ML16124B099

Palo Verde, Units 1, 2, and 3 - Annual Radiological Environmental Operating Report 2015

ML16124B099
Person / Time
Site:	Palo Verde
Issue date:	04/29/2016
From:	Weber T N Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-07241-TNW/MDD/TMJ
Download: ML16124B099 (80)

Text

Technical Specification 5.6.2 5.6.2A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Diablo Canyon Palo Verde Wolf Creek Palo Verde Nuclear Generating Station PO Box 52034 Phoenix, Arizona 85072-2034 Mail Station 7636 102-07241-TNW/MDD/TMJ April 29, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Annual Radiological Environmental Operating Report 2015 In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2015. No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Michael DiLorenzo, Licensing Section Leader, at (623) 393-3495. Sincerely, Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/TMJ/akf

Enclosure:

Annual Radiological Environmental Operating Report 2015 cc: M. L. Dapas NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. M. Watford NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS A. V. Godwin Arizona Radiation Regulatory Agency (ARRA) T. Morales Arizona Radiation Regulatory Agency (ARRA)

ENCLOSURE Palo Verde Nuclear Generating Station UNITS 1, 2, and 3 Annual Radiological Environmental Operating Report 2015

1. Introduction ............................................................................................................................. 2 Overview ..................................................................................................................................... 2 Radiation and Radioactivity ........................................................................................................ 3 2. Description of the Monitoring Program .................................................................................. 5 2.1 Radiological Environmental Monitoring Program ............................................................... 5 2.2 Radiological Environmental Monitoring Program Changes for 2015 .................................. 5 2.3 REMP Deviations/Abnormal Events Summary .................................................................... 6 2.4 Ground Water Protection ...................................................................................................... 7 3. Sample Collection Program .................................................................................................. 14 3.1 Water ................................................................................................................................... 14 3.2 Vegetation ........................................................................................................................... 14 3.3 Milk ..................................................................................................................................... 14 3.4 Air ....................................................................................................................................... 14 3.5 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 4.3 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 ................................................................................... 17 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 Ground Water ...................................................................................................................... 29 8.7 Surface Water ...................................................................................................................... 29 8.8 Sludge and Sediment ........................................................................................................... 30 8.8.1 WRF 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 ..................................................... 58 10. Land Use Census ................................................................................................................ 64 10.1. Introduction ................................................................................................................ 64 10.2. Census Results ............................................................................................................ 64 11. Summary and Conclusions ................................................................................................ 69 12. References .......................................................................................................................... 73 LIST OF TABLES Table 2-1 Sample Collection Locations .......................................................................................... 8 Table 2-2 Sample Collection Schedule ........................................................................................... 9 Table 2-3 Summaries of the REMP Deviations/Abnormal Events .............................................. 10 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 ......................................................................................................... 47 Table 8-12 Hard -To-Detect Radionuclide Results ...................................................................... 49 Table 9-1 TLD Site Locations ...................................................................................................... 59 Table 9-2 Environmental TLD Results ......................................................................................... 61 Table 10-1 Land Use Census ........................................................................................................ 65 Table 11-1 Environmental Radiological Monitoring Program Annual Summary ........................ 70 TABLE OF FIGURES Figure 1-1 Sources of Radiation Exposure in the United States ..................................................... 4 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 ........................................................................... 50 Figure 8-2 Gross Beta in Air, 3rd - 4th Quarter ............................................................................ 51 Figure 8-3 Historical Gross Beta in Air (Weekly System Average) ............................................ 52 Figure 8-4 Historical Gross Beta in Air (Annual Site to Site Comparisons) Compared to Pre-Op....................................................................................................................................................... 53 Figure 8-5 Gross Beta in Drinking Water ..................................................................................... 54 Figure 8-6 Evaporation Pond Tritium Activity (Pre-Op- 2008) ................................................... 55 Figure 8-7 Evaporation Pond Tritium Activity (2009-2015) ........................................................ 56 Figure 8-8 Sedimentation Basin 2 Cs-137 .................................................................................... 57 Figure 9-1 Network Environmental TLD Exposure Rates ........................................................... 62 Figure 9-2 Environmental TLD Comparison- Pre-Operational VS 2015 ..................................... 63 Figure 10-1 Historical Comparison of Nearest Resident Dose ..................................................... 66 Figure 10-2 Historical Comparison of Nearest Milk Animal Dose .............................................. 67 Figure 10-3 Historical Comparison of Nearest Garden Dose ....................................................... 68

ABSTRACT 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 2015, the following categories of samples were collected by APS:

• Broad leaf vegetation

• Groundwater

• Drinking water

• Surface water

• Airborne particulate and radioiodine

• Goat milk

• Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmental gamma radiation. The Environmental TLD program is also conducted by APS. The Arizona Radiation Regulatory Agency (ARRA) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by ARRA include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) deep wells. Offsite samples analyzed by ARRA include two (2) local resident wells. ARRA 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 2015. All references are specifically identified in Section 12. Overview The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of members of the public resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the 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 (e.g., 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 Section IV.B.2 of Appendix I to 10 CFR Part 50. 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 "Manmade" 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: occupations, 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 mrem. 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. The most significant contributor to radiation exposure from manmade sources is medical procedures. Diagnostic s-rays and nuclear medicine procedures, such as those that use iodine-131 or cesium-137, are examples of manmade 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 perform ionizing radiation dosimeter analyses. 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 2015 New Vegetation Sample Location The 2015 Land Use Census results have identified a new Radiological Environmental Monitoring Program (REMP) garden sample location. Per the Land Use Census procedure, 74RM-0EN07 Revision 14, a Condition Report shall be generated if a new sample location is identified that yields a 20% greater dose to an indicator location than current indicator locations. The new vegetation indicator location's calculated dose is 2.05E-01 mRem versus a criterion of 1.99E-01 mRem. This sampling location was included as supplemental data for 2015 and is included in the 2015 AREOR. This sampling location will be included in the REMP, beginning in 2016, as a required location as annotated in the ODCM, Revision 27.

Configuration of Air Sample Stations The PVNGS Annual Radiological Environmental Operating Report 2013, section 2.3 REMP Deviation/Abnormal Events Summary references Letter 218-03709-JLM and describes the lowering of Radiological Environmental Monitoring Program (REMP) air samples. An evaluation concludes the air sample locations should not be lowered due to measurement variation concerns (CRDR 3805133). In April 2013, CRDR 4385407 was generated to lower the air sample locations based on industrial safety issues. This modification was evaluated, determining the sampling height should be restored to ensure representative monitoring of effluents and the impact on the environment, as well as maintain historical sample continuity (CRDR 4567692).

The configurations of all the air sample monitoring stations were restored to meet the intent of NUREG 1301 and Radiological Assessment Branch Technical Position, Revision 1. Consideration should be given to incorporation of EPA Guidance For Network Design and Optimum Site Exposure For PM2.5 And PM10 and ASTM document Standard Guide for Choosing Locations and sampling Methods to Monitor Atmospheric Deposition at Non-Urban Locations (CRAI 4577972). Changing the configuration to meet these requirements led to placing the air sample collection point to outside of the instrument weather housing, by utilizing a gooseneck sample line extension. This allowed sampling at the pre-operational sample height. The restoration of the sampling height configuration was completed with objective evidence on 2/19/2015. 2.3 REMP Deviations/Abnormal Events Summary During calendar year 2015, there were eleven (11) deviations/abnormal events with regards to the monitoring program. Refer to Table 2-3 for more detail and any corrective actions taken. Seven (7) of the events involved air sample stations. Three (3) events were due to defective pump vanes which were discovered due to the failure of pumps following routine maintenance in which the pump vanes had been replaced. The defective vanes remaining in inventory were identified and pulled from the supply and replaced. One (1) of the events involved the validity of several samples being questioned due to water intrusion occurring following the placement of the sample heads outside of the housing. An evaluation conducted in conjunction with the vendor concluded that the samples were valid. To avoid unnecessary wear on the sampling equipment and to ensure public confidence in the air sampling portion of the program, the rain shields were upgraded. No other water intrusion events have happened since the rain shield upgrades. The final three (3) air sample events involved a disconnected suction tube at Site 35, dislodged sample cartage at Site 35, and a loss of power at Site 17A. All events have been evaluated and corrective measures have been taken when necessary to prevent recurrence. One (1) event was a missed LLD for La-150 for Site 49 drinking water. The missed LLD was attributed to a software malfunction. There was no detectable activity in this sample and the LLD that was achieved was well below the action level.

One (1) event was exceedance of the quarterly I-131 reporting level of 20 pCi/L. This occurred at Evaporation Pond 1C, fourth calendar quarter. The source is radiopharmaceutical I-131 that originates in the Phoenix sewage effluent that supplies makeup to the Reservoirs and Circulating Water system. This water is wasted to the Evaporation Ponds. This is not a plant effluent.

The final two (2) events involved environmental TLD locations, Site 10 and Site 49. Site 10 sampling stanchion was discovered to be missing; however, the TLD and housing were left, undamaged. Site 49 sampling stanchion was temporarily moved, approximately 20 feet, to avoid TLD damage or missing data during road construction in the area.

2.4 Ground Water 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 radiological 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 Arlington School 14A Air NNE2 371stAve. 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 ground water ONSITE Well 27ddc 58 ground water 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 #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 # AIR PARTICULATE MILK AIRBORNE RADIOIODINE VEGETATIONGROUNDWATER 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/AA63 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 17A sample pump lost power between 2/10/2015-2/17/2015. The air sample pump lost power during the sample period, resulting in the inability to determine the actual sample volume. Results for this sampling period found to be INVALID. Power restored and sample volume for the following sample period was VALID. Event documented through CR 16-04887 (Table 8-1 and Table 8-4 , Note 1) 2. Air Samples stations had water intrusion 2/24/2015-3/3/2015, 3/16/2015-3/23/2015, and 4/28/2015-5/5/2015. Air sample cartridges were found to have water intrusion following heavy rain, causing the technician to question the sample integrity. These events were documented through CR 15-00990 and 15-01374. An evaluation was completed to determine the ability of the sample cartridge to maintain efficiency under the documented conditions. Vendor verified that the efficiency test data representing the F&J long term scenario is applicable to the facts and circumstances which occurred in these events (EVAL 15-00990-001). Data is considered VALID and is included in this report (Table 8-1 and Table 8-4, Note 2) 3. Air Sample Site 35 cartridge found on ground 8/11/2015 Sample for Site 35 found dislodged from pump and lying on ground- sample determined to be INVALID for sample period 8/4/2015-8/11/2015. Event documented through CR 15-05977 (Table 8-2 and Table 8-5, Note 1). 4. Air Sample Site 35 found with suction tube disconnected on 10/28/2015. On 10/28/2015, technician found REMP Air Sample Site 35 with the suction tube disconnected. Filter appeared white/as new. Technician believed that the suction tube came loose during the previous sample change-out the week before.

Suction restored and pump flow verified. Sample determined to be INVALID for sample period 10/20/2015-10/28/2015. Event documented through CR 16-04924 (Table 8-2 and Table 8-5, Note 2). 5. Air Sample Pump found energized but not running at Site 15 and Site 40 on 11/23/2015. Technician found REMP Air Sample Pumps at Site 15 and Site 40 energized but not running. Pumps were replaced and confirmed to be satisfactory. Results for these samples found to be INVALID for sample period 11/17/2015-11/23/2015. Event documented through CR 16-04949 (Table 8-2 and Table 8-5, Note 3). Cause later determined to be due to pump vane failures limited to recent shipment of rebuild kits (CR 15-12551) 6. Air Sample Pump found energized but not running at Site 15 on 12/1/2015. Technician found REMP Air Sample Pump at Site 15 energized but not running. Pump was replaced and confirmed to be satisfactory. Results for these samples found to be INVALID for sample period 11/23/2015-12/1/2015. Event documented through CR 15-11875 (Table 8-2 and Table 8-5, Note 3). Cause later determined to be due to pump vane failures limited to recent shipment of rebuild kits (CR 15-12551)

7. Air Sample Pump found energized but not running at Site 15 on 12/15/2015. Technician found REMP Air Sample Pumps at Site 15 energized but not running. Pump was replaced and confirmed to be satisfactory. Results for these samples found to be INVALID for sample period 12/8/2015-12/15/2015. Event documented through CR 15-12551 and cause determined to be due to pump vane failures limited to recent shipment of rebuild kits (Table 8-2 and Table 8-5, Note 3). 8. Missed La-140 LLD for Site 49 Drinking Water Sample On Tuesday 11-24-15 the count-room detectors were not usable due to software (APEX) malfunction. This malfunction resulted in the inability to achieve the required LLD of 15 pCi/L for Site

49. The achieved LLD for Site 49 was <32 pCi/L with a reporting level of 200 pCi/L. This is the only exception for meeting LLDs in drinking water. This event was documented through CR 15-11873 and CR 16-05908 (Table 8-8, Note 1). 9. Evaporation Pond 1C exceeded 4th Quarter I-131 reporting level of 20 pCi/L resulting in a unity value of greater than 1.0 (one).

The quarterly tritium value 2341. Evaporation Pond 1C had an I-131 validated result greater than the ODCM Reporting Level. Low level tritium (2341+/-193 pCi/L) was detected in Evaporation Pond 1C, which is below the ODCM Reporting Level. If more than one radionuclide from the ODCM Reporting Level table is detected, a unity value calculation must be performed, The elevated I-131 concentrations, originating from radiopharmaceuticals in Phoenix Influent (CRDR 4568037), accounted for 93% of the unity value. This occurrence is documented through CR 16-05005 (Table 8-10). 10. Site 49 TLD Sample Stanchion relocated due to construction. Technician observed fresh grading in apparent preparation for future road work had been done around the sample stanchion on 9-24-15, while performing the quarterly change-out of environmental TLDs. The technician moved the stanchion ~20 feet to prevent inadvertent damage or loss of the TLDs. The TLD stanchion was returned to original location during the next quarterly TLD change-out. This event and follow-up actions were documented through CR 15-08047 and AI 15-08047-004. 11. Site 10 TLD Sample Stanchion missing. Technician found the Site 10 TLD field holder, still intact and sealed, lying on the ground near the sample site, on 9-24-15 while performing the quarterly REMP environmental TLD change-out. The pipe and concrete were gone and could not be located. This event and evaluation were documented through CR 15-08042 and EVAL 15-08042-002. 12. Site 50 TLDs missing due to vandalism. The two TLDs used for monitoring location 50 were missing at the time of exchange due to vandalism. Processing results appear normal and are consistent with historical readings. In addition, no neutron exposure was measured at any of the monitored locations. Intralaboratory comparisons indicated an average bias of 0.001, with a standard deviation of 2.4 percent.

This event was documented through Correspondence Letter 218-03835-JER

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 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 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 Reclamation Facility (WRF), 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 I-131. Particulate filters were composited quarterly, by location, and analyzed for gamma emitting radionuclides.

3.5 Sludge and Sediment Sludge samples were obtained weekly from the WRF waste centrifuge (whenever the plant was operational) and analyzed for gamma emitting radionuclides. Cooling tower sludge was analyzed for gamma emitting radionuclides prior to disposal in the WRF 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 an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides. 4.2 Airborne Radioiodine The charcoal cartridge is counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for I-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. 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.

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. 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 an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides. 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 (HNO3) 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.

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. For reference, a priori LLDs are indicated at the top of data tables for samples having required LLD values. 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 2 counting 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.

