0280.0294.84321-Aug-178-Aug-170.0290.0300.0270.0280.0290.0250.0290.0290.0230.0250.0278.7338-Aug-1715-Aug-170.0340.0280.0320.0360.0320.0330.0320.0300.0310.0340.0326.9 3415-Aug-1722-Aug-170.0300.0250.0260.0280.0270.0260.0230.0250.0220.0220.02510.0 3522-Aug-1729-Aug-170.0350.0320.0290.0340.0320.0340.0320.0320.0320.0320.0324.4 3629-Aug-175-Sep-170.0420.0390.0360.0370.0400.0350.0350.0400.0390.0350.0386.6375-Sep-1712-Sep-170.0440.0350.0390.0420.0410.0440.0410.0380.0410.0410.0417.0 3812-Sep-1719-Sep-170.0340.0270.0300.0280.0320.0310.0300.0180.0320.0270.02915.9 3919-Sep-1726-Sep-170.0290.0310.0280.0260.0260.0260.0270.0300.0260.0320.0288.0Mean0.0340.0310.0320.0320.0310.0320.0310.0300.0320.0310.0323.2Note 4: CR 17-10693 Site 6 pump found not running due to power failure at pole. Sample voulme 270m^3 of expected 433m^3. Sample INVALID due to insufficient sample volume(control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note4026-Sep-173-Oct-170.0420.0430.0440.0430.0440.0490.0490.0440.0400.0420.0446.7413-Oct-1710-Oct-170.0410.0380.0380.0380.0380.0420.0400.0390.0380.0380.0393.84210-Oct-1717-Oct-170.0400.0380.0390.0320.0360.0410.0340.0400.0370.0270.03711.9 4317-Oct-1724-Oct-170.0330.0330.0340.0350.0350.0350.0340.0340.0340.0350.0342.2 4424-Oct-1731-Oct-170.0350.0400.0340.0330.0300.0330.0380.0320.0400.0380.03510.24531-Oct-176-Nov-170.0360.0330.0310.0340.0350.0330.0310.0350.0310.0320.0335.5466-Nov-1714-Nov-170.0320.0330.027 0.0280.0300.0270.0260.0290.0260.0250.0289.84714-Nov-1720-Nov-170.0460.0380.0280.0270.0340.0290.0300.0260.0320.0310.03218.3 4820-Nov-1728-Nov-170.0480.0390.0410.0410.0400.0300.0400.0430.0400.0420.04011.4 4928-Nov-175-Dec-170.0570.0530.0530.0470.0560.0500.0540.0520.0500.0520.0525.6 505-Dec-1712-Dec-170.0310.0260.0280.0230.0240.0330.0270.0300.0270.0240.02711.8 5112-Dec-1719-Dec-170.0480.0470.0480.0450.0420.0430.0450.0470.0460.0450.0464.5 5219-Dec-1726-Dec-170.0520.0450.0420.0390.0430.0470.0460.0400.0430.0450.0448.6Mean0.0410.0390.0370.0360.0380.0380.0380.0380.0370.0370.0384.1Annual Average0.032270.030810.030590.030130.029980.031640.030960.030090.030440.030320.03077.9144PARTICULATE GROSS BETA IN AIR 3rd QUARTERODCM re quired sam ples denoted b y *units are pCi/m 33rd QuarterPARTICULATE GROSS BETA IN AIR 4th QUARTERODCM required samples denoted by *units are pCi/m 3 Table 8-3 Gamma in Air Filter Composites (control)QUARTERSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteENDPOINTNUCLIDE46A*

7A14A*15*17A2129*3540*Note27-Mar-17Cs-134<0.002<0.001<0.004<0.003<0.003<0.005<0.003<0.001<0.006<0.003Cs-137<0.002<0.002<0.005<0.003<0.002<0.004<0.003<0.002<0.002<0.00227-Jun-17Cs-134<0.002<0.006<0.001<0.004<0.002<0.002<0.001<0.004<0.001<0.001Cs-137<0.003<0.008<0.002<0.002<0.001<0.002<0.001<0.004<0.002<0.00126-Sep-17Cs-134<0.002<0.004<0.0007<0.003<0.002<0.003<0.002<0.003<0.002<0.002Cs-137<0.002<0.005<0.0009<0.002<0.002<0.004<0.0009<0.004<0.003<0.00226-Dec-17Cs-134<0.003<0.001<0.0007<0.002<0.001<0.004<0.002<0.002<0.002<0.001Cs-137<0.003<0.002<0.0009<0.0005<0.0009<0.002<0.002<0.006<0.002<0.006Note 1: Site 35, See Note 1 from 1st Quarter Gross BetaNote 2: Site 15, See Note 2 from 1st Quarter Gross BetaNote 3: Site 6A, See Note 3 from 2nd Quarter Gross Betaunits are pCi/m 31, 2 3ODCM required samples denoted by *GAMMA IN AIR FILTER COMPOSITES Table 8-4 Radioiodine in Air 1st-2nd Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note127-Dec-163-Jan-17<0.039<0.031<0.045<0.031<0.046<0.0340<0.045<0.008<0.044<0.052123-Jan-1710-Jan-17<0.024<0.029<0.042<0.026<0.033<0.030<0.033<0.028<0.018<0.042310-Jan-1717-Jan-17<0.036<0.028<0.040<0.028<0.041<0.036<0.053<0.034<0.017<0.0422417-Jan-1724-Jan-17<0.013<0.042<0.013<0.030<0.007<0.062<0.034<0.019<0.063<0.039 524-Jan-1731-Jan-17<0.036<0.026<0.027<0.018<0.054<0.018<0.034<0.039<0.036<0.034 631-Jan-177-Feb-17<0.038<0.026<0.042<0.026<0.042<0.037<0.055<0.024<0.026<0.034 77-Feb-1714-Feb-17<0.040<0.032<0.032<0.018<0.033<0.037<0.061<0.020<0.029<0.050 814-Feb-1721-Feb-17<0.024<0.018<0.047<0.022<0.042<0.034<0.012<0.035<0.023<0.042 921-Feb-1728-Feb-17<0.031<0.027<0.034<0.026<0.042<0.044<0.033<0.027<0.028<0.0121028-Feb-177-Mar-17<0.039<0.017<0.037<0.022<0.032<0.030<0.041<0.028<0.022<0.040117-Mar-1714-Mar-17<0.035<0.041<0.044<0.024<0.041<0.036<0.028<0.033<0.045<0.020 1214-Mar-1721-Mar-17<0.037<0.024<0.036<0.024<0.053<0.041<0.036<0.0360<0.025<0.0131321-Mar-1727-Mar-17<0.029<0.032<0.059<0.031<0.040<0.041<0.040<0.050<0.035<0.067Note 1: CR 18-03209 Site 35 had reduced pump runtime. Volume was 238 m^3. Sample INVALID due to insufficient sample volumeNote 2: CR 17-00760 Site 15 Particulate Filter had small hole. Sample volume, filter loading, and filter deposition normal. Sample VALID. (control)Week #DATEDATE46A*7A14A*15*17A2129*3540*Note1427-Mar-174-Apr-17<0.023<0.021<0.021<0.035<0.026<0.032<0.032<0.038<0.047<0.047154-Apr-1711-Apr-17<0.030<0.051<0.035<0.035<0.027<0.043<0.029<0.056<0.036<0.034 1611-Apr-1718-Apr-17<0.054<0.031<0.042<0.019<0.031<0.042<0.012<0.039<0.034<0.0431718-Apr-1726-Apr-17<0.036<0.065<0.042<0.028<0.043<0.030<0.043<0.025<0.028<0.03031826-Apr-172-May-17<0.054<0.049<0.022<0.067<0.052<0.008<0.065<0.033<0.037<0.066 192-May-179-May-17<0.031<0.007<0.037<0.037<0.026<0.033<0.034<0.050<0.037<0.033 209-May-1716-May-17<0.018<0.033<0.031<0.026<0.040<0.018<0.019<0.007<0.040<0.0222116-May-1723-May-17<0.034<0.023<0.042<0.023<0.033<0.032<0.023<0.027<0.037<0.0232223-May-1730-May-17<0.036<0.019<0.035<0.024<0.063<0.046<0.013<0.050<0.028<0.046 2330-May-176-Jun-17<0.035<0.022<0.049<0.018<0.033<0.033<0.054<0.031<0.024<0.035246-Jun-1713-Jun-17<0.044<0.025<0.027<0.018<0.023<0.031<0.031<0.032<0.024<0.029 2513-Jun-1720-Jun-17<0.020<0.024<0.034<0.034<0.042<0.039<0.039<0.028<0.034<0.0392620-Jun-1727-Jun-17<0.030<0.026<0.042<0.026<0.054<0.040<0.042<0.034<0.018<0.035Note 3: CR 17-06259 Site 6A pump found not running due to power supply to pole severed. Runtime 81.2 hrs of typical 168 hrs. Sample INVALID due to insufficient runtime