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/m3) 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 10a 1 0.04b49 Cs-134 9 1 0.003b47 Cs-137 10 1 0.003b 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 m3, 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, Rev. 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 2015, 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 Range Acceptable? ID Type Value** Value Error E11152 Tritium H-3 pCi/L 1.26E+04 1.21E+04 3.55E+02 34 0.96 0.75-1.33YES E11153 Gamma Water I-131 pCi/L 9.67E+01 9.60E+01 8.56E+00 11 0.99 0.60-1.66YES Ce-141 pCi/L 1.39E+02 1.59E+02 1.02E+01 16 1.14 0.75-1.33YES Cr-51 pCi/L 3.66E+02 2.69E+02 4.74E+01 6 0.73 0.50-2.00YES Cs-134 pCi/L 1.26E+02 1.14E+02 7.80E+00 15 0.90 0.60-1.66YES Cs-137 pCi/L 1.67E+02 1.76E+02 1.22E+01 14 1.05 0.60-1.66YES Co-58 pCi/L 1.80E+02 1.90E+02 1.20E+01 16 1.06 0.75-1.33YES Mn-54 pCi/L 1.59E+02 1.75E+02 1.19E+01 15 1.10 0.60-1.66YES Fe-59 pCi/L 1.95E+02 1.79E+02 2.19E+01 8 0.92 0.60-1.66YES Zn-65 pCi/L 2.99E+02 3.01E+02 2.32E+01 13 1.01 0.60-1.66YES Co-60 pCi/L 3.28E+02 3.27E+02 1.61E+01 20 1.00 0.75-1.33YES E11154 I-131 Cartridge I-131 pCi/ea 7.78E+01 8.31E+01 2.70E+00 31 1.07 0.75-1.33YES E11155 Gamma Filter Ce-141 pCi/ea 6.96E+01 6.93E+01 3.58E+00 19 1.00 0.75-1.33YES Cr-51 pCi/ea 1.83E+02 2.09E+02 1.87E+01 11 1.14 0.60-1.66YES Cs-134 pCi/ea 6.31E+01 5.23E+01 3.89E+00 13 0.83 0.60-1.66YES Cs-137 pCi/ea 8.34E+01 8.24E+01 5.60E+00 15 0.99 0.60-1.66YES Co-58 pCi/ea 8.99E+01 9.17E+01 6.05E+00 15 1.02 0.60-1.66YES Mn-54 pCi/ea 7.94E+01 8.66E+01 5.88E+00 15 1.09 0.60-1.66YES Fe-59 pCi/ea 9.75E+01 1.08E+02 1.00E+01 11 1.11 0.60-1.66YES Zn-65 pCi/ea 1.50E+02 1.78E+02 1.20E+01 15 1.19 0.60-1.66YES Co-60 pCi/ea 1.64E+02 1.78E+02 9.30E+00 19 1.09 0.75-1.33YES E11156 Gamma Milk I-131 pCi/L 1.42E+01 1.65E+01 1.98E+00 8 1.16 0.60-1.66YES Ce-141 pCi/L 1.80E+01 1.73E+01 2.77E+00 6 0.96 0.50-2.00YES Cr-51 pCi/L 4.75E+01 6.08E+01 1.06E+01 6 1.28 0.50-2.00YES Cs-134 pCi/L 1.63E+01 1.66E+01 1.72E+00 10 1.02 0.60-1.66YES Cs-137 pCi/L 2.16E+01 2.16E+01 2.35E+00 9 1.00 0.60-1.66YES Co-58 pCi/L 2.33E+01 2.37E+01 2.86E+00 8 1.02 0.60-1.66YES Mn-54 pCi/L 2.06E+01 2.04E+01 2.35E+00 9 0.99 0.60-1.66YES Fe-59 pCi/L 2.53E+01 2.53E+01 5.40E+00 5 1.00 0.50-2.00YES Zn-65 pCi/L 3.88E+01 4.79E+01 5.16E+00 9 1.23 0.60-1.66YES Co-60 pCi/L 4.26E+01 4.29E+01 3.25E+00 13 1.01 0.60-1.66YES Table 7.1 Interlaboratory Comparison Results (Continued) E11157 Beta Filter G. Beta pCi/ea 8.78E+01 9.90E+012.20E+00 45 1.13 0.75-1.33YES E11349 Gamma Filter Ce-141 pCi/ea 8.12E+01 8.06E+018.53E+00 9 0.99 0.60-1.66YES Cr-51 pCi/ea 2.05E+02 1.72E+024.44E+01 4 0.84 0.50-2.00YES Cs-134 pCi/ea 8.07E+01 6.54E+014.36E+00 15 0.81 0.60-1.66YES Cs-137 pCi/ea 9.71E+01 1.05E+021.34E+01 8 1.08 0.60-1.66YES Co-58 pCi/ea 1.00E+02 1.06E+021.22E+01 9 1.06 0.60-1.66YES Mn-54 pCi/ea 1.11E+02 1.33E+021.39E+01 10 1.20 0.60-1.66YES Fe-59 pCi/ea 8.60E+01 1.05E+021.01E+01 10 1.22 0.60-1.66YES Zn-65 pCi/ea 1.35E+02 1.64E+021.62E+01 10 1.21 0.60-1.66YES Co-60 pCi/ea 1.26E+02 1.31E+028.18E+00 16 1.04 0.75-1.33YES E11350 I-131 Cartridge I-131 pCi/ea 7.46E+01 7.23E+011.42E+01 5 0.97 0.50-2.00YES E11351 Beta Water G. Beta pCi/L 2.37E+02 2.73E+026.00E+00 46 1.15 0.75-1.33YES E11352 Beta Filter G. Beta pCi/ea 7.87E+01 8.73E+011.50E+00 58 1.11 0.80-1.25YES

• 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 Systems; Water Chemistry; Confirmatory Measurements" 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 Gross Beta RAD-101 g beta pCi/L 38.8 32.9 21.3 - 40.8 Acceptable Water Tritium RAD-103 H-3 pCi/L 20,700 21,300 18700 - 23400 Acceptable Water Gamma RAD-103 Ba-133 pCi/L 31 32.5 25.9 - 36.7 Acceptable Cs-134 pCi/L 58.1 62.3 50.6 - 68.5 Acceptable Cs-137 pCi/L 144 157 141 - 175 Acceptable Co-60 pCi/L 72.2 71.1 64.0 - 80.7 Acceptable Zn-65 pCi/L 139 126 113 - 149 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. Random errors are beyond the control of the analyst. 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, and 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 2015 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 0.016 to 0.059 pCi/m3. 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.

8.2 Airborne Radioiodine Table 8-4 and Table 8-5 present the quarterly radioiodine 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 radionuclides. 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 6.5 pCi/liter. The gross beta activity is attributable to natural (background) radioactive materials.

8.6 Ground Water Ground water 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 Ponds 1B, 1C, and 2A. The I-131 levels ranged from 18 pCi/L - 23 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 2341 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 WRF Centrifuge Waste Sludge Sludge samples were obtained from the WRF 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 WRF Influent. The concentration of I-131 ranged from "no detectable" to 937 pCi/kg.

Results for WRF centrifuge waste sludge can be found in Table 8-11. 8.8.2 Cooling Tower Sludge Sludge/sediment originating from the Unit 2 and Unit 3 Cooling Towers and Circulating Water canals was disposed of in the WRF sludge landfill during 2015. 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(%)Note130-Dec-146-Jan-150.0470.0560.0550.0530.0510.0570.0580.0580.0530.0570.0546.526-Jan-1513-Jan-150.0490.0540.0550.0500.0550.0570.0580.0550.0530.0540.0545.1 313-Jan-1520-Jan-150.0390.0400.0380.0340.0350.0380.0370.0390.0360.0380.0375.5420-Jan-1527-Jan-150.0320.0360.0380.0340.0320.0360.0340.0350.0330.0350.0355.1527-Jan-153-Feb-150.0260.0300.0270.0290.0280.0280.0340.0330.0280.0280.0298.3 63-Feb-1510-Feb-150.0370.0530.0450.0450.0450.0460.0490.0480.0430.0460.0469.2710-Feb-1517-Feb-150.0300.0320.0270.0310.028*0.0250.0300.0310.0310.0297.91817-Feb-1523-Feb-150.0480.0500.0460.0460.0470.0460.0450.0460.0460.0490.0473.1 924-Feb-153-Mar-150.0210.0200.0200.0210.0210.0200.0200.0180.0220.0210.0204.82103-Mar-1510-Mar-150.0320.0310.0330.0330.0330.0310.0340.0240.0300.0280.03110.21110-Mar-1516-Mar-150.0450.0460.0460.0470.0480.0480.0460.0410.0450.0500.0465.1 1216-Mar-1523-Mar-150.0370.0360.0360.0360.0370.0360.0350.0350.0340.0360.0362.321323-Mar-1531-Mar-150.0250.0250.0250.0260.0260.0260.0240.0250.0230.0270.0254.7Mean0.0360.0390.0380.0370.0370.0390.0380.0370.0370.0380.0382.6(control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note1431-Mar-157-Apr-150.0320.0340.0370.0340.0320.0380.0350.0340.0310.0370.0346.4157-Apr-1514-Apr-150.0260.0250.0240.0250.0260.0310.0240.0250.0250.0250.0267.5 1614-Apr-1521-Apr-150.0310.0280.0310.0320.0340.0310.0310.0290.0310.0290.0315.61721-Apr-1528-Apr-150.0240.0210.0220.0240.0220.0240.0240.0240.0220.0230.0234.91828-Apr-155-May-150.0290.0240.0280.0290.0310.0320.0310.0290.0290.0300.0298.02195-May-1512-May-150.0270.0230.0260.0260.0220.0280.0260.0240.0260.0230.0256.92012-May-1519-May-150.0190.0160.0180.0200.0160.0210.0160.0210.0220.0180.01911.6 2119-May-1526-May-150.0330.0290.0310.0300.0280.0290.0300.0270.0310.0290.0305.82226-May-152-Jun-150.0370.0380.0410.0370.0230.0430.0350.0400.0320.0250.03519.1232-Jun-159-Jun-150.0310.0320.0310.0320.0290.0320.0300.0330.0300.0300.0313.2 249-Jun-1516-Jun-150.0390.0380.0360.0380.0400.0380.0360.0350.0370.0350.0374.52516-Jun-1523-Jun-150.0490.0430.0450.0430.0540.0370.0460.0430.0460.0460.0459.82623-Jun-1529-Jun-150.0430.0360.0380.0380.0340.0450.0380.0280.0390.0350.03712.7Mean0.0320.0300.0310.0310.0300.0330.0310.0300.0310.0300.0313.6Note:1. Sample for Site 17-A INVALID due to power loss from line out2. Weekly samples initially invalidated due to water intrusion; data provided as INFO ONLY. Evaluation 15-00990-001- Vendor confirmed sample media not compromised- conditions within testing criteria. Data included in this report.ODCM required samples denoted by *units are pCi/m31st Quarter2nd Quarter Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note2729-Jun-157-Jul-150.0420.0450.0410.0420.0380.0350.0360.0440.0380.0420.0408.1287-Jul-1514-Jul-150.0340.0350.0330.0330.0320.0330.0310.0340.0340.0350.0334.42914-Jul-1521-Jul-150.0290.0240.0290.0240.0240.0240.0230.0290.0250.0220.02510.9 3021-Jul-1529-Jul-150.0230.0210.0280.0230.0220.0200.0250.0290.0180.0210.02314.83129-Jul-154-Aug-150.0320.0330.0280.0250.0340.0270.0310.0280.0230.0270.02912.6324-Aug-1511-Aug-150.0340.0360.0330.0330.0360.0340.0310.037*0.0280.0348.41 3311-Aug-1518-Aug-150.0290.0330.0300.0310.0320.0330.0320.0310.0310.0300.0314.03418-Aug-1525-Aug-150.0310.0200.0270.0280.0270.0240.0230.0270.0300.0260.02612.13525-Aug-151-Sep-150.0340.0320.0340.0350.0330.0310.0340.0330.0350.0280.0336.1 361-Sep-158-Sep-150.0360.0350.0290.0310.0320.0320.0280.0250.0280.0230.03013.6378-Sep-1515-Sep-150.0340.0340.0390.0310.0310.0350.0300.0350.0360.0350.0347.63815-Sep-1522-Sep-150.0240.0240.0250.0260.0280.0250.0240.0280.0240.0260.0256.13922-Sep-1529-Sep-150.0470.0550.0490.0500.0530.0320.0460.0490.0470.0430.04713.3Mean0.0330.0330.0330.0320.0320.0300.0300.0330.0310.0300.032#REF!(control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note4029-Sep-156-Oct-150.0330.0420.0420.0380.0450.0410.0340.0390.0380.0390.0399.4416-Oct-1513-Oct-150.0340.0340.0340.0290.0310.0310.0290.0350.0310.0310.0327.04213-Oct-1520-Oct-150.0440.0430.0420.0370.0480.0430.0340.0410.0430.0330.04111.24320-Oct-1528-Oct-150.0470.0530.0520.0460.0540.0530.0390.048*0.0480.0499.524428-Oct-153-Nov-150.0510.0470.0530.0410.0570.0470.0390.0520.0430.0430.04712.5 453-Nov-159-Nov-150.0350.0340.0280.0290.0350.0370.0270.0290.0270.0270.03112.5469-Nov-1517-Nov-150.0390.0350.0360.0360.0380.0360.0330.0340.0370.0360.0365.54717-Nov-1523-Nov-150.0330.0400.0330.033*0.02540.0330.0330.0320.033*0.02280.0347.53 4823-Nov-151-Dec-150.0430.0420.0440.042*0.0450.0400.0450.0440.0400.0434.33491-Dec-158-Dec-150.0590.0580.0560.0550.0560.0570.0570.0590.0570.0580.0572.5508-Dec-1515-Dec-150.0460.0280.0460.041*0.0430.0460.0400.0450.0410.04213.435115-Dec-1521-Dec-150.0420.0390.0390.0370.0380.0360.0390.0360.0360.0370.0385.65221-Dec-1528-Dec-150.0260.0300.0280.0280.0280.0260.0260.0240.0220.0240.0269.1Mean0.0410.0400.0410.0380.0430.0410.0370.0390.0380.0380.0405.0Annual Average0.03550.03550.03570.03450.03530.03550.03410.03500.03400.03380.03497.9964min 6A0.0157min 7a0.018min 17A0.020all ind min0.016all ind mean0.034max 6A0.0576max 7a0.056max 17A0.057all ind max0.059Note:1. Sample for Site 35 found dislodged from pump and lying on ground- sample determined to be INVALID (CR 15-05977)2. Sample for Site 35 found with suction tube disconnected Filter showed no signs of sample collection (CR 16-04924)3. Air Sample Pump found energized but not running at Site 15 and Site 40 (11/23/2015), and at Site 15 (11/15/2015 and 12/15/2015). Samples invalid (CR 16-04949, 15-11875, and 15-12551). Problem identified as faulty vane kits and corrected.ODCM required samples denoted by *units are pCi/m33rd Quarter4th Quarter Table 8-3 Gamma in Air Filter Composites (control)QUARTERSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteENDPOINTNUCLIDE46A*7A14A*15*17A2129*3540*31-Mar-15Cs-134<0.0019<0.0028<0.0023<0.0046<0.0020<0.0021<0.0017<0.0028<0.0021<0.0033Cs-137<0.0029<0.0028<0.0025<0.0040<0.0020<0.0011<0.0023<0.0043<0.0020<0.004029-Jun-15Cs-134<0.0010<0.0042<0.0041<0.0019<0.0034<0.0022<0.0027<0.0023<0.0029<0.0021Cs-137<0.0033<0.0027<0.0044<0.0016<0.0046<0.0023<0.0047<0.0016<0.0041<0.002329-Sep-15Cs-134<0.0027<0.0024<0.0043<0.0011<0.0043<0.0034<0.0043<0.0039<0.0030<0.0018Cs-137<0.0041<0.0038<0.0053<0.0009<0.0053<0.0028<0.0062<0.0028<0.0032<0.006128-Dec-15Cs-134<0.0010<0.0007<0.0035<0.0061*<0.0031<0.0019<0.0025<0.0028**<0.0030<0.0011Cs-137<0.0048<0.0009<0.0044<0.0063*<0.0033<0.0016<0.0031<0.0024**<0.0048<0.0009* Site 15- two weeks invalid. Filters and volumes added into Quarterly stack** Site 35 (10/28/2015) Invalid - tube came off inside box. Vol of 1 m^3 and filter included in compositODCM required samples denoted by *units are pCi/m3 Table 8-4 Radioiodine in Air 1st - 2nd Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note130-Dec-146-Jan-15<0.0279<0.0585<0.0556<0.0315<0.0523<0.0333<0.0558<0.0357<0.0636<0.024326-Jan-1513-Jan-15<0.0284<0.0669<0.0561<0.0196<0.0443<0.0248<0.0576<0.0313<0.0679<0.0244 313-Jan-1520-Jan-15<0.0548<0.0526<0.0320<0.0493<0.0376<0.0625<0.0509<0.0295<0.0680<0.0376421-Jan-1527-Jan-15<0.0626<0.0572<0.0497<0.0594<0.0345<0.0446<0.0683<0.0530<0.0529<0.0532527-Jan-153-Feb-15<0.0183<0.0336<0.0682<0.023<0.0280<0.0668<0.0280<0.0501<0.0246<0.042263-Feb-1510-Feb-15<0.0320<0.0567<0.0544<0.0621<0.0689<0.0273<0.0588<0.0341<0.0657<0.0200 710-Feb-1517-Feb-15<0.0218<0.0329<0.0539<0.0295<0.0534*<0.0227<0.0552<0.0263<0.04611817-Feb-1523-Feb-15<0.0636<0.0640<0.0507<0.0079<0.0630<0.0234<0.0467<0.0294<0.0696<0.0344923-Feb-153-Mar-15<0.0195<0.0449<0.0473<0.0266<0.0370<0.0277<0.0489<0.0234<0.0598<0.02422103-Mar-1510-Mar-15<0.0628<0.0639<0.0312<0.0486<0.0396<0.0449<0.0379<0.0466<0.0304<0.06641110-Mar-1516-Mar-15<0.0261<0.0344<0.0399<0.0229<0.0406<0.0281<0.0389<0.0417<0.0283<0.03221216-Mar-1523-Mar-15<0.0346<0.0676<0.0418<0.0251<0.0578<0.0300<0.0457<0.0253<0.0457<0.03212 1323-Mar-1531-Mar-15<0.0377<0.0369<0.0285<0.0343<0.0222<0.0519<0.0233<0.0441<0.0291<0.0380(control)required LLD <0.070STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note1431-Mar-157-Apr-15<0.0317<0.0321<0.0376<0.0293<0.0551<0.0372<0.0545<0.0319<0.0670<0.0235157-Apr-1514-Apr-15<0.0239<0.0287<0.0548<0.0398<0.0549<0.0299<0.0550<0.0327<0.0296<0.06731614-Apr-1521-Apr-15<0.0340<0.0328<0.0424<0.0284<0.0694<0.0378<0.0338<0.0306<0.0394<0.02991721-Apr-1528-Apr-15<0.0627<0.0305<0.0658<0.0266<0.0670<0.0255<0.0685<0.0295<0.0602<0.01961828-Apr-155-May-15<0.0281<0.0538<0.0458<0.0273<0.0548<0.0242<0.0557<0.0339<0.0674<0.03352195-May-1512-May-15<0.0346<0.0531<0.0419<0.0225<0.0416<0.0348<0.0491<0.0328<0.0647<0.0263 2012-May-1519-May-15<0.0125<0.0489<0.0591<0.0296<0.0339<0.0217<0.0669<0.0687<0.0277<0.01882119-May-1526-May-15<0.0395<0.0370<0.0664<0.0395<0.0614<0.0299<0.0626<0.0301<0.0441<0.03402226-May-152-Jun-15<0.0402<0.0450<0.0171<0.0376<0.0207<0.0550<0.0237<0.0562<0.0217<0.0602 232-Jun-159-Jun-15<0.0465<0.0477<0.0635<0.0640<0.0504<0.0359<0.0688<0.0554<0.0633<0.0661 249-Jun-1516-Jun-15<0.0443<0.0445<0.0586<0.0514<0.0367<0.0444<0.0307<0.0435<0.0288<0.05632516-Jun-1523-Jun-15<0.0345<0.0302<0.0318<0.0304<0.0334<0.0364<0.0346<0.0266<0.0272<0.03342623-Jun-1529-Jun-15<0.0437<0.0558<0.0466<0.0369<0.0664<0.0287<0.0387<0.0325<0.0490<0.0310Note:1. Sample for Site 17-A INVALID due to power loss from line outrequired LLD <0.0702. Weekly samples initially invalidated due to water intrusion; data provided as INFO ONLY. Evaluation 15-00990-001- Vendor confirmed sample media not compromised- conditions within testing criteria. Data included in this report.ODCM required samples denoted by *units are pCi/m31st Quarter2nd Quarter Table 8-5 Radioiodine in Air 3rd - 4th Quarter (control)0.070STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note2729-Jun-157-Jul-15<0.0231<0.0446<0.0375<0.0221<0.0590<0.0263<0.0274<0.0237<0.0466<0.0248287-Jul-1514-Jul-15<0.0334<0.0582<0.0685<0.0245<0.0510<0.0299<0.0699<0.0305<0.0505<0.01922914-Jul-1521-Jul-15<0.0353<0.0638<0.0422<0.0265<0.0651<0.0273<0.0562<0.0326<0.0392<0.0183 3021-Jul-1529-Jul-15<0.0602<0.0366<0.0435<0.0506<0.0475<0.0567<0.0521<0.0601<0.0522<0.0422 3129-Jul-154-Aug-15<0.0347<0.0496<0.0673<0.0354<0.0676<0.0341<0.0609<0.0258<0.0665<0.0226 324-Aug-1511-Aug-15<0.0211<0.0643<0.0355<0.0321<0.0386<0.0282<0.0323<0.0260*<0.066313311-Aug-1518-Aug-15<0.0302<0.0296<0.0178<0.0292<0.0229<0.0350<0.0386<0.0313<0.0331<0.0251 3418-Aug-1525-Aug-15<0.0275<0.0569<0.0619<0.0254<0.0419<0.0304<0.0690<0.0299<0.0520<0.0318 3525-Aug-151-Sep-15<0.0366<0.0374<0.0295<0.0364<0.0358<0.0296<0.0207<0.0187<0.0073<0.0323 361-Sep-158-Sep-15<0.0380<0.0196<0.0521<0.0378<0.0367<0.0289<0.0403<0.0379<0.0282<0.0370 378-Sep-1515-Sep-15<0.0579<0.0581<0.0123<0.0421<0.0112<0.0304<0.0440<0.0281<0.0336<0.03433815-Sep-1522-Sep-15<0.0282<0.0342<0.0558<0.0347<0.0341<0.0348<0.0390<0.0330<0.0447<0.0303 3922-Sep-1529-Sep-15<0.0532<0.0265<0.0123<0.0391<0.0610<0.0413<0.0537<0.0382<0.0265<0.0224(control)0.070STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note4029-Sep-156-Oct-15<0.0472<0.0278<0.0353<0.0347<0.0573<0.0382<0.05460.053<0.0404<0.0521416-Oct-1513-Oct-15<0.0358<0.0223<0.0481<0.0312<0.0387<0.0269<0.0513<0.0370<0.0320<0.04114213-Oct-1520-Oct-15<0.0233<0.0468<0.0402<0.0261<0.0386<0.0183<0.0353<0.0255<0.0428<0.0385 4320-Oct-1528-Oct-15<0.0370<0.0376<0.0321<0.0359<0.0301<0.0223<0.0332<0.0387*<0.02752 4428-Oct-153-Nov-15<0.0338<0.0411<0.0683<0.0384<0.0651<0.0481<0.0558<0.0362<0.0206<0.0307 453-Nov-159-Nov-15<0.0578<0.0532<0.0517<0.0277<0.0388<0.0453<0.0358<0.0559<0.0356<0.0.296469-Nov-1517-Nov-15<0.0206<0.0220<0.0287<0.0247<0.0562<0.0240<0.0296<0.0263<0.0223<0.02824717-Nov-1523-Nov-15<0.0315<0.0427<0.0363<0.0268*<0.0399<0.0289<0.0379<0.0366*3 4823-Nov-151-Dec-15<0.0346<0.0408<0.0122<0.0579*<0.0334<0.0420<0.0492<0.0425<0.0492<0.03353491-Dec-158-Dec-15<0.0429<0.0221<0.0421<0.0294<0.0348<0.0487<0.0240<0.0517<0.0292<0.0235508-Dec-1515-Dec-15<0.0302<0.0261<0.0553<0.0413*<0.0352<0.0303<0.0322<0.0263<0.0347<0.020835115-Dec-1521-Dec-15<0.0378<0.0351<0.0272<0.0392<0.0374<0.0222<0.0425<0.0083<0.0466<0.03685221-Dec-1528-Dec-15<0.0428<0.0340<0.0409<0.0265<0.0449<0.0492<0.0692<0.0450<0.0203<0.0316Note:1. Sample for Site 35 found dislodged from pump and lying on ground- sample determined to be INVALID (CR 15-05977)

2. Sample for Site 35 found with suction tube disconnected Filter showed no signs of sample collection (CR 16-04924)

3. Air Sample Pump found energized but not running at Site 15 and Site 40 (11/23/2015), and at Site 15 (11/15/2015 and 12/15/2015). Samples invalid (CR 16-04949, 15-11875, and 15-12551). Problem identified as faulty vane kits and corrected.ODCM required samples denoted by *units are pCi/m33rd Quarter4th Quarter Table 8-6 Vegetation units are pCi/kg, wet<60<60<80LOCATIONTYPEDATE COLLECTEDI-131Cs-134Cs-137LOCALRESIDENCE(Site #47)*Red Cabbage22-Jan-15<54<59<65Green Cabbage22-Jan-15<42<44<73Green Cabbage12-Feb-15<55<59<57Savory Cabbage12-Feb-15<39<41<34Savory Cabbage12-Mar-15<45<56<54COMMERCIALFARM(Site #62)*Green Cabbage22-Oct-15<59<44<62Green Cabbage20-Nov-15<42<42<75Green Cabbage10-Dec-15<50<31<62Lettus22-Jan-15<57<50<73Red Lettuce12-Feb-15<53<48<54Kale12-Mar-15<59<51<69Broccoli Greens16-Apr-15<42<58<63Swiss Chard16-Apr-15<39<59<52 Swiss Chard14-May-15<47<45<57Swiss Chard18-Jun-15<43<37<50Swiss Chard15-Jul-15<55<36<80 Basil12-Aug-15<48<54<48Basil23-Sep-15<54<48<70Lettus10-Dec-15<54<31<54LOCAL RESIDENCE (Site #51)**NONE AVAILABLE****NONE AVAILABLE**

• • NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**ODCM required samples denoted by ***NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**Vegetation 2015**NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**

• • NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**

Table 8-7 Milk SAMPLEDATE<1<15<18<60<15LOCATIONCOLLECTEDI-131Cs-134Cs-137Ba-140La-14022-Jan-15<1<0.8<0.9<3<1Local Resident12-Feb-15Goats12-Mar-15<1<0.8<0.9<3<1(Site #51)*16-Apr-15<1<0.8<0.9<3<114-May-15<1<0.8<1<3<118-Jun-15<1<0.8<0.9<3<115-Jul-15<1<0.8<0.9<3<112-Aug-15<1<0.8<1<3<0.923-Sep-15<1<1<1<4<1.608-Oct-15<1<0.7<0.8<3<120-Nov-15<1<0.8<0.9<3<110-Dec-15<1<0.8<1<3<115-Jan-1520-Feb-15<1<0.8<1<3<124-Mar-15<1<0.8<1<3<1Local Resident23-Apr-15<1<0.8<1<3<1Goats21-May-15<1<0.8<1<3<1(Site #53)*19-Jun-15<1<0.8<1<3<123-Jul-15<1<0.8<1<3<127-Aug-15<1<0.8<1<3<0.917-Sep-15<1<0.6<1<3<1 22-Oct-15<1<0.9<1<4<1.520-Nov-15<1<0.8<1<3<110-Dec-15<1<1<1<3<115-Jan-15<1<0.8<1<3<1Local Resident12-Feb-15<1<0.8<1<3<1Goats12-Mar-15<1<0.7<0.9<3<1(Site #54)09-Apr-15<1<0.8<1<3<107-May-15<1<0.8<1<3<111-Jun-15<1<0.8<1<3<0.909-Jul-15<1<0.8<1<3<0.913-Aug-15<1<0.8<0.9<3<118-Sep-15<1<0.7<0.8<3<108-Oct-15<1<0.6<0.7<3<112-Nov-15<1<0.8<0.9<3<1 10-Dec-15<1<0.8<0.9<3<1**No Sample Available: newborn goats**ODCM required samples denoted by *units are pCi/liter**No Sample Available**

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 BetaNote27-Jan-15<10<9<17<12<24<12<16<10<9<11<30<15<3.3323-Feb-15<12<10<24<10<29<9<16<10<9<10<41<14<3.0931-Mar-15<10<9<18<13<30<10<15<8<10<10<26<11<3243.632.1128-Apr-15<12<9<21<10<25<11<17<11<8<12<41<153.712.02LOCAL26-May-25<11<14<30<13<21<13<18<12<14<13<44<13<3.42RESIDENCE29-Jun-15<12<10<20<14<25<11<20<10<9<13<32<15<324<3.35(Site #48) *29-Jul-15<13<15<27<12<30<13<21<14<14<8<41<126.091.9025-Aug-15<10<8<16<8<19<7<16<9<10<10<32<123.651.9629-Sep-15<7<7<15<8<16<8<14<7<6<7<25<15<3283.651.9727-Oct-15<3<3<7<4<7<4<6<4<3<4<15<104.261.8423-Nov-15<9<8<16<11<20<11<16<6<7<9<19<93.961.8328-Dec-15<5<5<8<5<11<5<9<5<4<5<15<10<3343.171.8727-Jan-15<8<8<15<8<15<10<12<9<6<9<32<155.241.6523-Feb-15<11<15<25<13<30<13<22<12<12<13<43<145.341.4931-Mar-15<11<12<22<13<30<11<20<10<10<13<38<15<3194.241.5228-Apr-15<13<12<22<11<29<14<23<12<12<12<45<155.341.55LOCAL26-May-25<11<11<20<10<24<13<17<11<11<13<37<153.421.56RESIDENCE29-Jun-15<13<13<21<11<25<10<18<10<12<12<34<15<3234.281.50(Site #55)29-Jul-15<11<8<17<12<19<10<17<9<10<11<31<153.491.4825-Aug-15<9<11<22<13<25<11<19<10<10<9<36<153.871.4829-Sep-15<8<9<14<7<17<9<14<7<7<9<26<15<3284.411.5628-Oct-15<5<5<10<6<13<5<8<6<5<6<18<154.141.6323-Nov-15<10<10<21<10<21<10<17<9<9<12<33<96.051.5828-Dec-15<10<10<19<10<20<8<17<10<8<11<32<15<335<2.38ODCM required samples denoted by *units are pCi/liter 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 BetaNote27-Jan-15<9<8<19<9<18<10<16<8<8<9<35<12<2.1723-Feb-15<13<15<27<15<26<14<22<14<11<11<46<142.001.2231-Mar-15<8<9<23<13<29<12<19<11<11<15<37<15<3202.291.3328-Apr-15<12<12<27<14<24<13<24<10<12<13<44<134.281.4126-May-25<9<13<27<13<27<12<20<12<12<14<34<123.481.50LOCAL29-Jun-15<8<9<16<12<26<9<14<10<10<9<29<15<324<2.08RESIDENCE29-Jul-15<9<11<17<11<22<9<13<9<9<8<33<152.731.40(Site #46) *25-Aug-15<10<15<19<15<27<15<21<13<12<15<43<4<2.0729-Sep-15<9<8<18<8<18<10<14<9<7<8<31<13<3283.271.4428-Oct-15<3<3<6<3<6<3<5<4<3<3<12<82.391.4423-Nov-15<7<9<19<7<14<10<16<8<7<9<26<123.171.3828-Dec-15<12<9<18<9<26<12<22<11<8<13<37<14<332<2.2427-Jan-15<8<9<19<12<25<10<14<9<9<9<31<15<2.1523-Feb-15<11<11<14<12<23<7<16<9<11<10<33<15<1.8331-Mar-15<10<8<19<15<19<12<18<9<10<10<41<15<319<2.0128-Apr-15<11<8<20<12<27<13<20<11<10<12<37<14<1.9826-May-25<11<10<25<12<25<11<17<9<11<12<37<13<2.18LOCAL29-Jun-15<10<11<21<13<27<12<21<10<10<13<42<15<325<2.07RESIDENCE29-Jul-15<11<8<17<10<23<10<16<9<9<10<34<14<2.08(Site #49) *25-Aug-15<12<13<18<8<25<15<22<14<10<13<44<11<2.0629-Sep-15<8<7<14<7<15<8<11<7<6<8<22<15<325<2.0928-Oct-15<5<6<10<6<11<6<9<6<5<6<23<14<2.1723-Nov-15<1<1<2<1<2<1<2<2<1<1<4*<323.531.40128-Dec-15<8<7<14<8<16<8<12<7<6<8<25<9<3333.041.46Note:1. LLD for La-140 not met due to APEX error. CR 15-11873ODCM required samples denoted by *units are pCi/liter Table 8-9 Groundwater units are pCi/literSAMPLEDATE<15<15<30<15<30<15<30<15<15<18<60<15<2000LOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium27-Jan-15<12<12<21<12<23<13<18<13<9<10<44<15<316WELL 27ddc28-Apr-15<13<14<28<14<24<14<23<11<11<13<35<15<313(Site #57)*28-Jul-15<11<11<23<15<23<14<19<13<12<13<45<13<32427-Oct-15<5<5<12<6<14<6<8<6<5<6<20<15<32827-Jan-15<10<11<24<12<25<12<13<12<10<12<41<15<319WELL 34abb28-Apr-15<10<9<22<11<25<10<17<10<9<10<31<15<315(Site #58)*28-Jul-15<12<11<23<12<19<10<18<12<10<10<40<15<32127-Oct-15<4< 3<7<4<9<5<7<4<4<4<16<13<325ODCM required samples denoted by