.required LLD <0.070RADIOIODINE IN AIR 1st QUARTERRADIOIODINE IN AIR 2nd QUARTERODCM re quired sam ples denoted b y *units are pCi/m 3 required LLD <0.070ODCM required samples denoted by *units are pCi/m 3 Table 8-5 Radioiodine in Air 3rd-4th Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note2727-Jun-173-Jul-17<0.0216<0.0472<0.0261<0.0384<0.0381<0.0484<0.0449<0.0263<0.0487<0.0081283-Jul-1711-Jul-17<0.0525<0.0366<0.0230<0.0108<0.0058<0.0292<0.0230<0.0428<0.0232<0.02922911-Jul-1718-Jul-17<0.0067<0.0319<0.0413<0.0218<0.0405<0.0308<0.0121<0.0254<0.0468<0.00653018-Jul-1725-Jul-17<0.0189<0.0609<0.0479<0.0253<0.0469<0.0334<0.0138<0.0207<0.0386<0.033843125-Jul-171-Aug-17<0.0265<0.0118<0.0471<0.0064<0.0471<0.0261<0.0422<0.0225<0.01804321-Aug-178-Aug-17<0.0484<0.0309<0.0666<0.0234<0.0452<0.0256<0.0690<0.0325<0.0337<0.0297 338-Aug-1715-Aug-17<0.0288<0.0404<0.0584<0.0315<0.0415<0.0186<0.0515<0.0219<0.0417<0.03333415-Aug-1722-Aug-17<0.0070<0.0427<0.0590<0.0183<0.0494<0.0260<0.0393<0.0078<0.0574<0.02673522-Aug-1729-Aug-17<0.0415<0.0554<0.0261<0.0339<0.0318<0.0418<0.0228<0.0334<0.0066<0.0596 3629-Aug-175-Sep-17<0.0069<0.0422<0.0350<0.0185<0.0501<0.0265<0.0433<0.0070<0.0502<0.0234 375-Sep-1712-Sep-17<0.0487<0.0478<0.0327<0.0492<0.0328<0.0121<0.0262<0.0540<0.0182<0.0553 3812-Sep-1719-Sep-17<0.0480<0.0254<0.0116<0.0063<0.0462<0.0174<0.0567<0.0251<0.0531<0.0222 3919-Sep-1726-Sep-17<0.0236<0.0320<0.0268<0.0442<0.0233<0.0329<0.0504<0.0235<0.0444<0.0240Note 4: CR 17-10693 Site 6A pump found not running due to power failure at pole. Sample voulme 270m^3 of expected 433m^3. Sample INVALID due to insufficient sample volume(control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note4026-Sep-173-Oct-17<0.0287<0.0330<0.0419<0.0179<0.0542<0.0188<0.0326<0.0176<0.0123<0.0321 413-Oct-1710-Oct-17<0.0230<0.0179<0.0293<0.0227<0.0233<0.0227<0.0323<0.0265<0.0265<0.0181 4210-Oct-1717-Oct-17<0.0231<0.0226<0.0232<0.0263<0.0294<0.0233<0.0288<0.0181<0.0181<0.0177 4317-Oct-1724-Oct-17<0.0325<0.0200<0.0319<0.0248<0.0321<0.0294<0.0250<0.0203<0.0203<0.0251 4424-Oct-1731-Oct-17<0.0221<0.0319<0.0281<0.0218<0.0247<0.0321<0.0230<0.0219<0.0349<0.0235 4531-Oct-176-Nov-17<0.0292<0.0391<0.0407<0.0322<0.0516<0.0445<0.0400<0.0502<0.0278<0.0599466-Nov-1714-Nov-17<0.0222<0.0276<0.0469<0.0233<0.0364<0.0168<0.0359<0.0270<0.0197<0.03594714-Nov-1720-Nov-17<0.0482<0.0377<0.0075<0.0378<0.0361<0.0139<0.0443<0.0335<0.0656<0.0384 4820-Nov-1728-Nov-17<0.0436<0.0062<0.0219<0.0232<0.0425<0.0291<0.0264<0.0064<0.0270<0.0311 4928-Nov-175-Dec-17<0.0286<0.0280<0.0072<0.0315<0.0249<0.0314<0.0325<0.0073<0.0071<0.0251 505-Dec-1712-Dec-17<0.0185<0.0412<0.0583<0.0218<0.0396<0.0195<0.0315<0.0333<0.0322<0.02195112-Dec-1719-Dec-17<0.0478<0.0390<0.0457<0.0320<0.0382<0.0311<0.0595<0.0339<0.0281<0.0534 5219-Dec-1726-Dec-17<0.0390<0.0349<0.0523<0.0132<0.0524<0.0478<0.0630<0.0436<0.0677<0.0457required LLD <0.070RADIOIODINE IN AIR 3rd QUARTERODCM required samples denoted by *units are pCi/m 3ODCM re quired sam ples denoted b y *units are pCi/m 3RADIOIODINE IN AIR 4th QUARTERrequired LLD <0.070 Table 8-6 Vegetation