• Table 8-10 Surface Water 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-140Tritium45 ACRE*27-Jan-15<11<9<20<11<22<12<191910<10<12<41<15<321RESERVOIR28-Apr-15<13<12<25<12<27<11<20<12<10<12<36<15<324(Site #61)

• 28-Jul-15<10<10<16<11<19<10<16137<9<10<35<15<32927-Oct-15<5<5<13<6<12<5<9<7<5<5<20<14<33085 ACRE*27-Jan-15<11<11<26<11<21<11<211412<10<12<44<14<327RESERVOIR28-Apr-15<10<9<19<15<23<9<17<12<10<14<33<12<338(Site #60) * *28-Jul-15<12<11<23<13<22<12<181911<10<13<39<15<33027-Oct-15<5<5<9<5<10<5<844<4<5<19<14<328EVAP POND 127-Jan-15<8<9<25<13<30<11<16<11<9<12<37<131156222(Site #59) *28-Apr-15<11<10<26<10<29<11<21<11<11<13<43<141415216CELL 1A28-Jul-15<13<14<22<15<30<12<17<12<12<12<38<12118121427-Oct-15<8<6<15<8<17<7<12<7<6<8<25<81337220CELL 1B27-Jan-15<10<12<25<10<21<11<18<11<11<9<38<14<338*4/28/2015<11<11<22<10<26<12<211811<11<11<44<1592620628-Jul-15<11<11<25<15<26<11<15<9<8<11<33<12107021027-Oct-15<11<9<21<12<17<11<21<11<11<12<44<11748192CELL 1C27-Jan-15<13<14<28<15<30<13<20<11<10<14<37<13<33728-Apr-15<13<12<27<15<28<13<22<10<11<15<39<1543319828-Jul-15<9<11<28<13<30<10<20<12<9<13<36<10461199*10/27/2015<7<8<18<10<19<8<14238<7<9<28<112341193*Recounted and averagedODCM required samples denoted by *units are pCi/liter Table 8.10 Surface Water EVAP POND 227-Jan-15<12<11<26<13<25<13<21<13<11<11<38<15456209(Site #63) *28-Apr-15<11<8<23<11<30<12<18<10<10<14<37<10636201CELL 2A*28-Jul-15<12<13<27<12<30<13<201410<10<13<38<13716+/-20527-Oct-15<4<4<9<5<9<5<7<5<4<5<17<7541205CELL 2B27-Jan-15<14<12<29<14<30<13<21<13<10<13<40<1288921828-Apr-15<10<8<20<13<30<11<18<12<10<10<34<1567820228-Jul-15<11<10<22<12<26<10<17<11<9<10<39<1562420427-Oct-15<4<4<10<7<12<6<10<5<5<6<23<10537205EVAP POND 327-Jan-15<12<12<29<13<26<11<19<13<10<12<41<15912217(Site #64) *28-Apr-15<12<11<28<13<30<12<16<11<10<12<42<111014208CELL 3A28-Jul-15<12<11<24<13<30<11<23<11<10<14<36<1480920827-Oct-15<6<6<13<7<15<6<10<6<6<7<22<15745208CELL 3B27-Jan-15<11<9<22<12<24<10<18<10<9<11<37<1582421528-Apr-15<11<11<27<14<30<11<19<10<10<13<46<1543519628-Jul-15<10<9<23<12<30<9<18<10<11<12<33<1279320827-Oct-15<8<7<18<9<22<8<13<7<7<9<26<15819210*Recounted and averagedODCM required samples denoted by *units are pCi/liter Table 8.10 Surface Water SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium **6-Jan-15<12<10<23<15<23<11<1819 9<10<11<36<1313-Jan-15<15<11<23<12<27<9<1818 12<10<12<36<1320-Jan-15<11<11<19<12<30<9<2115 7<10<12<40<1427-Jan-15<12<8<24<15<27<13<223311<10<11<39<15<3313-Feb-15<11<12<24<15<23<13<164511<10<13<42<1010-Feb-15<13<12<23<11<29<11<2148<10<11<36<1217-Feb-15<12<12<30<15<22<14<214013<12<11<44<1323-Feb-15<9<9<19<12<20<12<184812<9<11<40<15<3443-Mar-15<11<10<18<15<24<9<203612<10<12<33<1310-Mar-15<10<13<21<12<27<12<204213<10<10<38<1216-Mar-15<11<10<19<10<17<12<196714<9<11<34<1423-Mar-15<11<11<25<13<30<9<184611<9<11<34<1231-Mar-15<11<8<23<11<27<10<223912<8<11<33<15<342WRF7-Apr-15<11<9<21<12<22<10<164312<10<12<31<12 INFLUENT14-Apr-1521-Apr-1528-Apr-15<11<11<22<10<19<9<18<11<10<10<34<14<3265-May-15<11<12<26<13<28<12<191811<11<14<35<1512-May-15<13<12<24<11<29<13<18189<11<13<39<819-May-15<11<15<21<13<23<14<19<12<13<12<47<1526-May-15<9<10<27<11<26<10<16129<10<11<35<15<3292-Jun-15<12<8<18<14<19<10<181711<9<11<40<159-Jun-15<11<10<28<11<29<12<18269<10<11<38<1316-Jun-15<13<13<25<13<26<13<203314<12<13<38<1523-Jun-15<8<9<23<10<23<9<16119<9<11<37<1529-Jun-15<11<10<20<11<26<9<151710<10<10<29<15<3347-Jul-15<12<13<27<15<25<13<211810<10<15<42<1514-Jul-15<12<11<28<14<30<14<23249<11<13<45<1521-Jul-15<9<10<20<13<24<9<192011<8<13<36<15** monthly compositeNO SAMPLE- WRF OUTAGEODCM required samples denoted by *units are pCi/literNO SAMPLE- WRF OUTAGE Table 8.10 Surface Water 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-140Tritium **Note28-Jul-15<10<13<20<12<30<14<203011<11<13<34<13<3324-Aug-15<11<9<22<13<30<10<182510<10<11<38<1311-Aug-15<12<14<25<14<29<15<221213<12<15<48<1418-Aug-15<12<13<17<15<28<10<25<12<12<12<37<15 25-Aug-15<12<14<16<15<21<12<20<12<11<12<32<141-Sep-15<13<11<27<15<29<13<22<13<12<13<42<98-Sep-15<8<8<17<9<19<8<1496<8<8<29<24115-Sep-15<6<6<11<6<12<6<10<6<6<6<20<822-Sep-15<1<1<2<1<2<1<293<1<1<6*<13<33429-Sep-15<6<6<14<7<13<6<10176<6<6<22<10<3416-Oct-15<9<7<17<8<18<8<16<239<8<10<32<1013-Oct-15<7<6<13<6<14<7<1175<5<8<20<10WRF20-Oct-15 INFLUENT27-Oct-15<7<7<13<7<13<7<10148<6<7<26<14<3383-Nov-15<4<4<8<3<8<4<643<3<4<11<49-Nov-15<9<7<13<11<15<11<1756<7<11<35<1217-Nov-15<6<6<11<6<16<6<1186<5<6<20<723-Nov-15<3<3<6<2<5<3<5166<2<3<14<158<33611-Dec-15<6<6<12<5<9<5<10<7<4<5<20<148-Dec-15<9<9<16<10<18<9<13<8<6<11<24<9*12/15/2015<7<6<11<7<12<6<1294<6<7<20<7C21-Dec-15<7<8<14<9<15<6<1277<6<6<21<1128-Dec-15<3<3<6<4<7<4<6154<3<4<11<6<346*Recounted and averaged1. LLD for La-140 not met due to APEX software issue documented in CR 15-11873. WRF Influent source is Phoenix Sewage; samples taken prior to interface with plant. Not ODCM sample location; reported for trending.ODCM required samples denoted by *units are pCi/liter** monthly compositeNO SAMPLE- WRF OUTAGE Table 8.10 Surface Water SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium6-Jan-1513-Jan-1520-Jan-15 27-Jan-15<8<9<18<12<25<11<16<10<9<11<33<15<3313-Feb-15<13<15<29<15<28<12<20<10<12<13<38<12<36210-Feb-15<13<11<29<11<30<12<23<10<10<12<47<14<36317-Feb-15<10<13<23<12<24<13<19<11<11<13<37<1454221523-Feb-15<14<12<26<11<30<14<19<10<12<12<40<133622193-Mar-15<11<12<19<7<29<12<18<10<11<13<31<1548320810-Mar-15<11<14<21<11<25<12<22<10<9<15<37<1451521216-Mar-15<13<11<26<15<28<14<21<10<10<13<43<12569+/-21023-Mar-15<12<12<22<13<24<11<15<11<11<10<30<1541621331-Mar-157-Apr-1514-Apr-1521-Apr-15 28-Apr-155-May-15<10<13<18<15<22<13<23<11<10<12<50<15<34212-May-1519-May-15<7<7<19<10<19<7<14<7<7<9<32<1243320827-May-15<10<9<19<10<24<11<17<10<9<12<34<12<3432-Jun-159-Jun-1516-Jun-1523-Jun-15 29-Jun-15**EMPTY****EMPTY****EMPTY**units are pCi/literODCM required samples denoted by ***EMPTY****EMPTY**

• • EMPTY****EMPTY****EMPTY**SEDIMENTATION BASIN #2**EMPTY****EMPTY****EMPTY****EMPTY****EMPTY****EMPTY**

Table 8.10 Surface Water 7-Jul-1514-Jul-1521-Jul-15<14<14<25<13<20<15<19<11<10<10<46<3<353*7/28/2015<10<9<20<12<24<11<18<9<9<11<36<15<3484-Aug-15<10<10<17<14<24<10<21<9<11<11<37<15<34111-Aug-1518-Aug-15 22-Sep-151-Sep-15 8-Sep-1515-Sep-15 22-Sep-1529-Sep-156-Oct-1513-Oct-15 20-Oct-15 27-Oct-153-Nov-159-Nov-1617-Nov-15 23-Nov-151-Dec-15 8-Dec-1515-Dec-15 21-Dec-15 28-Dec-15* Duplicate on Gamma only; results avereraged**EMPTY****EMPTY****EMPTY**units are pCi/liter**EMPTY****EMPTY**

• • EMPTY**

• • EMPTY**

• • EMPTY**SEDIMENTATION BASIN #2**EMPTY****EMPTY****EMPTY****EMPTY**

• • EMPTY****EMPTY****EMPTY**

• • EMPTY**

• • EMPTY**

• • EMPTY****EMPTY****EMPTY****EMPTY****EMPTY**

• • EMPTY**ODCM required samples denoted by

• Table 8-11 Sludge/Sediment SAMPLEDATE<6,000<150<180LOCATIONCOLLECTEDI-131Cs-134Cs-137In-1116-Jan-15167 81<122<10713-Jan-15374 149<108<13620-Jan-15296 122<98<8327-Jan-15354148<125<1733-Feb-15461140<104<80WRF10-Feb-15875186<103<110CENTRIFUGE17-Feb-15441133<103<123WASTE SLUDGE23-Feb-15405181<102<1763-Mar-15457178<147<14010-Mar-15507165<101<12516-Mar-15377119<96<14023-Mar-15538146<117<14131-Mar-15526139<111<1057-Apr-15588163<149<16714-Apr-1521-Apr-1528-Apr-15265155<146<1715-May-15None Detected<143<9812-May-15399150<150<16219-May-15229115<96<12826-May-15None Detected<101<1692-Jun-15344131<136<1589-Jun-15166131<146<18016-Jun-15396154<28<16123-Jun-15937193<117<10029-Jun-15686203<143<1647-Jul-15635152<105<13214-Jul-15311122<102<11321-Jul-15512127<84<12728-Jul-15772192<128<1754-Aug-15680149<80<7811-Aug-15475140<117<8218-Aug-15487123<107<29ODCM required samples denoted by *units are pCi/kg, wetNO SAMPLE- WRF OUTAGENO SAMPLE- WRF OUTAGE Table 8.11 Sludge/Sediment SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-11125-Aug-15284133<145<1691-Sep-15368119<68<1148-Sep-15399103<42<5215-Sep-15586143<79<12022-Sep-15540178<149<173WRF29-Sep-15569144<146<168CENTRIFUGE6-Oct-15431146<116<151WASTE SLUDGE13-Oct-15661184<117<13220-Oct-1527-Oct-153-Nov-15None Detected<122<1069-Nov-15175116<84<10317-Nov-15409138<113<17724-Nov-15296150<82<301-Dec-15452155<99<1748-Dec-15None Detected<102<13715-Dec-15267150<134<12821-Dec-1516076<68<6929-Dec-1534184<63<47SEDIMENTATION BASIN #2ODCM required samples denoted by *units are pCi/kg, wetNO SAMPLE- WRF OUTAGENO SAMPLE- WRF OUTAGENo Sample Table 8.11 Sludge/Sediment Cooling Tower Sludge Unit Cycle Approximate Volume (yd3) Isotope Activity Range (pCi/g) Sample Type U3R17 375 All principal gamma emitters <MDA Towers/Canal Sludge U3R18 295 All principal gamma emitters Cs-137/ 2.48 E-1 Towers/Canal Sludge U2R19 338 All principal gamma emitters <MDA Towers/Canal Sludge Note: The Cs-137 identified in U3R18 cooling tower sludge is atypical and meets ARRA SAL 7-368 criteria for onsite landfill disposal. ARRA analysis found all samples to meet criteria for disposal in the onsite landfill per SAL 7-368. Table 8-12 Hard -To-Detect Radionuclide Results Hard-To-Detect Radionuclide (pCi/Liter) Sample Location Well numberSample DateC-14 Fe-55Ni-63Sr-90Unit 1 (outside RCA)APP-12 12/22/2015 <60.2 <145<3.62<1.92Unit 2 (inside RCA)H0A 12/31/2015 <58.3 <148<3.90<1.99Unit 3 (inside RCA)H2 12/29/2015 <58.7 <162<3.58<1.90

10. Land Use Census 10.1. Introduction In accordance with the PVNGS ODCM, Section 6.2, the annual Land Use Census was performed in June 2015. 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 Land Use Census 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 Nearest Resident There was no change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.248 mRem. Milk Animal There was no change in milk animal status from the previous year. Dose calculations indicated the highest dose to be 0.399 mRem. Vegetable Gardens One garden was added to the ODCM as a required sampling location. This location was identified as part of the 2014 Land Use Census; however, due to the garden not meeting the required size of 500 square feet, it was sampled as a Supplemental sample. In 2015, the garden was identified as meeting the minimum 500 square foot size and added to the ODCM. Dose calculations indicated the highest dose to be 0.321 mRem. See Table 10-1for 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 2014 N 1.55 3.10 3.66 Resident Garden Milk 7.24E-2 1.66E-1 1.57E-1 NNE 1.52 3.30 3.05 Resident Garden Milk 1.35E-1 3.21E-1 3.99E-1 NE 2.16 NONE NONE Resident 1.49E-1 ENE 2.05 4.84 4.84 Resident Garden Milk 1.52E-1 2.05E-1 2.05E-1 Garden location added. E 2.81 NONE NONE Resident 1.15E-1 ESE 1.95 NONE NONE Resident 2.48E-1 SE 3.36 NONE NONE Resident 2.23E-1 SSE NONE NONE NONE NA S NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.71E-1 WSW 0.75 NONE NONE Resident 1.26E-1 W 0.70 NONE NONE Resident 7.09E-2 WNW NONE NONE NONE NA NW 0.93 NONE NONE Resident 7.70E-2 NNW 1.30 NONE NONE Resident 6.21E-2 Comments: Dose calculations were performed using GASPAR code and 2015 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual organ dose identified.