<60<60<80LOCATIONTYPEDATE COLLECTEDI-131Cs-134Cs-137NoteLOCALLettuce16-Feb-17<33<35<40RESIDENCELettuce16-Mar-17<35<21<43(Site #47)*Lettuce20-Apr-17<30<22<59Lettuce18-May-17<52<59<40Lettuce15-Jun-17<51<56<56Broccolli Leaf21-Dec-17<48<48<77Lettuce20-Jan-17<54<54<47Lettuce16-Feb-17<31<39<54Lettuce16-Mar-17<23<35<39Lettuce20-Apr-17<42<38<50Spinach20-Apr-17<37<35<46COMMERCIALFARM(Site #62)*Spinach19-Oct-17<55<55<47Kale19-Oct-17<45<45<48Arugula19-Oct-17<47<51<63Kale16-Nov-17<56<45<42Spinach16-Nov-17<44<40<39Arugula16-Nov-17<50<47<76Tango Lettuce21-Dec-17<60<48<54Grean Oak Lettuce21-Dec-17<44<39<14Red Leaf Lettuce21-Dec-17<35<46

<69Lettuce20-Apr-17<54<50<49Lettuce18-May-17<56<44<59Lettuce16-Jun-17<46<59<48Sample Not Available for JuneSample Not Available For JulySample Not Available for JanuaryLOCAL RESIDENCE (Site #51)Sample Not Available for AugustSample Not Available for SeptemberSample Not Available for NovemberSample Not Available for OctoberSample Not Available for JulySample Not Available for AugustSample Not Available for SeptemberSample Not Available for DecemberSample Not Available for JanuarySample Not Available for FebruarySample Not Available for MarchVEGETATIONODCM required samples denoted by *units are pCi/kg, wetSample Not Available for MaySample Not Available for OctoberSample Not Available for JulySample Not Available for AugustSample Not Available for SeptemberSample Not Available for November Table 8-7 Milk SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137Ba-140La-140NoteLocal ResidentGoats(Site #51)*16-Jun-17<1<1<1<3<120-Jul-17<1<1<1<3<117-Aug-17<1<1<1<3<121-Sep-17<1<1<1<3<119-Oct-17<1<1<1<3<116-Nov-17<1<1<1<3<1 21-Dec-17<1<1<1<3<126-Jan-17<1<1<1<3<123-Feb-17<1<1<1<3<123-Mar-17<1<1<1<3<1Local Resident27-Apr-17<1<1<1<3<1Goats25-May-17<1<1<1<3<1(Site #53)*22-Jun-17<1<1<1<3<1127-Jul-17<1<1<1<3<124-Aug-17<1<1<1<3<113-Jan-17<1<1<1<3<1Local Resident09-Feb-17<1<1<1<3<1Goats09-Mar-17<1<1<1<3<1(Site #54)*13-Apr-17<1<1<1<3<111-May-17<1<1<1<3<109-Jun-17<1<1<1<3<120-Jul-17<1<1<1<3<110-Aug-17<1<1<1<3<114-Sep-17<1<1<1<3<1 13-Oct-17<1<1<1<3<109-Nov-17<1<1<1<3<114-Dec-17<1<1<1<3<1No Sample Available for JanuaryNo Sample Available for FebruaryODCM required samples denoted by *units are pCi/literNo Sample Available for MarchNo Sample Available for MayNo Sample Available for AprilNo Sample Available for SeptemberNo Sample Available for OctoberNo Sample Available for NovemberNo Sample Available for December Table 8-8 Drinking Water

<2000SAMPLEMONTH<15<15<30<15<30<15<30<15<15<18<60<15Qtrly<4.0LOCATIONENDPOINTMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumGross BetaNote31-Jan-17<5<5<11<5<10<5<10<6<5<5<19<125.0428-Feb-17<6<6<11<6<12<6<11<5<6<6<17<103.871.9527-Mar-17<12<10<28<12<27<12<18<9<11<11<28<14<323<1.8826-Apr-17<9<7<20<10<16<12<20<14<7<9<38<226.262.071LOCAL30-May-17<9<12<21<12<26<12<19<9<11<9<29<145.331.92RESIDENCE27-Jun-17<12<12<20<7<24<15<21<11<11<10<35<13<3264.032.01(Site #48) *25-Jul-17<1<1<2<1<2<2<2<2<0.9<1<5<145.561.95329-Aug-17<7<8<17<8<18<9<15<8<8<10<23<154.371.9226-Sep-17<12<12<23<15<29<13<22<11<14<10<40<13<205<3.2931-Oct-17<8<5<16<7<18<7<13<7<6<8<25<145.551.7928-Nov-17<15<10<25<13<28<13<19<10<12<12<31<96.071.7826-Dec-17<12<12<21<13<26<14<22<11<13<15<39<14<306<3.0931-Jan-17<7<6<13<7<13<7<10<6<6<7<21<125.931.9128-Feb-17<7<7<17<6<17<9<14<8<7<8<24<112.270.9527-Mar-17<15<15<23<14<29<13<24<13<12<13<37<11<323<1.9926-Apr-17<13<9<21<9<19<11<20<18<9<12<46<2115.721.932LOCAL30-May-17<9<10<17<11<17<11<19<9<9<12<33<115.401.85RESIDENCE27-Jun-17<9<8<15<9<20<8<19<9<7<10<32<14<3296.842.02(Site #55)25-Jul-17<0.9<1<.2<0.9<2<2<.2<.2<0.8<0.8<5<153.551.78329-Aug-17<8<7<15<5<15<6<12<7<6<7<25<125.631.8526-Sep-17<8<6<13<7<17<7<13<7<7<7<23<14<2003.271.9531-Oct-17<11<9<21<9<20<10<11<9<9<13<37<14<3.9028-Nov-17<10<11<21<6<24<12<18<8<8<9<27<12<3.9126-Dec-17<7<9<16<7<16<8<15<9<8<8<29<15<3634.191.90 5Note 2: CR 17-10476 LLD for I-131 and La-140 not met due to error in sample collection date input into analysis softwareNote 5: CR 18-01383 Oringal analysis indicated possible Co-58 activity. Confirmatory count was done; verified no Co58 activity present. DRINKING WATER ODCM required samples denoted by *units are pCi/literNote 1: CR 17-10476 LLD for La-140 not met due to error in sample collection date input into analysis softwareNote 3: Long count time to achieve LLDs resulted in lower than typical MDAs on most nuclides. Long count time due to extensive time between sam ple ac quisition and anal ysis time Table 8-8 Drinking Water (Continued)