11. Summary and Conclusions The conclusions are based on a review of the radio assay results and environmental gamma radiation measurements for the 2015 calendar year. Where possible, the data were compared to pre-operational sample data. All sample results for 2015 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, WRF Influent, WRF 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. There was no measurable radiological impact on the environment in 2015 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 2015 Medium or Pathway Sampled Lower Limit of Detection (LLD) All Indicator Locations Location with Highest Annual Mean Control Locations (Unit of Measurement) Type and Total Number of Analyses Performed (from Table 6.1) Mean (f)a Name Mean (f)a Mean (f)a Number of Nonroutine Reported Measurements Range Distance and Range Direction Range Direct Radiation (mrem/std. qtr.) TLD - 200 NA 25.2 (187/188) Site #35 31.9 (4/4) 24.9(8/8) 1 18.3 - 33.9 8 miles 330° 29.9 - 33.9 22.8 - 28.0 Air Particulates (pCi/m3) Gross Beta - 519 0.01 0.035 (545/552) Site # 29 0.035 (52/52) 0.035 (52/52) 7 0.016 - 0.059 1 mile 270º 0.018 - 0.059 0.016 - 0.058 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/m3) Gamma Spec. - 519 I-131 0.07 <LLD NA <LLD <LLD 4 <LLD NA <LLD <LLD Broadleaf Vegetation (pCi/Kg-wet) Gamma Spec. - 10 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 8 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 3.9 (29/48) Site #55 4.5 (11/12) NA 0 2.0 - 6.1 3 miles 214° 3.4 -6.5 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 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 1 Gamma Spec. - 27 Milk I-131 1 <LLD NA <LLD <LLD 0 (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. - 30 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 15 (7/36) Site #59 21 (2/12) NA 0 13-23 Onsite 180° 18-23 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 20 3000 865 (26/36) Site #59 1107 (10/12) NA 0 433 - 2341 Onsite 180° 433 - 2341 (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. 1985-2013 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 26, 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, 17 Oct. 2014. Web. 08 Apr. 2016. 10. "NCRP Report No. 160: Ionizing Radiation Exposure of the Population of the United States." Journal of Radiological Protection J. Radiol. Prot. 29.3 (2009): 465. Web.

Technical Specification 5.6.2 5.6.2A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Diablo Canyon Palo Verde Wolf Creek Palo Verde Nuclear Generating Station PO Box 52034 Phoenix, Arizona 85072-2034 Mail Station 7636 102-07241-TNW/MDD/TMJ April 29, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Annual Radiological Environmental Operating Report 2015 In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2015. No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Michael DiLorenzo, Licensing Section Leader, at (623) 393-3495. Sincerely, Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/TMJ/akf

Enclosure:

Annual Radiological Environmental Operating Report 2015 cc: M. L. Dapas NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. M. Watford NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS A. V. Godwin Arizona Radiation Regulatory Agency (ARRA) T. Morales Arizona Radiation Regulatory Agency (ARRA)

ENCLOSURE Palo Verde Nuclear Generating Station UNITS 1, 2, and 3 Annual Radiological Environmental Operating Report 2015

1. Introduction ............................................................................................................................. 2 Overview ..................................................................................................................................... 2 Radiation and Radioactivity ........................................................................................................ 3 2. Description of the Monitoring Program .................................................................................. 5 2.1 Radiological Environmental Monitoring Program ............................................................... 5 2.2 Radiological Environmental Monitoring Program Changes for 2015 .................................. 5 2.3 REMP Deviations/Abnormal Events Summary .................................................................... 6 2.4 Ground Water Protection ...................................................................................................... 7 3. Sample Collection Program .................................................................................................. 14 3.1 Water ................................................................................................................................... 14 3.2 Vegetation ........................................................................................................................... 14 3.3 Milk ..................................................................................................................................... 14 3.4 Air ....................................................................................................................................... 14 3.5 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 4.3 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 ................................................................................... 17 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 Ground Water ...................................................................................................................... 29 8.7 Surface Water ...................................................................................................................... 29 8.8 Sludge and Sediment ........................................................................................................... 30 8.8.1 WRF 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 ..................................................... 58 10. Land Use Census ................................................................................................................ 64 10.1. Introduction ................................................................................................................ 64 10.2. Census Results ............................................................................................................ 64 11. Summary and Conclusions ................................................................................................ 69 12. References .......................................................................................................................... 73 LIST OF TABLES Table 2-1 Sample Collection Locations .......................................................................................... 8 Table 2-2 Sample Collection Schedule ........................................................................................... 9 Table 2-3 Summaries of the REMP Deviations/Abnormal Events .............................................. 10 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 ......................................................................................................... 47 Table 8-12 Hard -To-Detect Radionuclide Results ...................................................................... 49 Table 9-1 TLD Site Locations ...................................................................................................... 59 Table 9-2 Environmental TLD Results ......................................................................................... 61 Table 10-1 Land Use Census ........................................................................................................ 65 Table 11-1 Environmental Radiological Monitoring Program Annual Summary ........................ 70 TABLE OF FIGURES Figure 1-1 Sources of Radiation Exposure in the United States ..................................................... 4 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 ........................................................................... 50 Figure 8-2 Gross Beta in Air, 3rd - 4th Quarter ............................................................................ 51 Figure 8-3 Historical Gross Beta in Air (Weekly System Average) ............................................ 52 Figure 8-4 Historical Gross Beta in Air (Annual Site to Site Comparisons) Compared to Pre-Op....................................................................................................................................................... 53 Figure 8-5 Gross Beta in Drinking Water ..................................................................................... 54 Figure 8-6 Evaporation Pond Tritium Activity (Pre-Op- 2008) ................................................... 55 Figure 8-7 Evaporation Pond Tritium Activity (2009-2015) ........................................................ 56 Figure 8-8 Sedimentation Basin 2 Cs-137 .................................................................................... 57 Figure 9-1 Network Environmental TLD Exposure Rates ........................................................... 62 Figure 9-2 Environmental TLD Comparison- Pre-Operational VS 2015 ..................................... 63 Figure 10-1 Historical Comparison of Nearest Resident Dose ..................................................... 66 Figure 10-2 Historical Comparison of Nearest Milk Animal Dose .............................................. 67 Figure 10-3 Historical Comparison of Nearest Garden Dose ....................................................... 68

ABSTRACT 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 2015, the following categories of samples were collected by APS:

• Broad leaf vegetation

• Groundwater

• Drinking water

• Surface water

• Airborne particulate and radioiodine

• Goat milk

• Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmental gamma radiation. The Environmental TLD program is also conducted by APS. The Arizona Radiation Regulatory Agency (ARRA) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by ARRA include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) deep wells. Offsite samples analyzed by ARRA include two (2) local resident wells. ARRA 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 2015. All references are specifically identified in Section 12. Overview The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of members of the public resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the 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 (e.g., 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 Section IV.B.2 of Appendix I to 10 CFR Part 50. 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 "Manmade" 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: occupations, 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 mrem. 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. The most significant contributor to radiation exposure from manmade sources is medical procedures. Diagnostic s-rays and nuclear medicine procedures, such as those that use iodine-131 or cesium-137, are examples of manmade 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 perform ionizing radiation dosimeter analyses. 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 2015 New Vegetation Sample Location The 2015 Land Use Census results have identified a new Radiological Environmental Monitoring Program (REMP) garden sample location. Per the Land Use Census procedure, 74RM-0EN07 Revision 14, a Condition Report shall be generated if a new sample location is identified that yields a 20% greater dose to an indicator location than current indicator locations. The new vegetation indicator location's calculated dose is 2.05E-01 mRem versus a criterion of 1.99E-01 mRem. This sampling location was included as supplemental data for 2015 and is included in the 2015 AREOR. This sampling location will be included in the REMP, beginning in 2016, as a required location as annotated in the ODCM, Revision 27.

Configuration of Air Sample Stations The PVNGS Annual Radiological Environmental Operating Report 2013, section 2.3 REMP Deviation/Abnormal Events Summary references Letter 218-03709-JLM and describes the lowering of Radiological Environmental Monitoring Program (REMP) air samples. An evaluation concludes the air sample locations should not be lowered due to measurement variation concerns (CRDR 3805133). In April 2013, CRDR 4385407 was generated to lower the air sample locations based on industrial safety issues. This modification was evaluated, determining the sampling height should be restored to ensure representative monitoring of effluents and the impact on the environment, as well as maintain historical sample continuity (CRDR 4567692).

The configurations of all the air sample monitoring stations were restored to meet the intent of NUREG 1301 and Radiological Assessment Branch Technical Position, Revision 1. Consideration should be given to incorporation of EPA Guidance For Network Design and Optimum Site Exposure For PM2.5 And PM10 and ASTM document Standard Guide for Choosing Locations and sampling Methods to Monitor Atmospheric Deposition at Non-Urban Locations (CRAI 4577972). Changing the configuration to meet these requirements led to placing the air sample collection point to outside of the instrument weather housing, by utilizing a gooseneck sample line extension. This allowed sampling at the pre-operational sample height. The restoration of the sampling height configuration was completed with objective evidence on 2/19/2015. 2.3 REMP Deviations/Abnormal Events Summary During calendar year 2015, there were eleven (11) deviations/abnormal events with regards to the monitoring program. Refer to Table 2-3 for more detail and any corrective actions taken. Seven (7) of the events involved air sample stations. Three (3) events were due to defective pump vanes which were discovered due to the failure of pumps following routine maintenance in which the pump vanes had been replaced. The defective vanes remaining in inventory were identified and pulled from the supply and replaced. One (1) of the events involved the validity of several samples being questioned due to water intrusion occurring following the placement of the sample heads outside of the housing. An evaluation conducted in conjunction with the vendor concluded that the samples were valid. To avoid unnecessary wear on the sampling equipment and to ensure public confidence in the air sampling portion of the program, the rain shields were upgraded. No other water intrusion events have happened since the rain shield upgrades. The final three (3) air sample events involved a disconnected suction tube at Site 35, dislodged sample cartage at Site 35, and a loss of power at Site 17A. All events have been evaluated and corrective measures have been taken when necessary to prevent recurrence. One (1) event was a missed LLD for La-150 for Site 49 drinking water. The missed LLD was attributed to a software malfunction. There was no detectable activity in this sample and the LLD that was achieved was well below the action level.

One (1) event was exceedance of the quarterly I-131 reporting level of 20 pCi/L. This occurred at Evaporation Pond 1C, fourth calendar quarter. The source is radiopharmaceutical I-131 that originates in the Phoenix sewage effluent that supplies makeup to the Reservoirs and Circulating Water system. This water is wasted to the Evaporation Ponds. This is not a plant effluent.

The final two (2) events involved environmental TLD locations, Site 10 and Site 49. Site 10 sampling stanchion was discovered to be missing; however, the TLD and housing were left, undamaged. Site 49 sampling stanchion was temporarily moved, approximately 20 feet, to avoid TLD damage or missing data during road construction in the area.

2.4 Ground Water 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 radiological 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 Arlington School 14A Air NNE2 371stAve. 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 ground water ONSITE Well 27ddc 58 ground water 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 #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 # AIR PARTICULATE MILK AIRBORNE RADIOIODINE VEGETATIONGROUNDWATER 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/AA63 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 17A sample pump lost power between 2/10/2015-2/17/2015. The air sample pump lost power during the sample period, resulting in the inability to determine the actual sample volume. Results for this sampling period found to be INVALID. Power restored and sample volume for the following sample period was VALID. Event documented through CR 16-04887 (Table 8-1 and Table 8-4 , Note 1) 2. Air Samples stations had water intrusion 2/24/2015-3/3/2015, 3/16/2015-3/23/2015, and 4/28/2015-5/5/2015. Air sample cartridges were found to have water intrusion following heavy rain, causing the technician to question the sample integrity. These events were documented through CR 15-00990 and 15-01374. An evaluation was completed to determine the ability of the sample cartridge to maintain efficiency under the documented conditions. Vendor verified that the efficiency test data representing the F&J long term scenario is applicable to the facts and circumstances which occurred in these events (EVAL 15-00990-001). Data is considered VALID and is included in this report (Table 8-1 and Table 8-4, Note 2) 3. Air Sample Site 35 cartridge found on ground 8/11/2015 Sample for Site 35 found dislodged from pump and lying on ground- sample determined to be INVALID for sample period 8/4/2015-8/11/2015. Event documented through CR 15-05977 (Table 8-2 and Table 8-5, Note 1). 4. Air Sample Site 35 found with suction tube disconnected on 10/28/2015. On 10/28/2015, technician found REMP Air Sample Site 35 with the suction tube disconnected. Filter appeared white/as new. Technician believed that the suction tube came loose during the previous sample change-out the week before.

Suction restored and pump flow verified. Sample determined to be INVALID for sample period 10/20/2015-10/28/2015. Event documented through CR 16-04924 (Table 8-2 and Table 8-5, Note 2). 5. Air Sample Pump found energized but not running at Site 15 and Site 40 on 11/23/2015. Technician found REMP Air Sample Pumps at Site 15 and Site 40 energized but not running. Pumps were replaced and confirmed to be satisfactory. Results for these samples found to be INVALID for sample period 11/17/2015-11/23/2015. Event documented through CR 16-04949 (Table 8-2 and Table 8-5, Note 3). Cause later determined to be due to pump vane failures limited to recent shipment of rebuild kits (CR 15-12551) 6. Air Sample Pump found energized but not running at Site 15 on 12/1/2015. Technician found REMP Air Sample Pump at Site 15 energized but not running. Pump was replaced and confirmed to be satisfactory. Results for these samples found to be INVALID for sample period 11/23/2015-12/1/2015. Event documented through CR 15-11875 (Table 8-2 and Table 8-5, Note 3). Cause later determined to be due to pump vane failures limited to recent shipment of rebuild kits (CR 15-12551)

7. Air Sample Pump found energized but not running at Site 15 on 12/15/2015. Technician found REMP Air Sample Pumps at Site 15 energized but not running. Pump was replaced and confirmed to be satisfactory. Results for these samples found to be INVALID for sample period 12/8/2015-12/15/2015. Event documented through CR 15-12551 and cause determined to be due to pump vane failures limited to recent shipment of rebuild kits (Table 8-2 and Table 8-5, Note 3). 8. Missed La-140 LLD for Site 49 Drinking Water Sample On Tuesday 11-24-15 the count-room detectors were not usable due to software (APEX) malfunction. This malfunction resulted in the inability to achieve the required LLD of 15 pCi/L for Site

49. The achieved LLD for Site 49 was <32 pCi/L with a reporting level of 200 pCi/L. This is the only exception for meeting LLDs in drinking water. This event was documented through CR 15-11873 and CR 16-05908 (Table 8-8, Note 1). 9. Evaporation Pond 1C exceeded 4th Quarter I-131 reporting level of 20 pCi/L resulting in a unity value of greater than 1.0 (one).

The quarterly tritium value 2341. Evaporation Pond 1C had an I-131 validated result greater than the ODCM Reporting Level. Low level tritium (2341+/-193 pCi/L) was detected in Evaporation Pond 1C, which is below the ODCM Reporting Level. If more than one radionuclide from the ODCM Reporting Level table is detected, a unity value calculation must be performed, The elevated I-131 concentrations, originating from radiopharmaceuticals in Phoenix Influent (CRDR 4568037), accounted for 93% of the unity value. This occurrence is documented through CR 16-05005 (Table 8-10). 10. Site 49 TLD Sample Stanchion relocated due to construction. Technician observed fresh grading in apparent preparation for future road work had been done around the sample stanchion on 9-24-15, while performing the quarterly change-out of environmental TLDs. The technician moved the stanchion ~20 feet to prevent inadvertent damage or loss of the TLDs. The TLD stanchion was returned to original location during the next quarterly TLD change-out. This event and follow-up actions were documented through CR 15-08047 and AI 15-08047-004. 11. Site 10 TLD Sample Stanchion missing. Technician found the Site 10 TLD field holder, still intact and sealed, lying on the ground near the sample site, on 9-24-15 while performing the quarterly REMP environmental TLD change-out. The pipe and concrete were gone and could not be located. This event and evaluation were documented through CR 15-08042 and EVAL 15-08042-002. 12. Site 50 TLDs missing due to vandalism. The two TLDs used for monitoring location 50 were missing at the time of exchange due to vandalism. Processing results appear normal and are consistent with historical readings. In addition, no neutron exposure was measured at any of the monitored locations. Intralaboratory comparisons indicated an average bias of 0.001, with a standard deviation of 2.4 percent.

This event was documented through Correspondence Letter 218-03835-JER

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 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 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 Reclamation Facility (WRF), 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 I-131. Particulate filters were composited quarterly, by location, and analyzed for gamma emitting radionuclides.

3.5 Sludge and Sediment Sludge samples were obtained weekly from the WRF waste centrifuge (whenever the plant was operational) and analyzed for gamma emitting radionuclides. Cooling tower sludge was analyzed for gamma emitting radionuclides prior to disposal in the WRF 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 an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides. 4.2 Airborne Radioiodine The charcoal cartridge is counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for I-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. 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.

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. 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 an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides. 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 (HNO3) 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.