<2000SAMPLEMONTH<15<15<30<15<30<15<30<15<15<18<60<15Qtrly<4.0LOCATIONENDPOINTMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumGross BetaNote31-Jan-17<5<5<8<4<9<4<8<4<4<4<15<82.851.3728-Feb-17<13<13<21<13<26<14<23<13<11<13<42<72.621.3327-Mar-17<11<9<23<12<17<11<16<9<8<10<29<12<3253.651.5426-Apr-17<12<9<23<12<29<13<19<17<8<10<50<1853.141.47230-May-17<10<8<23<7<17<9<17<8<8<6<34<142.321.34LOCAL27-Jun-17<9<9<17<6<19<11<15<9<8<7<26<14<3273.771.88RESIDENCE25-Jul-17<1<1<3<1<3<1<2<3<1<1< 7<15<2.193(Site #46) *29-Aug-17<5<7<12<5<13<6<10<5<6<6<19<154.571.7926-Sep-17<12<8<18<9<24<11<17<8<9<11<33<13<2093.351.9231-Oct-17<7<6<11<6<12<5<11<6<5<6<21<12<3.8328-Nov-17<9<10<20<10<25<12<16<8<9<12<39<6<3.8026-Dec-17<11<12<20<11<22<10<19<9<10<11<34<12<3653.351.8131-Jan-17<7<7<11<7<14<7<13<8<7<8<26<133.441.3828-Feb-17<9<8<17<7<20<9<15<8<7<8<26<132.871.3327-Mar-17<7<8<13<7<16<8<13<7<7<6<22<12<324<1.4126-Apr-17<12<12<27<11<21<14<19<17<12<11<50<200<2.13230-May-17<11<11<19<10<27<11<17<11<10<12<36<142.941.36 LOCAL27-Jun-17<10<10<15<11<23<10<17<7<9<13<30<15<327<2.89RESIDENCE25-Jul-17<0.9<0.9<2<1<2<0.9<1<2<0.7<1<5<150<2.103 and 4(Site #49) *29-Aug-17<9<10<20<9<20<9<15<9<10<11<34<123.301.7226-Sep-17<7<5<13<7<14<8<11<6<5<7<22<14<194<2.9831-Oct-17<9<10<15<10<22<10<18<8<7<9<29<14<3.7628-Nov-17<8<8<16<11<21<12<17<9<8<11<33<14<3.7526-Dec-17<6<6<13<5<12<6<11<5<5<6<17<11<365<2.79Note 2: CR 17-10476 LLD for I-131 and La-140 not met due to error in sample collection date input into analysis softwareNote 4: CR 18-00109 LLD for La-140 not met due to extensive time between sample acquisition and analysisNote 3: Long count time to achieve LLDs resulted in lower than typical MDAs on most nuclides. Long count time due to extensive time between sample acquisition and analysis timeODCM required samples denoted by *units are pCi/literDRINKING WATER Table 8-9 Groundwater SAMPLEDATE<15<15<30<15<30<15<30<15<15<18<60<15<2000LOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNotes1-Feb-17WELL 27ddc25-Apr-17<13<11<19<12<28<14<23<11<11<13<37<8<322(Site #57)*25-Jul-17<7<7<13<8<14<8<12<7<5<7<22<15<36326-Sep-17<13<10<23<12<26<14<18<10<12<11<35<12<34119-Dec-17<9<8<16<8<18<8<15<7<7<10<27<13<3641-Feb-17 <10<9<18<8<20<12<16<9<8<7<34<15<335WELL 34abb25-Apr-17 1(Site #58)*27-Jun-17<13<11<20<13<26<13<23<12<10<13<38<13<32825-Jul-17<7<7<16<7<17<8<12<7<6<8<24<14<36926-Sep-17<13<14<22<11<27<14<20<11<12<12<38<15<34119-Dec-17<11<9<17<10<22<13<19<9<11<12<34<14<370 27-Jun-17<14<11<23<12<26<13<19<9<12<13<37<13<328 125-Jul-17<9<11<19<12<21<13<18<11<8<11<34<13<37019-Dec-17<8<8<12<8<16<8<14<7<7<7<25<12<368GROUNDWATER ODCM required samples denoted by *units are pCi/literNote 1: On Site deep wells under construction. Site 58 was out of service during sampling period. Supplemental sampling occurred in June for Site 58 and new deep well under construction**Out of Service****Out of Service**Well 34aab**Not in Service**