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. For reference, a priori LLDs are indicated at the top of data tables for samples having required LLD values. 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 2 counting 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.

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/m3) 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 10a 1 0.04b49 Cs-134 9 1 0.003b47 Cs-137 10 1 0.003b 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 m3, 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, Rev. 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 2015, 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 Range Acceptable? ID Type Value** Value Error E11152 Tritium H-3 pCi/L 1.26E+04 1.21E+04 3.55E+02 34 0.96 0.75-1.33YES E11153 Gamma Water I-131 pCi/L 9.67E+01 9.60E+01 8.56E+00 11 0.99 0.60-1.66YES Ce-141 pCi/L 1.39E+02 1.59E+02 1.02E+01 16 1.14 0.75-1.33YES Cr-51 pCi/L 3.66E+02 2.69E+02 4.74E+01 6 0.73 0.50-2.00YES Cs-134 pCi/L 1.26E+02 1.14E+02 7.80E+00 15 0.90 0.60-1.66YES Cs-137 pCi/L 1.67E+02 1.76E+02 1.22E+01 14 1.05 0.60-1.66YES Co-58 pCi/L 1.80E+02 1.90E+02 1.20E+01 16 1.06 0.75-1.33YES Mn-54 pCi/L 1.59E+02 1.75E+02 1.19E+01 15 1.10 0.60-1.66YES Fe-59 pCi/L 1.95E+02 1.79E+02 2.19E+01 8 0.92 0.60-1.66YES Zn-65 pCi/L 2.99E+02 3.01E+02 2.32E+01 13 1.01 0.60-1.66YES Co-60 pCi/L 3.28E+02 3.27E+02 1.61E+01 20 1.00 0.75-1.33YES E11154 I-131 Cartridge I-131 pCi/ea 7.78E+01 8.31E+01 2.70E+00 31 1.07 0.75-1.33YES E11155 Gamma Filter Ce-141 pCi/ea 6.96E+01 6.93E+01 3.58E+00 19 1.00 0.75-1.33YES Cr-51 pCi/ea 1.83E+02 2.09E+02 1.87E+01 11 1.14 0.60-1.66YES Cs-134 pCi/ea 6.31E+01 5.23E+01 3.89E+00 13 0.83 0.60-1.66YES Cs-137 pCi/ea 8.34E+01 8.24E+01 5.60E+00 15 0.99 0.60-1.66YES Co-58 pCi/ea 8.99E+01 9.17E+01 6.05E+00 15 1.02 0.60-1.66YES Mn-54 pCi/ea 7.94E+01 8.66E+01 5.88E+00 15 1.09 0.60-1.66YES Fe-59 pCi/ea 9.75E+01 1.08E+02 1.00E+01 11 1.11 0.60-1.66YES Zn-65 pCi/ea 1.50E+02 1.78E+02 1.20E+01 15 1.19 0.60-1.66YES Co-60 pCi/ea 1.64E+02 1.78E+02 9.30E+00 19 1.09 0.75-1.33YES E11156 Gamma Milk I-131 pCi/L 1.42E+01 1.65E+01 1.98E+00 8 1.16 0.60-1.66YES Ce-141 pCi/L 1.80E+01 1.73E+01 2.77E+00 6 0.96 0.50-2.00YES Cr-51 pCi/L 4.75E+01 6.08E+01 1.06E+01 6 1.28 0.50-2.00YES Cs-134 pCi/L 1.63E+01 1.66E+01 1.72E+00 10 1.02 0.60-1.66YES Cs-137 pCi/L 2.16E+01 2.16E+01 2.35E+00 9 1.00 0.60-1.66YES Co-58 pCi/L 2.33E+01 2.37E+01 2.86E+00 8 1.02 0.60-1.66YES Mn-54 pCi/L 2.06E+01 2.04E+01 2.35E+00 9 0.99 0.60-1.66YES Fe-59 pCi/L 2.53E+01 2.53E+01 5.40E+00 5 1.00 0.50-2.00YES Zn-65 pCi/L 3.88E+01 4.79E+01 5.16E+00 9 1.23 0.60-1.66YES Co-60 pCi/L 4.26E+01 4.29E+01 3.25E+00 13 1.01 0.60-1.66YES Table 7.1 Interlaboratory Comparison Results (Continued) E11157 Beta Filter G. Beta pCi/ea 8.78E+01 9.90E+012.20E+00 45 1.13 0.75-1.33YES E11349 Gamma Filter Ce-141 pCi/ea 8.12E+01 8.06E+018.53E+00 9 0.99 0.60-1.66YES Cr-51 pCi/ea 2.05E+02 1.72E+024.44E+01 4 0.84 0.50-2.00YES Cs-134 pCi/ea 8.07E+01 6.54E+014.36E+00 15 0.81 0.60-1.66YES Cs-137 pCi/ea 9.71E+01 1.05E+021.34E+01 8 1.08 0.60-1.66YES Co-58 pCi/ea 1.00E+02 1.06E+021.22E+01 9 1.06 0.60-1.66YES Mn-54 pCi/ea 1.11E+02 1.33E+021.39E+01 10 1.20 0.60-1.66YES Fe-59 pCi/ea 8.60E+01 1.05E+021.01E+01 10 1.22 0.60-1.66YES Zn-65 pCi/ea 1.35E+02 1.64E+021.62E+01 10 1.21 0.60-1.66YES Co-60 pCi/ea 1.26E+02 1.31E+028.18E+00 16 1.04 0.75-1.33YES E11350 I-131 Cartridge I-131 pCi/ea 7.46E+01 7.23E+011.42E+01 5 0.97 0.50-2.00YES E11351 Beta Water G. Beta pCi/L 2.37E+02 2.73E+026.00E+00 46 1.15 0.75-1.33YES E11352 Beta Filter G. Beta pCi/ea 7.87E+01 8.73E+011.50E+00 58 1.11 0.80-1.25YES

• 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 Systems; Water Chemistry; Confirmatory Measurements" 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 Gross Beta RAD-101 g beta pCi/L 38.8 32.9 21.3 - 40.8 Acceptable Water Tritium RAD-103 H-3 pCi/L 20,700 21,300 18700 - 23400 Acceptable Water Gamma RAD-103 Ba-133 pCi/L 31 32.5 25.9 - 36.7 Acceptable Cs-134 pCi/L 58.1 62.3 50.6 - 68.5 Acceptable Cs-137 pCi/L 144 157 141 - 175 Acceptable Co-60 pCi/L 72.2 71.1 64.0 - 80.7 Acceptable Zn-65 pCi/L 139 126 113 - 149 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. Random errors are beyond the control of the analyst. 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, and 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 2015 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 0.016 to 0.059 pCi/m3. 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.

8.2 Airborne Radioiodine Table 8-4 and Table 8-5 present the quarterly radioiodine 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 radionuclides. 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 6.5 pCi/liter. The gross beta activity is attributable to natural (background) radioactive materials.

8.6 Ground Water Ground water 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 Ponds 1B, 1C, and 2A. The I-131 levels ranged from 18 pCi/L - 23 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 2341 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 WRF Centrifuge Waste Sludge Sludge samples were obtained from the WRF 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 WRF Influent. The concentration of I-131 ranged from "no detectable" to 937 pCi/kg.

Results for WRF centrifuge waste sludge can be found in Table 8-11. 8.8.2 Cooling Tower Sludge Sludge/sediment originating from the Unit 2 and Unit 3 Cooling Towers and Circulating Water canals was disposed of in the WRF sludge landfill during 2015. 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(%)Note130-Dec-146-Jan-150.0470.0560.0550.0530.0510.0570.0580.0580.0530.0570.0546.526-Jan-1513-Jan-150.0490.0540.0550.0500.0550.0570.0580.0550.0530.0540.0545.1 313-Jan-1520-Jan-150.0390.0400.0380.0340.0350.0380.0370.0390.0360.0380.0375.5420-Jan-1527-Jan-150.0320.0360.0380.0340.0320.0360.0340.0350.0330.0350.0355.1527-Jan-153-Feb-150.0260.0300.0270.0290.0280.0280.0340.0330.0280.0280.0298.3 63-Feb-1510-Feb-150.0370.0530.0450.0450.0450.0460.0490.0480.0430.0460.0469.2710-Feb-1517-Feb-150.0300.0320.0270.0310.028*0.0250.0300.0310.0310.0297.91817-Feb-1523-Feb-150.0480.0500.0460.0460.0470.0460.0450.0460.0460.0490.0473.1 924-Feb-153-Mar-150.0210.0200.0200.0210.0210.0200.0200.0180.0220.0210.0204.82103-Mar-1510-Mar-150.0320.0310.0330.0330.0330.0310.0340.0240.0300.0280.03110.21110-Mar-1516-Mar-150.0450.0460.0460.0470.0480.0480.0460.0410.0450.0500.0465.1 1216-Mar-1523-Mar-150.0370.0360.0360.0360.0370.0360.0350.0350.0340.0360.0362.321323-Mar-1531-Mar-150.0250.0250.0250.0260.0260.0260.0240.0250.0230.0270.0254.7Mean0.0360.0390.0380.0370.0370.0390.0380.0370.0370.0380.0382.6(control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note1431-Mar-157-Apr-150.0320.0340.0370.0340.0320.0380.0350.0340.0310.0370.0346.4157-Apr-1514-Apr-150.0260.0250.0240.0250.0260.0310.0240.0250.0250.0250.0267.5 1614-Apr-1521-Apr-150.0310.0280.0310.0320.0340.0310.0310.0290.0310.0290.0315.61721-Apr-1528-Apr-150.0240.0210.0220.0240.0220.0240.0240.0240.0220.0230.0234.91828-Apr-155-May-150.0290.0240.0280.0290.0310.0320.0310.0290.0290.0300.0298.02195-May-1512-May-150.0270.0230.0260.0260.0220.0280.0260.0240.0260.0230.0256.92012-May-1519-May-150.0190.0160.0180.0200.0160.0210.0160.0210.0220.0180.01911.6 2119-May-1526-May-150.0330.0290.0310.0300.0280.0290.0300.0270.0310.0290.0305.82226-May-152-Jun-150.0370.0380.0410.0370.0230.0430.0350.0400.0320.0250.03519.1232-Jun-159-Jun-150.0310.0320.0310.0320.0290.0320.0300.0330.0300.0300.0313.2 249-Jun-1516-Jun-150.0390.0380.0360.0380.0400.0380.0360.0350.0370.0350.0374.52516-Jun-1523-Jun-150.0490.0430.0450.0430.0540.0370.0460.0430.0460.0460.0459.82623-Jun-1529-Jun-150.0430.0360.0380.0380.0340.0450.0380.0280.0390.0350.03712.7Mean0.0320.0300.0310.0310.0300.0330.0310.0300.0310.0300.0313.6Note:1. Sample for Site 17-A INVALID due to power loss from line out2. Weekly samples initially invalidated due to water intrusion; data provided as INFO ONLY. Evaluation 15-00990-001- Vendor confirmed sample media not compromised- conditions within testing criteria. Data included in this report.ODCM required samples denoted by *units are pCi/m31st Quarter2nd Quarter Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note2729-Jun-157-Jul-150.0420.0450.0410.0420.0380.0350.0360.0440.0380.0420.0408.1287-Jul-1514-Jul-150.0340.0350.0330.0330.0320.0330.0310.0340.0340.0350.0334.42914-Jul-1521-Jul-150.0290.0240.0290.0240.0240.0240.0230.0290.0250.0220.02510.9 3021-Jul-1529-Jul-150.0230.0210.0280.0230.0220.0200.0250.0290.0180.0210.02314.83129-Jul-154-Aug-150.0320.0330.0280.0250.0340.0270.0310.0280.0230.0270.02912.6324-Aug-1511-Aug-150.0340.0360.0330.0330.0360.0340.0310.037*0.0280.0348.41 3311-Aug-1518-Aug-150.0290.0330.0300.0310.0320.0330.0320.0310.0310.0300.0314.03418-Aug-1525-Aug-150.0310.0200.0270.0280.0270.0240.0230.0270.0300.0260.02612.13525-Aug-151-Sep-150.0340.0320.0340.0350.0330.0310.0340.0330.0350.0280.0336.1 361-Sep-158-Sep-150.0360.0350.0290.0310.0320.0320.0280.0250.0280.0230.03013.6378-Sep-1515-Sep-150.0340.0340.0390.0310.0310.0350.0300.0350.0360.0350.0347.63815-Sep-1522-Sep-150.0240.0240.0250.0260.0280.0250.0240.0280.0240.0260.0256.13922-Sep-1529-Sep-150.0470.0550.0490.0500.0530.0320.0460.0490.0470.0430.04713.3Mean0.0330.0330.0330.0320.0320.0300.0300.0330.0310.0300.032#REF!(control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteRSDWeek #DATEDATE46A*7A14A*15*17A2129*3540*Mean(%)Note4029-Sep-156-Oct-150.0330.0420.0420.0380.0450.0410.0340.0390.0380.0390.0399.4416-Oct-1513-Oct-150.0340.0340.0340.0290.0310.0310.0290.0350.0310.0310.0327.04213-Oct-1520-Oct-150.0440.0430.0420.0370.0480.0430.0340.0410.0430.0330.04111.24320-Oct-1528-Oct-150.0470.0530.0520.0460.0540.0530.0390.048*0.0480.0499.524428-Oct-153-Nov-150.0510.0470.0530.0410.0570.0470.0390.0520.0430.0430.04712.5 453-Nov-159-Nov-150.0350.0340.0280.0290.0350.0370.0270.0290.0270.0270.03112.5469-Nov-1517-Nov-150.0390.0350.0360.0360.0380.0360.0330.0340.0370.0360.0365.54717-Nov-1523-Nov-150.0330.0400.0330.033*0.02540.0330.0330.0320.033*0.02280.0347.53 4823-Nov-151-Dec-150.0430.0420.0440.042*0.0450.0400.0450.0440.0400.0434.33491-Dec-158-Dec-150.0590.0580.0560.0550.0560.0570.0570.0590.0570.0580.0572.5508-Dec-1515-Dec-150.0460.0280.0460.041*0.0430.0460.0400.0450.0410.04213.435115-Dec-1521-Dec-150.0420.0390.0390.0370.0380.0360.0390.0360.0360.0370.0385.65221-Dec-1528-Dec-150.0260.0300.0280.0280.0280.0260.0260.0240.0220.0240.0269.1Mean0.0410.0400.0410.0380.0430.0410.0370.0390.0380.0380.0405.0Annual Average0.03550.03550.03570.03450.03530.03550.03410.03500.03400.03380.03497.9964min 6A0.0157min 7a0.018min 17A0.020all ind min0.016all ind mean0.034max 6A0.0576max 7a0.056max 17A0.057all ind max0.059Note:1. Sample for Site 35 found dislodged from pump and lying on ground- sample determined to be INVALID (CR 15-05977)2. Sample for Site 35 found with suction tube disconnected Filter showed no signs of sample collection (CR 16-04924)3. Air Sample Pump found energized but not running at Site 15 and Site 40 (11/23/2015), and at Site 15 (11/15/2015 and 12/15/2015). Samples invalid (CR 16-04949, 15-11875, and 15-12551). Problem identified as faulty vane kits and corrected.ODCM required samples denoted by *units are pCi/m33rd Quarter4th Quarter Table 8-3 Gamma in Air Filter Composites (control)QUARTERSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteENDPOINTNUCLIDE46A*7A14A*15*17A2129*3540*31-Mar-15Cs-134<0.0019<0.0028<0.0023<0.0046<0.0020<0.0021<0.0017<0.0028<0.0021<0.0033Cs-137<0.0029<0.0028<0.0025<0.0040<0.0020<0.0011<0.0023<0.0043<0.0020<0.004029-Jun-15Cs-134<0.0010<0.0042<0.0041<0.0019<0.0034<0.0022<0.0027<0.0023<0.0029<0.0021Cs-137<0.0033<0.0027<0.0044<0.0016<0.0046<0.0023<0.0047<0.0016<0.0041<0.002329-Sep-15Cs-134<0.0027<0.0024<0.0043<0.0011<0.0043<0.0034<0.0043<0.0039<0.0030<0.0018Cs-137<0.0041<0.0038<0.0053<0.0009<0.0053<0.0028<0.0062<0.0028<0.0032<0.006128-Dec-15Cs-134<0.0010<0.0007<0.0035<0.0061*<0.0031<0.0019<0.0025<0.0028**<0.0030<0.0011Cs-137<0.0048<0.0009<0.0044<0.0063*<0.0033<0.0016<0.0031<0.0024**<0.0048<0.0009* Site 15- two weeks invalid. Filters and volumes added into Quarterly stack** Site 35 (10/28/2015) Invalid - tube came off inside box. Vol of 1 m^3 and filter included in compositODCM required samples denoted by *units are pCi/m3 Table 8-4 Radioiodine in Air 1st - 2nd Quarter (control)STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note130-Dec-146-Jan-15<0.0279<0.0585<0.0556<0.0315<0.0523<0.0333<0.0558<0.0357<0.0636<0.024326-Jan-1513-Jan-15<0.0284<0.0669<0.0561<0.0196<0.0443<0.0248<0.0576<0.0313<0.0679<0.0244 313-Jan-1520-Jan-15<0.0548<0.0526<0.0320<0.0493<0.0376<0.0625<0.0509<0.0295<0.0680<0.0376421-Jan-1527-Jan-15<0.0626<0.0572<0.0497<0.0594<0.0345<0.0446<0.0683<0.0530<0.0529<0.0532527-Jan-153-Feb-15<0.0183<0.0336<0.0682<0.023<0.0280<0.0668<0.0280<0.0501<0.0246<0.042263-Feb-1510-Feb-15<0.0320<0.0567<0.0544<0.0621<0.0689<0.0273<0.0588<0.0341<0.0657<0.0200 710-Feb-1517-Feb-15<0.0218<0.0329<0.0539<0.0295<0.0534*<0.0227<0.0552<0.0263<0.04611817-Feb-1523-Feb-15<0.0636<0.0640<0.0507<0.0079<0.0630<0.0234<0.0467<0.0294<0.0696<0.0344923-Feb-153-Mar-15<0.0195<0.0449<0.0473<0.0266<0.0370<0.0277<0.0489<0.0234<0.0598<0.02422103-Mar-1510-Mar-15<0.0628<0.0639<0.0312<0.0486<0.0396<0.0449<0.0379<0.0466<0.0304<0.06641110-Mar-1516-Mar-15<0.0261<0.0344<0.0399<0.0229<0.0406<0.0281<0.0389<0.0417<0.0283<0.03221216-Mar-1523-Mar-15<0.0346<0.0676<0.0418<0.0251<0.0578<0.0300<0.0457<0.0253<0.0457<0.03212 1323-Mar-1531-Mar-15<0.0377<0.0369<0.0285<0.0343<0.0222<0.0519<0.0233<0.0441<0.0291<0.0380(control)required LLD <0.070STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note1431-Mar-157-Apr-15<0.0317<0.0321<0.0376<0.0293<0.0551<0.0372<0.0545<0.0319<0.0670<0.0235157-Apr-1514-Apr-15<0.0239<0.0287<0.0548<0.0398<0.0549<0.0299<0.0550<0.0327<0.0296<0.06731614-Apr-1521-Apr-15<0.0340<0.0328<0.0424<0.0284<0.0694<0.0378<0.0338<0.0306<0.0394<0.02991721-Apr-1528-Apr-15<0.0627<0.0305<0.0658<0.0266<0.0670<0.0255<0.0685<0.0295<0.0602<0.01961828-Apr-155-May-15<0.0281<0.0538<0.0458<0.0273<0.0548<0.0242<0.0557<0.0339<0.0674<0.03352195-May-1512-May-15<0.0346<0.0531<0.0419<0.0225<0.0416<0.0348<0.0491<0.0328<0.0647<0.0263 2012-May-1519-May-15<0.0125<0.0489<0.0591<0.0296<0.0339<0.0217<0.0669<0.0687<0.0277<0.01882119-May-1526-May-15<0.0395<0.0370<0.0664<0.0395<0.0614<0.0299<0.0626<0.0301<0.0441<0.03402226-May-152-Jun-15<0.0402<0.0450<0.0171<0.0376<0.0207<0.0550<0.0237<0.0562<0.0217<0.0602 232-Jun-159-Jun-15<0.0465<0.0477<0.0635<0.0640<0.0504<0.0359<0.0688<0.0554<0.0633<0.0661 249-Jun-1516-Jun-15<0.0443<0.0445<0.0586<0.0514<0.0367<0.0444<0.0307<0.0435<0.0288<0.05632516-Jun-1523-Jun-15<0.0345<0.0302<0.0318<0.0304<0.0334<0.0364<0.0346<0.0266<0.0272<0.03342623-Jun-1529-Jun-15<0.0437<0.0558<0.0466<0.0369<0.0664<0.0287<0.0387<0.0325<0.0490<0.0310Note:1. Sample for Site 17-A INVALID due to power loss from line outrequired LLD <0.0702. Weekly samples initially invalidated due to water intrusion; data provided as INFO ONLY. Evaluation 15-00990-001- Vendor confirmed sample media not compromised- conditions within testing criteria. Data included in this report.ODCM required samples denoted by *units are pCi/m31st Quarter2nd Quarter Table 8-5 Radioiodine in Air 3rd - 4th Quarter (control)0.070STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note2729-Jun-157-Jul-15<0.0231<0.0446<0.0375<0.0221<0.0590<0.0263<0.0274<0.0237<0.0466<0.0248287-Jul-1514-Jul-15<0.0334<0.0582<0.0685<0.0245<0.0510<0.0299<0.0699<0.0305<0.0505<0.01922914-Jul-1521-Jul-15<0.0353<0.0638<0.0422<0.0265<0.0651<0.0273<0.0562<0.0326<0.0392<0.0183 3021-Jul-1529-Jul-15<0.0602<0.0366<0.0435<0.0506<0.0475<0.0567<0.0521<0.0601<0.0522<0.0422 3129-Jul-154-Aug-15<0.0347<0.0496<0.0673<0.0354<0.0676<0.0341<0.0609<0.0258<0.0665<0.0226 324-Aug-1511-Aug-15<0.0211<0.0643<0.0355<0.0321<0.0386<0.0282<0.0323<0.0260*<0.066313311-Aug-1518-Aug-15<0.0302<0.0296<0.0178<0.0292<0.0229<0.0350<0.0386<0.0313<0.0331<0.0251 3418-Aug-1525-Aug-15<0.0275<0.0569<0.0619<0.0254<0.0419<0.0304<0.0690<0.0299<0.0520<0.0318 3525-Aug-151-Sep-15<0.0366<0.0374<0.0295<0.0364<0.0358<0.0296<0.0207<0.0187<0.0073<0.0323 361-Sep-158-Sep-15<0.0380<0.0196<0.0521<0.0378<0.0367<0.0289<0.0403<0.0379<0.0282<0.0370 378-Sep-1515-Sep-15<0.0579<0.0581<0.0123<0.0421<0.0112<0.0304<0.0440<0.0281<0.0336<0.03433815-Sep-1522-Sep-15<0.0282<0.0342<0.0558<0.0347<0.0341<0.0348<0.0390<0.0330<0.0447<0.0303 3922-Sep-1529-Sep-15<0.0532<0.0265<0.0123<0.0391<0.0610<0.0413<0.0537<0.0382<0.0265<0.0224(control)0.070STARTSTOPSiteSiteSiteSiteSiteSiteSiteSiteSiteSiteWeek #DATEDATE46A*7A14A*15*17A2129*3540*Note4029-Sep-156-Oct-15<0.0472<0.0278<0.0353<0.0347<0.0573<0.0382<0.05460.053<0.0404<0.0521416-Oct-1513-Oct-15<0.0358<0.0223<0.0481<0.0312<0.0387<0.0269<0.0513<0.0370<0.0320<0.04114213-Oct-1520-Oct-15<0.0233<0.0468<0.0402<0.0261<0.0386<0.0183<0.0353<0.0255<0.0428<0.0385 4320-Oct-1528-Oct-15<0.0370<0.0376<0.0321<0.0359<0.0301<0.0223<0.0332<0.0387*<0.02752 4428-Oct-153-Nov-15<0.0338<0.0411<0.0683<0.0384<0.0651<0.0481<0.0558<0.0362<0.0206<0.0307 453-Nov-159-Nov-15<0.0578<0.0532<0.0517<0.0277<0.0388<0.0453<0.0358<0.0559<0.0356<0.0.296469-Nov-1517-Nov-15<0.0206<0.0220<0.0287<0.0247<0.0562<0.0240<0.0296<0.0263<0.0223<0.02824717-Nov-1523-Nov-15<0.0315<0.0427<0.0363<0.0268*<0.0399<0.0289<0.0379<0.0366*3 4823-Nov-151-Dec-15<0.0346<0.0408<0.0122<0.0579*<0.0334<0.0420<0.0492<0.0425<0.0492<0.03353491-Dec-158-Dec-15<0.0429<0.0221<0.0421<0.0294<0.0348<0.0487<0.0240<0.0517<0.0292<0.0235508-Dec-1515-Dec-15<0.0302<0.0261<0.0553<0.0413*<0.0352<0.0303<0.0322<0.0263<0.0347<0.020835115-Dec-1521-Dec-15<0.0378<0.0351<0.0272<0.0392<0.0374<0.0222<0.0425<0.0083<0.0466<0.03685221-Dec-1528-Dec-15<0.0428<0.0340<0.0409<0.0265<0.0449<0.0492<0.0692<0.0450<0.0203<0.0316Note:1. Sample for Site 35 found dislodged from pump and lying on ground- sample determined to be INVALID (CR 15-05977)