Table 8-10 Surface Water SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNotes1-Feb-17<11<10<13<10<16<10<18139<9<11<31<11<33525-Apr-17<10<11<21<10<23<10<16<9<10<11<26<13<32325-Jul-17<10<10<23<13<26<11<20<13<9<14<42<14<37126-Sep-17<10<8<18<11<17<9<16<13<8<7<24<11<34419-Dec-17<8<8<15<8<17<8<16<9<8<9<24<14<3621-Feb-17<12<10<14<8<23<10<19<15<9<12<33<15<33425-Apr-17<10<10<16<9<23<12<19<10<9<13<35<13<32325-Jul-17<8<9<23<10<24<10<18<14<10<13<30<14<37126-Sep-17<10<10<19<11<17<10<16<10<10<9<31<13<34119-Dec-17<9<10<16<9<23<11<18 88<10<12<30<11<3631-Feb-17<6<6<15<7<14<7<1085<6<7<20<101342 22325-Apr-17<11<12<22<14<29<12<21<12<13<11<40<141680 22025-Jul-17<10<8<11<10>19<11<14<12<8<11<33<131212 21926-Sep-17<13<9<26<13<25<10<21<9<12<13<33<131263 20019-Dec-171-Feb-1725-Apr-1725-Jul-1719-Dec-17<10<10<17<10<19<13<19<12<9<12<30<9402 2181-Feb-1725-Apr-17<12<10<29<11<26<12<19<9<7<12<34<9<320 125-Jul-17<5<5<11<6<13<5<10<6<6<6<21<151363 22019-Dec-171-Feb-17<9<8<19<10<20<7<15<7<5<6<30<131168 22025-Apr-1725-Jul-1726-Sep-17<10<10<21<11<30<10<19<10<10<9<35<7505 20019-Dec-17<11<11<27<12<24<11<17<10<8<8<28<9673 2111-Feb-1725-Apr-1725-Jul-1719-Dec-17<10<10<23<10<24<11<19<9<8<11<34<9 720 215 21-Feb-1725-Apr-1725-Jul-1719-Dec-17<10<11<24<11<29<11<17<7<9<12<27<7505 2101-Feb-1725-Apr-17<13<9<27<15<24<12<21<10<10<14<32<8464 19825-Jul-17<11<9<24<14<23<10<19<8<10<14<28<11577 20619-Dec-17ODCM required samples denoted by *units are pCi/literNote 2: Tritium sample duplicated and averaged.CELL 3BCELL 1BCELL 1CCELL 2BEVAP POND 3 (Site #64)

  • CELL 3AEVAP POND 1 (Site #59)
  • CELL 1AEVAP POND 2 (Site #63)
  • CELL 2A85 ACRE RESERVOIR (Site #60)
  • 45 ACRE RESERVOIR (Site #61)
  • Note 1: H-3 results abnormally low. Sample unavailable for reanalysis. Similar results found in subsequent sample led to discovery of reporting error. Results considered INVALID. CR 18-00638**No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample****No Influent Since Last Sample**

Table 8-10 Surface Water (Continued)

SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium Notes3-Jan-17<8<7<19<9<18<10<15179<7<7<29<1410-Jan-17<10<10<21<8<23<11<2186<9<11<32<1017-Jan-17<7<7<16<9<17<6<12189<6<7<23<724-Jan-17<15<22<19<23<39<21<323022<22<26<84<12 331-Jan-17<10<7<14<8<24<10<15<11<5<9<24<9<3507-Feb-17<11<11<22<10<18<10<18176<10<10<32<1314-Feb-17<6<6<11<6<13<6<10218<5<7<23<1321-Feb-17<11<9<18<8<22<11<16139<8<7<27<1428-Feb-17<12<9<20<12<24<12<20<12<9<12<33<15<3577-Mar-17<4<5<10<6<10<6<10267<5<5<18<1014-Mar-17<13<13<44<17<48<21<22<32<16<22<79<32 421-Mar-17<9<8<21<10<21<9<173311<8<10<28<728-Mar-17<10<8<16<8<20<8<15249<7<8<29<12<337WRF4-Apr-17<13<13<20<12<29<12<224012<10<13<36<11 INFLUENT11-Apr-17<11<11<20<11<23<10<15179<10<12<32<618-Apr-1725-Apr-17<8<7<14<10<21<7<13118<7<7<26<11<3422-May-17<11<10<20<10<25<13<21169<12<10<36<149-May-17<9<11<14<11<20<11<17 2410<9<11<30<1216-May-17<8<9<15<8<16<8<141810<8<8<29<1023-May-17<8<9<14<7<23<6<12159<7<7<27<14<34230-May-17<11<10<15<10<22<10<16188<9<11<31<10<3496-Jun-17<10<10<19<10<27<9<15<12<10<10

<37<1513-Jun-17<10<10<20<9<17<8<15<10<10<9<31<1220-Jun-17<9<11<18<7<14<11<17<10<9<10<27<13 27-Jun-17<9<9<13<7<25<10<16<11<7<8<28<12<3413-Jul-17<10<11<17<8<21<10<16<10<7<9<25<811-Jul-17<9<11<18<9<21<11<1898<8<10<30<1518-Jul-17<11<11<16<11<14<11<18<12<8<10<29<10Note 4: Several LLDs not achieved due to delay in sample analysis. CR 17-04054SURFACE WATERODCM required samples denoted by *units are pCi/literWRF OUTAGE- No SampleNote 3: Several LLDs not achieved due to incorrect volume entered into analysis system. CR 17-17823 Table 8-10 Surface Water (Continued)

SAMPLEDATE<15<15<30<15<30<15<30<15<15<18<60<15<3000LOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote25-Jul-17<11<9<17<9<21<9<14 1810<7<9<31<12<3721-Aug-17<10<11<18<10<17<8<15<10<9<10<33<88-Aug-17<9<8<13<7<20<9<15<13<9<7<31<1015-Aug-17<10<9<20<10<15<11<15 159<8<9<30<1522-Aug-17<12<10<18<12<24<10<1898<8<10<24<1329-Aug-17<11<11<20<11<24<12<19<12<10<12<28<9<3545-Sep-17<10<8<18<7<22<10<17<12<7<9<29<1012-Sep-17<10<10<20<7<22<10<13 3611<9<9<25<1219-Sep-17<11<12<21<9<24<9<19<13<8<9<30<1226-Sep-17<8<7<13<10<21<8<152010<7<8<28<10<3503-Oct-17<10<9<17<11<23<12<15138<7<7<29<1410-Oct-17WRF17-Oct-17 INFLUENT24-Oct-17<11<11<22<9<25<14<21 12<11<12<36<931-Oct-17<9<11<21<10<26<8<16149<8<9<33<12<3597-Nov-17<6<6<11<6<11<6<10116<5<6<18<1514-Nov-17<8<11<15<10<24<9<16<199<9<7<31<1221-Nov-17<11<11<18<8<20<9<214512<12<10<35<828-Nov-17<10<9<24<11<17<11<18<13<9<11<31<14<3505-Dec-17<12<8<18<8<22<9<16147<8<9<24<1012-Dec-17<9<5<14<8<15<7<15119<6<7<29<919-Dec-17<7<8<24<14<23<10<1599<7<7<29<1426-Dec-17<9<10<18<9<19<9<17<11<7<7<33<10<380WRF OUTAGE- No SampleSURFACE WATERODCM required samples denoted by *units are pCi/literWRF OUTAGE- No Sample Table 8-10 Surface Water (Continued)

SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote3-Jan-17<11<9<19<9<21<10<17<9<8<10

<31<15<35010-Jan-1717-Jan-17 24-Jan-17<20<20<33<5<32<16<42<20<16<23<69<20<356 331-Jan-177-Feb-1714-Feb-1721-Feb-17<11<11<19<9<28<11<16<10<9<10<40<14595 21828-Feb-17<9<10<17<7<28<11<17<8<9<11<38<13<3527-Mar-1714-Mar-17 21-Mar-17 28-Mar-174-Apr-1711-Apr-1718-Apr-17 25-Apr-172-May-179-May-1716-May-1723-May-17 30-May-176-Jun-1713-Jun-1720-Jun-17 27-Jun-17SURFACE WATEREMPTY- No SampleEMPTY- No SampleEMPTY- No SampleODCM re quired sam ples denoted b y *units are pCi/literNote 3: Several LLDs not achieved due to incorrect volume entered into analysis system. CR 17-17823EMPTY- No SampleEMPTY- No Sample EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleSEDIMENTATION BASIN #2EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No Sample Table 8-10 Surface Water (Continued) SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140TritiumNote3-Jul-1711-Jul-1718-Jul-1725-Jul-17<6<6<12<5<13<5<11<6<6<6<20<14<3301-Aug-17 8-Aug-1715-Aug-1722-Aug-17<14<11<27<12<29<13<24<10<10<10<9<34929-Aug-175-Sep-1712-Sep-1719-Sep-17 26-Sep-173-Oct-1710-Oct-1717-Oct-1724-Oct-17 31-Oct-177-Nov-1714-Nov-1721-Nov-17 28-Nov-175-Dec-1712-Dec-1719-Dec-1726-Dec-17units are pCi/literODCM required samples denoted by *EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleSEDIMENTATION BASIN #2EMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No SampleEMPTY- No Sample Table 8-11 Sludge/Sediment SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-111Notes3-Jan-17<68<10610-Jan-17 482163<118<16817-Jan-17 291156<80<11424-Jan-17 192138<40<13531-Jan-17<137<1687-Feb-17 788229<148<15514-Feb-17 695184<107<118 21-Feb-17 200133<127<17828-Feb-17 277163<61<1437-Mar-17<94<14114-Mar-17 469152<109<9321-Mar-17<102<17128-Mar-17 632165<117<1024-Apr-17 33191<51<8111-Apr-17 562186<128<18018-Apr-1725-Apr-17<116<1022-May-17<100<1119-May-17 724169<109<16216-May-17 891195<109<12323-May-17 919186<106<14630-May-17 467151<137<1206-Jun-17 959215<145<14813-Jun-17 654201<140<15920-Jun-17 679176<90<14427-Jun-17 348131<90<158SLUDGE/SEDIMENTWR OUTAGEWR CENTRIFUGE WASTE SLUDGEODCM required samples denoted by *units are pCi/kg, wet Table 8-11 Sludge/Sediment (Continued) SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-111Notes3-Jul-17 351147<146<16211-Jul-17 487151<35<3018-Jul-17 359144<126<14325-Jul-17 35344<23<231-Aug-17 498 191<146<1438-Aug-17 323137<106<16315-Aug-17<108<15522-Aug-17 314128<113<16929-Aug-17 364162<129<3215-Sep-17 415177<143<5112-Sep-17 481162<32<17819-Sep-17 264143<143<17726-Sep-17 427143<109<3053-Oct-17 510164<147<15510-Oct-17 423161<115<4217-Oct-1724-Oct-17 510138<81<8031-Oct-17 481141<65<307-Nov-17 375139<74<16214-Nov-17 646161<94<8221-Nov-17 523161<93<17728-Nov-17 302122<122<1165-Dec-17 363139<146<14512-Dec-17<125<15119-Dec-17 299169<139<11926-Dec-17 215120<146<169WR OUTAGEWR CENTRIFUGE WASTE SLUDGEODCM required samples denoted by *units are pCi/kg, wet Table 8-11 Sludge/Sediment (Continued) Cooling Tower Sludge Unit Cycle Approximate Volume (yd 3) Isotope Activity Range (pCi/g) Sample Type U2R20 302 All principal gamma-emitters <MDA Towers/Canal Sludge U1R20 512 All principal gamma-emitters <MDA Towers/Canal Sludge Table 8-12 Hard -To-Detect Radionuclide Results Hard-To-Detect Radionuclide (pCi/Liter) Sample Location Well number Sample Date C-14 Fe-55 Ni-63 Sr-90 Unit 1 (outside RCA) APP-12 11/9/2017 <66.7 <18.3 <2.39 <1.58 Unit 2 (inside RCA) H0A 11/3/2017 <67.1 <21.5 <2.68 <1.06 Unit 3 (inside RCA) H11 10/24/2017 <67.9 <19.9 <3.19 <1.03

9. Thermoluminescent Dosimeter (TLD) Results and Data The environmental TLD used at PVNGS is the Panasonic Model 812 Dosimeter. The Model 812 is a multi-element dosimeter combining two elements of lithium borate and two elements of calcium sulfate under various filters.

TLDs were placed in fifty locations from one to thirty-five miles from the PVNGS. TLD locations are shown in Figure 2-1 and Figure 2-2 and are described in Table 9-1. TLD results for 2017 are presented in Table 9-2. Definitions for Table 9-2 are as follows:

MDD Q: Minimum differential dose, quarterly, 3 times 90 th percentile sQ determined from analysis (mRem). MDD A: Minimum differential dose, annual, 3 times 90th percentile sA determined from analysis (mRem). B Q: Quarterly baseline (mRem) (average of previous 5 years)

M Q: Locations 91 day standard quarter normalized dose (mRem per standard quarter)

L Q: Quarterly investigation level dose (mRem)

B A: Baseline background dose (mRem) (annual)

M A: Annual monitoring data - MA determined by normalizing available quarterly data to 4 full quarters L A: Annual investigation level dose (mRem) ND: Non Detectable The baseline is calculated as the average of the previous 5 year measurements. The minimum differential dose (MDD) is calculated as 3times the 90 th percentile standard deviation of the data from the previous 5 years; quarterly MDD is calculated using the quarterly data and annual MDD is calculated using the annual summation of the quarterly data. Investigation level is calculated by the difference of the data measurement and the baseline; results less than, or equal to the MDD are Non Detectable (ND) and any result exceeding the MDD meets the threshold for the investigation level.