2. Sample for Site 35 found with suction tube disconnected Filter showed no signs of sample collection (CR 16-04924)

3. Air Sample Pump found energized but not running at Site 15 and Site 40 (11/23/2015), and at Site 15 (11/15/2015 and 12/15/2015). Samples invalid (CR 16-04949, 15-11875, and 15-12551). Problem identified as faulty vane kits and corrected.ODCM required samples denoted by *units are pCi/m33rd Quarter4th Quarter Table 8-6 Vegetation units are pCi/kg, wet<60<60<80LOCATIONTYPEDATE COLLECTEDI-131Cs-134Cs-137LOCALRESIDENCE(Site #47)*Red Cabbage22-Jan-15<54<59<65Green Cabbage22-Jan-15<42<44<73Green Cabbage12-Feb-15<55<59<57Savory Cabbage12-Feb-15<39<41<34Savory Cabbage12-Mar-15<45<56<54COMMERCIALFARM(Site #62)*Green Cabbage22-Oct-15<59<44<62Green Cabbage20-Nov-15<42<42<75Green Cabbage10-Dec-15<50<31<62Lettus22-Jan-15<57<50<73Red Lettuce12-Feb-15<53<48<54Kale12-Mar-15<59<51<69Broccoli Greens16-Apr-15<42<58<63Swiss Chard16-Apr-15<39<59<52 Swiss Chard14-May-15<47<45<57Swiss Chard18-Jun-15<43<37<50Swiss Chard15-Jul-15<55<36<80 Basil12-Aug-15<48<54<48Basil23-Sep-15<54<48<70Lettus10-Dec-15<54<31<54LOCAL RESIDENCE (Site #51)**NONE AVAILABLE****NONE AVAILABLE**

• • NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**ODCM required samples denoted by ***NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**Vegetation 2015**NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**

• • NONE AVAILABLE****NONE AVAILABLE****NONE AVAILABLE**

Table 8-7 Milk SAMPLEDATE<1<15<18<60<15LOCATIONCOLLECTEDI-131Cs-134Cs-137Ba-140La-14022-Jan-15<1<0.8<0.9<3<1Local Resident12-Feb-15Goats12-Mar-15<1<0.8<0.9<3<1(Site #51)*16-Apr-15<1<0.8<0.9<3<114-May-15<1<0.8<1<3<118-Jun-15<1<0.8<0.9<3<115-Jul-15<1<0.8<0.9<3<112-Aug-15<1<0.8<1<3<0.923-Sep-15<1<1<1<4<1.608-Oct-15<1<0.7<0.8<3<120-Nov-15<1<0.8<0.9<3<110-Dec-15<1<0.8<1<3<115-Jan-1520-Feb-15<1<0.8<1<3<124-Mar-15<1<0.8<1<3<1Local Resident23-Apr-15<1<0.8<1<3<1Goats21-May-15<1<0.8<1<3<1(Site #53)*19-Jun-15<1<0.8<1<3<123-Jul-15<1<0.8<1<3<127-Aug-15<1<0.8<1<3<0.917-Sep-15<1<0.6<1<3<1 22-Oct-15<1<0.9<1<4<1.520-Nov-15<1<0.8<1<3<110-Dec-15<1<1<1<3<115-Jan-15<1<0.8<1<3<1Local Resident12-Feb-15<1<0.8<1<3<1Goats12-Mar-15<1<0.7<0.9<3<1(Site #54)09-Apr-15<1<0.8<1<3<107-May-15<1<0.8<1<3<111-Jun-15<1<0.8<1<3<0.909-Jul-15<1<0.8<1<3<0.913-Aug-15<1<0.8<0.9<3<118-Sep-15<1<0.7<0.8<3<108-Oct-15<1<0.6<0.7<3<112-Nov-15<1<0.8<0.9<3<1 10-Dec-15<1<0.8<0.9<3<1**No Sample Available: newborn goats**ODCM required samples denoted by *units are pCi/liter**No Sample Available**

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 BetaNote27-Jan-15<10<9<17<12<24<12<16<10<9<11<30<15<3.3323-Feb-15<12<10<24<10<29<9<16<10<9<10<41<14<3.0931-Mar-15<10<9<18<13<30<10<15<8<10<10<26<11<3243.632.1128-Apr-15<12<9<21<10<25<11<17<11<8<12<41<153.712.02LOCAL26-May-25<11<14<30<13<21<13<18<12<14<13<44<13<3.42RESIDENCE29-Jun-15<12<10<20<14<25<11<20<10<9<13<32<15<324<3.35(Site #48) *29-Jul-15<13<15<27<12<30<13<21<14<14<8<41<126.091.9025-Aug-15<10<8<16<8<19<7<16<9<10<10<32<123.651.9629-Sep-15<7<7<15<8<16<8<14<7<6<7<25<15<3283.651.9727-Oct-15<3<3<7<4<7<4<6<4<3<4<15<104.261.8423-Nov-15<9<8<16<11<20<11<16<6<7<9<19<93.961.8328-Dec-15<5<5<8<5<11<5<9<5<4<5<15<10<3343.171.8727-Jan-15<8<8<15<8<15<10<12<9<6<9<32<155.241.6523-Feb-15<11<15<25<13<30<13<22<12<12<13<43<145.341.4931-Mar-15<11<12<22<13<30<11<20<10<10<13<38<15<3194.241.5228-Apr-15<13<12<22<11<29<14<23<12<12<12<45<155.341.55LOCAL26-May-25<11<11<20<10<24<13<17<11<11<13<37<153.421.56RESIDENCE29-Jun-15<13<13<21<11<25<10<18<10<12<12<34<15<3234.281.50(Site #55)29-Jul-15<11<8<17<12<19<10<17<9<10<11<31<153.491.4825-Aug-15<9<11<22<13<25<11<19<10<10<9<36<153.871.4829-Sep-15<8<9<14<7<17<9<14<7<7<9<26<15<3284.411.5628-Oct-15<5<5<10<6<13<5<8<6<5<6<18<154.141.6323-Nov-15<10<10<21<10<21<10<17<9<9<12<33<96.051.5828-Dec-15<10<10<19<10<20<8<17<10<8<11<32<15<335<2.38ODCM required samples denoted by *units are pCi/liter 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 BetaNote27-Jan-15<9<8<19<9<18<10<16<8<8<9<35<12<2.1723-Feb-15<13<15<27<15<26<14<22<14<11<11<46<142.001.2231-Mar-15<8<9<23<13<29<12<19<11<11<15<37<15<3202.291.3328-Apr-15<12<12<27<14<24<13<24<10<12<13<44<134.281.4126-May-25<9<13<27<13<27<12<20<12<12<14<34<123.481.50LOCAL29-Jun-15<8<9<16<12<26<9<14<10<10<9<29<15<324<2.08RESIDENCE29-Jul-15<9<11<17<11<22<9<13<9<9<8<33<152.731.40(Site #46) *25-Aug-15<10<15<19<15<27<15<21<13<12<15<43<4<2.0729-Sep-15<9<8<18<8<18<10<14<9<7<8<31<13<3283.271.4428-Oct-15<3<3<6<3<6<3<5<4<3<3<12<82.391.4423-Nov-15<7<9<19<7<14<10<16<8<7<9<26<123.171.3828-Dec-15<12<9<18<9<26<12<22<11<8<13<37<14<332<2.2427-Jan-15<8<9<19<12<25<10<14<9<9<9<31<15<2.1523-Feb-15<11<11<14<12<23<7<16<9<11<10<33<15<1.8331-Mar-15<10<8<19<15<19<12<18<9<10<10<41<15<319<2.0128-Apr-15<11<8<20<12<27<13<20<11<10<12<37<14<1.9826-May-25<11<10<25<12<25<11<17<9<11<12<37<13<2.18LOCAL29-Jun-15<10<11<21<13<27<12<21<10<10<13<42<15<325<2.07RESIDENCE29-Jul-15<11<8<17<10<23<10<16<9<9<10<34<14<2.08(Site #49) *25-Aug-15<12<13<18<8<25<15<22<14<10<13<44<11<2.0629-Sep-15<8<7<14<7<15<8<11<7<6<8<22<15<325<2.0928-Oct-15<5<6<10<6<11<6<9<6<5<6<23<14<2.1723-Nov-15<1<1<2<1<2<1<2<2<1<1<4*<323.531.40128-Dec-15<8<7<14<8<16<8<12<7<6<8<25<9<3333.041.46Note:1. LLD for La-140 not met due to APEX error. CR 15-11873ODCM required samples denoted by *units are pCi/liter Table 8-9 Groundwater units are pCi/literSAMPLEDATE<15<15<30<15<30<15<30<15<15<18<60<15<2000LOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium27-Jan-15<12<12<21<12<23<13<18<13<9<10<44<15<316WELL 27ddc28-Apr-15<13<14<28<14<24<14<23<11<11<13<35<15<313(Site #57)*28-Jul-15<11<11<23<15<23<14<19<13<12<13<45<13<32427-Oct-15<5<5<12<6<14<6<8<6<5<6<20<15<32827-Jan-15<10<11<24<12<25<12<13<12<10<12<41<15<319WELL 34abb28-Apr-15<10<9<22<11<25<10<17<10<9<10<31<15<315(Site #58)*28-Jul-15<12<11<23<12<19<10<18<12<10<10<40<15<32127-Oct-15<4< 3<7<4<9<5<7<4<4<4<16<13<325ODCM required samples denoted by