Locations exceeding the investigation level will be evaluated for cause and impact to the public and environment.

Historical environmental gamma radiation results for 1985 through 2017 are presented in graphical form on Figure 9-1 (excluding transit control TLD #45). Figure 9-2 depicts the environmental TLD results from 2017 as compared to the pre-operational TLD results (excluding sites #41 and #43, as they were deleted and later assigned to a new location, and #46-50, as they had no pre-op TLD at the location for comparison). The site to site comparisons indicate a direct correlation with respect to pre-operational results. It is indicated that the offsite dose, as measured by TLDs, has not changed since Palo Verde became operational.

Table 9-2 Environmental TLD Results B Q M QQ1M QQ2M QQ3M QQ4L QQ1L QQ2L QQ3L QQ4B A M A L A125.125.925.125.825.5NDNDNDND100.4102.3ND222.523.222.422.421.4NDNDNDND89.989.4ND324.325.124.723.223.3NDNDNDND97.296.3ND424.826.923.625.524.4NDNDNDND99.3100.5ND522.220.419.620.119.6NDNDNDND89.079.8ND627.028.328.027.8-NDNDND-107.884.0ND725.826.526.625.226.8NDNDNDND103.3105.1ND824.124.824.924.624.6NDNDNDND96.598.9ND928.629.227.928.628.9NDNDNDND114.5114.5ND1024.225.224.524.723.6NDNDNDND96.697.9ND1125.325.424.924.826.3NDNDNDND101.3101.4ND 1223.723.224.624.024.1NDNDNDND94.895.9ND1326.026.225.726.025.5NDNDNDND104.1103.5ND1425.325.425.725.725.0NDNDNDND101.3101.8ND1523.924.223.723.324.5NDNDNDND95.695.7ND1622.723.723.423.523.2NDNDNDND91.093.8ND1725.026.125.524.525.0NDNDNDND100.2101.1ND1823.724.423.222.623.4NDNDNDND94.793.6ND1925.826.024.924.925.3NDNDNDND103.4101.1ND 2024.625.525.024.424.8NDNDNDND98.599.6ND2126.126.027.726.025.3NDNDNDND104.3105.0ND2226.526.925.525.926.3NDNDNDND106.1104.7ND2323.623.824.023.022.9NDNDNDND94.393.7ND2423.123.922.422.022.7NDNDNDND92.391.1ND2523.824.423.123.823.5NDNDNDND95.194.8ND2627.928.528.328.828.0NDNDNDND111.6113.6ND2727.328.228.727.426.7NDNDNDND109.0111.0ND 2826.227.826.725.725.2NDNDNDND104.7105.4ND2924.724.824.125.125.2NDNDNDND98.699.2ND3026.126.726.926.026.3NDNDNDND104.5106.0ND 3123.724.323.823.123.5NDNDNDND94.694.6ND3225.925.426.025.925.4NDNDNDND103.5102.8ND3326.326.226.326.325.7NDNDNDND105.3104.4ND3428.129.028.527.528.3NDNDNDND112.5113.4ND3531.432.533.930.930.8NDNDNDND125.6128.2ND3626.626.627.625.625.4NDNDNDND106.3105.1ND3724.325.324.423.623.7NDNDNDND97.296.9ND3827.828.927.028.028.4NDNDNDND111.1112.2ND3924.725.824.824.023.7NDNDNDND98.698.2ND4025.426.125.025.624.6NDNDNDND101.5101.4ND 4126.927.426.727.826.0NDNDNDND107.7107.9ND4227.829.027.627.426.5NDNDNDND111.2110.5ND4327.929.028.628.827.0NDNDNDND111.5113.4ND4423.824.425.223.723.6NDNDNDND95.396.9ND455.96.25.95.95.3NDNDNDND23.523.3ND 4624.424.524.424.524.3NDNDNDND97.597.8ND4724.224.124.724.023.3NDNDNDND96.796.1ND4824.725.424.124.523.6NDNDNDND98.797.6ND4923.123.223.223.322.0NDNDNDND92.491.8ND5019.920.419.219.619.6NDNDNDND79.778.9NDQuarterly (mrem)SiteAnnual (mrem)Palo Verde 2017 MDD Q: 5 mrem Palo Verde 2017 MDDA: 10 mrem

10. Land Use Census 10.1 Introduction In accordance with the PVNGS ODCM, Section 6.2, the field portion of the annual Land Use Census was performed by June 2017. Observations were made in each of the 16 meteorological sectors to determine the nearest milking animals, residences, and gardens of greater than 500 square feet. This census was completed by driving the roads and speaking with residents. The results of the Land Use Census are presented in Table 10-1 and discussed below. The directions and distances listed are in sectors and miles from the Unit 2 containment.

10.2 Census Results The 2017 Land Use Census results have identified a new potential Radiological Effluent Release Report dose receptor location. Condition Report 18-04530 was generated to document the changes identified since the 2016 Land Use Census. Each location was evaluated. Below describes the changes identified and the evaluation results. Nearest Resident There was one (1) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.590 mrem. Milk Animal There were three (3) changes in milk animal status from the previous year. The locations were visited by the REMP manager to evaluate program particip ation potential. As of December 2017, none of the locations had goats. Dose calculations indicated the highest dose to be 0.660 mrem. Vegetable Gardens There were three (3) changes in nearest garden status from the previous year. One garden had a calculated dose lower than gardens currently in REMP. One garden location was removed due to absence of garden. One garden was evaluated and found to not currently meet the ODCM required size of 500 square feet, nor growing broadleaf vegetation; however, this location is being monitored for possible future inclusion in REMP. Dose calculations indicated the highest dose to be 0.590 mrem. See Table 10-1 for a summary of the specific results and Table 2-1 for current sample locations. Figure 10-1through Figure 10-3 provide graphs depicting historical calculated doses for nearest residents, nearest milk receptor, and nearest garden receptor locations in each sector. Differences in calculated doses are the result of many variables, including; Changes in receptor locations from year to year (proximity to the power plant)

Changes in local meteorology (wind direction, wind speed, precipitation, and temperature) Concurrent meteorology at the time of effluent releases Exposure pathways Table 10-1 Land Use Census (Distance and direction are relative to Unit 2 in miles) Sector Nearest Resident Nearest Garden Nearest Milk Animal (Cow/Goat) Calculated Dose (mrem) Change from 2016 N 1.55 1.71 1.94 Resident Garden Milk 5.50E-2 2.77E-1 2.49E-1 Garden Milk NNE 1.52 NONE 3.05 Resident Milk 7.87E-2 2.86E-1 Garden NE 2.16 2.16 4.40 Resident Garden Milk 5.90E-1 5.90E-1 2.53E-1 Garden Milk ENE 2.05 4.84 4.84 Resident Garden Milk 1.03E-1 1.85E-1 1.85E-1 E 2.81 NONE NONE Resident 7.68E-2 ESE 1.95 NONE NONE Resident 1.85E-1 SE 3.40 NONE 3.99 Resident Milk 1.22E-1 6.60E-1 Resident Milk SSE NONE NONE NONE NA S NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.37E-1 WSW 0.75 NONE NONE Resident 1.43E-1 W 0.70 NONE NONE Resident 8.48E-2 WNW NONE NONE NONE NA NW 0.93 NONE NONE Resident 7.02E-2 NNW 1.30 4.34 NONE Resident Garden 6.93E-2 8.03E-2 Comments: Dose calculations were performed using GASPAR code and 2016 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual critical organ dose identified.

11. Summary and Conclusions Summary The conclusions are based on a review of the radioassay results and environmental gamma radiation measurements for the 2017 calendar year. Where possible, the data were compared to pre-operational sample data. All sample results for 2017 are presented in Table 8-1 through Table 8-12 and do not include observations of naturally occurring radionuclides, with the exception of gross beta in air and gross beta in drinking water. Table 11-1 summarizes the ODCM required samples and is in the format required by the NRC BTP on Environmental Monitoring.

I-131 identified in the evaporation ponds, Water Resources influent, Water Resources centrifuge sludge, and reservoirs is the result of offsite sources and appears in the effluent sewage from Phoenix. The levels of I-131 detected in these locations are consistent with levels identified in previous years. Tritium concentrations identified in surface water onsite have been attributed to PVNGS permitted gaseous effluent releases and secondary plant releases. These concentrations are consistent with historical values.

Environmental radiation levels are consistent with measurements reported in previous Pre-operational and Operational Radiological Environmental annual reports, References 1 and 2.

Conclusion There was no measurable radiological impact on the environment in 2017 resulting from the operation of PVNGS.

Table 11-1 Environmental Radiological Monitoring Program Annual Summary TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530 Maricopa County, Arizona Calendar Year 2017 Medium or Pathway Sampled (Unit of Measurement) Type and Total Number of Analyses Performed Lower Limit of Detection (LLD) (from Table 6.1) All Indicator Locations Mean (f)a Range Location with Highest Annual Mean

Name Mean (f) a Distance and Range Direction Control Locations

Mean (f)a Range Number of Nonroutine Reported Measurements Direct Radiation (mrem/std. qtr.) TLD - 199 NA 25.3 (187/188) Site #35 32.1 (4/4) 25.8(8/8) 1 19.2 - 33.9 8 miles 330° 30.8 - 33.9 23.6 - 28.3 Air Particulates (pCi/m 3) Gross Beta - 519 0.01 0.031 (467/468) Site # 4 0.033 (52/52) 0.031 (49/52) 5 0.014 - 0.057 16 miles 92º 0.016 - 0.053 0.017 - 0.053 Gamma Spec Composite - 40 Cs-134 (quarterly) 0.05 <LLD NA <LLD <LLD 0 <LLD NA <LLD <LLD Cs-137 (quarterly) 0.06 <LLD NA <LLD <LLD 0 <LLD NA <LLD <LLD Air Radioiodine (pCi/m 3) Gamma Spec. - 519 I-131 0.07 <LLD NA <LLD <LLD 5 <LLD NA <LLD <LLD Broadleaf Vegetation (pCi/Kg-wet) Gamma Spec. - 23 I-131 60 <LLD NA <LLD <LLD 0 Cs-134 60 <LLD NA <LLD <LLD 0 Cs-137 80 <LLD NA <LLD <LLD 0

Groundwater (pCi/liter) H 12 2000 <LLD NA <LLD NA 0 Gamma Spec. -

8 Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 I-131 15 <LLD NA <LLD NA 0 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 Gross Beta - 48 4 4.23 (31/48) Site #48 5.12 (9/12) NA 0 2.27 - 6.84 1 mile 236

° 3.87 -6.26 H 16 2000 <LLD NA <LLD NA 0 Gamma Spec. - 48 Drinking Water (pCi/liter) Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 I-131 15 <LLD NA <LLD NA 3 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 5

Gamma Spec. - 27 Milk I-131 1 <LLD NA <LLD <LLD 1 (pCi/liter) <LLD NA <LLD <LLD Cs-134 15 <LLD NA <LLD <LLD 0 <LLD NA <LLD <LLD Cs-137 18 <LLD NA <LLD <LLD 0 <LLD NA <LLD <LLD Ba-140 60 <LLD NA <LLD <LLD 0 La-140 15 <LLD NA <LLD <LLD 0 Gamma Spec. - 24 Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 Surface Water (pCi/liter) I-131 15 10 (3/36) Site #61 13 (1/4) NA 0 8-13 Onsite 67° 13-13 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 H 25 3000 913 (13/36) Site #59 1374 (4/4) NA 1 402 - 1680 Onsite 180° 1212-1680 (a) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) NOTE: Miscellaneous samples that are not listed on Tables 2.1 and 9.1 (not ODCM required) are not included on this table.

12. References
1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985
2. 1985-2016 Annual Radiological Environmental Operating Reports, Palo Verde Nuclear Generating Station
3. Palo Verde Nuclear Generating Station Technical Specifications and Technical Reference Manual 4. Offsite Dose Calculation Manual, Revision 27, PVNGS Units 1, 2, and 3
5. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants
6. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants
7. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG-1301)
8. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007
9. "Sources of Radiation." NRC: Sources of Radiation. Nuclear Regulatory Commission, 2 Oct. 2017. Web. 21 Feb. 2018.
10. "NCRP Report No. 160: Ionizing Radiation Exposure of the Population of the United States." Journal of Radiological Pr otection J. Radiol. Prot. 29.3 (2009): 465. Web.
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