• Table 8-10 Surface Water 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-140Tritium45 ACRE*27-Jan-15<11<9<20<11<22<12<191910<10<12<41<15<321RESERVOIR28-Apr-15<13<12<25<12<27<11<20<12<10<12<36<15<324(Site #61)

• 28-Jul-15<10<10<16<11<19<10<16137<9<10<35<15<32927-Oct-15<5<5<13<6<12<5<9<7<5<5<20<14<33085 ACRE*27-Jan-15<11<11<26<11<21<11<211412<10<12<44<14<327RESERVOIR28-Apr-15<10<9<19<15<23<9<17<12<10<14<33<12<338(Site #60) * *28-Jul-15<12<11<23<13<22<12<181911<10<13<39<15<33027-Oct-15<5<5<9<5<10<5<844<4<5<19<14<328EVAP POND 127-Jan-15<8<9<25<13<30<11<16<11<9<12<37<131156222(Site #59) *28-Apr-15<11<10<26<10<29<11<21<11<11<13<43<141415216CELL 1A28-Jul-15<13<14<22<15<30<12<17<12<12<12<38<12118121427-Oct-15<8<6<15<8<17<7<12<7<6<8<25<81337220CELL 1B27-Jan-15<10<12<25<10<21<11<18<11<11<9<38<14<338*4/28/2015<11<11<22<10<26<12<211811<11<11<44<1592620628-Jul-15<11<11<25<15<26<11<15<9<8<11<33<12107021027-Oct-15<11<9<21<12<17<11<21<11<11<12<44<11748192CELL 1C27-Jan-15<13<14<28<15<30<13<20<11<10<14<37<13<33728-Apr-15<13<12<27<15<28<13<22<10<11<15<39<1543319828-Jul-15<9<11<28<13<30<10<20<12<9<13<36<10461199*10/27/2015<7<8<18<10<19<8<14238<7<9<28<112341193*Recounted and averagedODCM required samples denoted by *units are pCi/liter Table 8.10 Surface Water EVAP POND 227-Jan-15<12<11<26<13<25<13<21<13<11<11<38<15456209(Site #63) *28-Apr-15<11<8<23<11<30<12<18<10<10<14<37<10636201CELL 2A*28-Jul-15<12<13<27<12<30<13<201410<10<13<38<13716+/-20527-Oct-15<4<4<9<5<9<5<7<5<4<5<17<7541205CELL 2B27-Jan-15<14<12<29<14<30<13<21<13<10<13<40<1288921828-Apr-15<10<8<20<13<30<11<18<12<10<10<34<1567820228-Jul-15<11<10<22<12<26<10<17<11<9<10<39<1562420427-Oct-15<4<4<10<7<12<6<10<5<5<6<23<10537205EVAP POND 327-Jan-15<12<12<29<13<26<11<19<13<10<12<41<15912217(Site #64) *28-Apr-15<12<11<28<13<30<12<16<11<10<12<42<111014208CELL 3A28-Jul-15<12<11<24<13<30<11<23<11<10<14<36<1480920827-Oct-15<6<6<13<7<15<6<10<6<6<7<22<15745208CELL 3B27-Jan-15<11<9<22<12<24<10<18<10<9<11<37<1582421528-Apr-15<11<11<27<14<30<11<19<10<10<13<46<1543519628-Jul-15<10<9<23<12<30<9<18<10<11<12<33<1279320827-Oct-15<8<7<18<9<22<8<13<7<7<9<26<15819210*Recounted and averagedODCM required samples denoted by *units are pCi/liter Table 8.10 Surface Water SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium **6-Jan-15<12<10<23<15<23<11<1819 9<10<11<36<1313-Jan-15<15<11<23<12<27<9<1818 12<10<12<36<1320-Jan-15<11<11<19<12<30<9<2115 7<10<12<40<1427-Jan-15<12<8<24<15<27<13<223311<10<11<39<15<3313-Feb-15<11<12<24<15<23<13<164511<10<13<42<1010-Feb-15<13<12<23<11<29<11<2148<10<11<36<1217-Feb-15<12<12<30<15<22<14<214013<12<11<44<1323-Feb-15<9<9<19<12<20<12<184812<9<11<40<15<3443-Mar-15<11<10<18<15<24<9<203612<10<12<33<1310-Mar-15<10<13<21<12<27<12<204213<10<10<38<1216-Mar-15<11<10<19<10<17<12<196714<9<11<34<1423-Mar-15<11<11<25<13<30<9<184611<9<11<34<1231-Mar-15<11<8<23<11<27<10<223912<8<11<33<15<342WRF7-Apr-15<11<9<21<12<22<10<164312<10<12<31<12 INFLUENT14-Apr-1521-Apr-1528-Apr-15<11<11<22<10<19<9<18<11<10<10<34<14<3265-May-15<11<12<26<13<28<12<191811<11<14<35<1512-May-15<13<12<24<11<29<13<18189<11<13<39<819-May-15<11<15<21<13<23<14<19<12<13<12<47<1526-May-15<9<10<27<11<26<10<16129<10<11<35<15<3292-Jun-15<12<8<18<14<19<10<181711<9<11<40<159-Jun-15<11<10<28<11<29<12<18269<10<11<38<1316-Jun-15<13<13<25<13<26<13<203314<12<13<38<1523-Jun-15<8<9<23<10<23<9<16119<9<11<37<1529-Jun-15<11<10<20<11<26<9<151710<10<10<29<15<3347-Jul-15<12<13<27<15<25<13<211810<10<15<42<1514-Jul-15<12<11<28<14<30<14<23249<11<13<45<1521-Jul-15<9<10<20<13<24<9<192011<8<13<36<15** monthly compositeNO SAMPLE- WRF OUTAGEODCM required samples denoted by *units are pCi/literNO SAMPLE- WRF OUTAGE Table 8.10 Surface Water 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-140Tritium **Note28-Jul-15<10<13<20<12<30<14<203011<11<13<34<13<3324-Aug-15<11<9<22<13<30<10<182510<10<11<38<1311-Aug-15<12<14<25<14<29<15<221213<12<15<48<1418-Aug-15<12<13<17<15<28<10<25<12<12<12<37<15 25-Aug-15<12<14<16<15<21<12<20<12<11<12<32<141-Sep-15<13<11<27<15<29<13<22<13<12<13<42<98-Sep-15<8<8<17<9<19<8<1496<8<8<29<24115-Sep-15<6<6<11<6<12<6<10<6<6<6<20<822-Sep-15<1<1<2<1<2<1<293<1<1<6*<13<33429-Sep-15<6<6<14<7<13<6<10176<6<6<22<10<3416-Oct-15<9<7<17<8<18<8<16<239<8<10<32<1013-Oct-15<7<6<13<6<14<7<1175<5<8<20<10WRF20-Oct-15 INFLUENT27-Oct-15<7<7<13<7<13<7<10148<6<7<26<14<3383-Nov-15<4<4<8<3<8<4<643<3<4<11<49-Nov-15<9<7<13<11<15<11<1756<7<11<35<1217-Nov-15<6<6<11<6<16<6<1186<5<6<20<723-Nov-15<3<3<6<2<5<3<5166<2<3<14<158<33611-Dec-15<6<6<12<5<9<5<10<7<4<5<20<148-Dec-15<9<9<16<10<18<9<13<8<6<11<24<9*12/15/2015<7<6<11<7<12<6<1294<6<7<20<7C21-Dec-15<7<8<14<9<15<6<1277<6<6<21<1128-Dec-15<3<3<6<4<7<4<6154<3<4<11<6<346*Recounted and averaged1. LLD for La-140 not met due to APEX software issue documented in CR 15-11873. WRF Influent source is Phoenix Sewage; samples taken prior to interface with plant. Not ODCM sample location; reported for trending.ODCM required samples denoted by *units are pCi/liter** monthly compositeNO SAMPLE- WRF OUTAGE Table 8.10 Surface Water SAMPLEDATELOCATIONCOLLECTEDMn-54Co-58Fe-59Co-60Zn-65Nb-95Zr-95I-131Cs-134Cs-137Ba-140La-140Tritium6-Jan-1513-Jan-1520-Jan-15 27-Jan-15<8<9<18<12<25<11<16<10<9<11<33<15<3313-Feb-15<13<15<29<15<28<12<20<10<12<13<38<12<36210-Feb-15<13<11<29<11<30<12<23<10<10<12<47<14<36317-Feb-15<10<13<23<12<24<13<19<11<11<13<37<1454221523-Feb-15<14<12<26<11<30<14<19<10<12<12<40<133622193-Mar-15<11<12<19<7<29<12<18<10<11<13<31<1548320810-Mar-15<11<14<21<11<25<12<22<10<9<15<37<1451521216-Mar-15<13<11<26<15<28<14<21<10<10<13<43<12569+/-21023-Mar-15<12<12<22<13<24<11<15<11<11<10<30<1541621331-Mar-157-Apr-1514-Apr-1521-Apr-15 28-Apr-155-May-15<10<13<18<15<22<13<23<11<10<12<50<15<34212-May-1519-May-15<7<7<19<10<19<7<14<7<7<9<32<1243320827-May-15<10<9<19<10<24<11<17<10<9<12<34<12<3432-Jun-159-Jun-1516-Jun-1523-Jun-15 29-Jun-15**EMPTY****EMPTY****EMPTY**units are pCi/literODCM required samples denoted by ***EMPTY****EMPTY**

• • EMPTY****EMPTY****EMPTY**SEDIMENTATION BASIN #2**EMPTY****EMPTY****EMPTY****EMPTY****EMPTY****EMPTY**

Table 8.10 Surface Water 7-Jul-1514-Jul-1521-Jul-15<14<14<25<13<20<15<19<11<10<10<46<3<353*7/28/2015<10<9<20<12<24<11<18<9<9<11<36<15<3484-Aug-15<10<10<17<14<24<10<21<9<11<11<37<15<34111-Aug-1518-Aug-15 22-Sep-151-Sep-15 8-Sep-1515-Sep-15 22-Sep-1529-Sep-156-Oct-1513-Oct-15 20-Oct-15 27-Oct-153-Nov-159-Nov-1617-Nov-15 23-Nov-151-Dec-15 8-Dec-1515-Dec-15 21-Dec-15 28-Dec-15* Duplicate on Gamma only; results avereraged**EMPTY****EMPTY****EMPTY**units are pCi/liter**EMPTY****EMPTY**

• • EMPTY**

• • EMPTY**

• • EMPTY**SEDIMENTATION BASIN #2**EMPTY****EMPTY****EMPTY****EMPTY**

• • EMPTY****EMPTY****EMPTY**

• • EMPTY**

• • EMPTY**

• • EMPTY****EMPTY****EMPTY****EMPTY****EMPTY**

• • EMPTY**ODCM required samples denoted by

• Table 8-11 Sludge/Sediment SAMPLEDATE<6,000<150<180LOCATIONCOLLECTEDI-131Cs-134Cs-137In-1116-Jan-15167 81<122<10713-Jan-15374 149<108<13620-Jan-15296 122<98<8327-Jan-15354148<125<1733-Feb-15461140<104<80WRF10-Feb-15875186<103<110CENTRIFUGE17-Feb-15441133<103<123WASTE SLUDGE23-Feb-15405181<102<1763-Mar-15457178<147<14010-Mar-15507165<101<12516-Mar-15377119<96<14023-Mar-15538146<117<14131-Mar-15526139<111<1057-Apr-15588163<149<16714-Apr-1521-Apr-1528-Apr-15265155<146<1715-May-15None Detected<143<9812-May-15399150<150<16219-May-15229115<96<12826-May-15None Detected<101<1692-Jun-15344131<136<1589-Jun-15166131<146<18016-Jun-15396154<28<16123-Jun-15937193<117<10029-Jun-15686203<143<1647-Jul-15635152<105<13214-Jul-15311122<102<11321-Jul-15512127<84<12728-Jul-15772192<128<1754-Aug-15680149<80<7811-Aug-15475140<117<8218-Aug-15487123<107<29ODCM required samples denoted by *units are pCi/kg, wetNO SAMPLE- WRF OUTAGENO SAMPLE- WRF OUTAGE Table 8.11 Sludge/Sediment SAMPLEDATELOCATIONCOLLECTEDI-131Cs-134Cs-137In-11125-Aug-15284133<145<1691-Sep-15368119<68<1148-Sep-15399103<42<5215-Sep-15586143<79<12022-Sep-15540178<149<173WRF29-Sep-15569144<146<168CENTRIFUGE6-Oct-15431146<116<151WASTE SLUDGE13-Oct-15661184<117<13220-Oct-1527-Oct-153-Nov-15None Detected<122<1069-Nov-15175116<84<10317-Nov-15409138<113<17724-Nov-15296150<82<301-Dec-15452155<99<1748-Dec-15None Detected<102<13715-Dec-15267150<134<12821-Dec-1516076<68<6929-Dec-1534184<63<47SEDIMENTATION BASIN #2ODCM required samples denoted by *units are pCi/kg, wetNO SAMPLE- WRF OUTAGENO SAMPLE- WRF OUTAGENo Sample Table 8.11 Sludge/Sediment Cooling Tower Sludge Unit Cycle Approximate Volume (yd3) Isotope Activity Range (pCi/g) Sample Type U3R17 375 All principal gamma emitters <MDA Towers/Canal Sludge U3R18 295 All principal gamma emitters Cs-137/ 2.48 E-1 Towers/Canal Sludge U2R19 338 All principal gamma emitters <MDA Towers/Canal Sludge Note: The Cs-137 identified in U3R18 cooling tower sludge is atypical and meets ARRA SAL 7-368 criteria for onsite landfill disposal. ARRA analysis found all samples to meet criteria for disposal in the onsite landfill per SAL 7-368. Table 8-12 Hard -To-Detect Radionuclide Results Hard-To-Detect Radionuclide (pCi/Liter) Sample Location Well numberSample DateC-14 Fe-55Ni-63Sr-90Unit 1 (outside RCA)APP-12 12/22/2015 <60.2 <145<3.62<1.92Unit 2 (inside RCA)H0A 12/31/2015 <58.3 <148<3.90<1.99Unit 3 (inside RCA)H2 12/29/2015 <58.7 <162<3.58<1.90

10. Land Use Census 10.1. Introduction In accordance with the PVNGS ODCM, Section 6.2, the annual Land Use Census was performed in June 2015. 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 Land Use Census 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 Nearest Resident There was no change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.248 mRem. Milk Animal There was no change in milk animal status from the previous year. Dose calculations indicated the highest dose to be 0.399 mRem. Vegetable Gardens One garden was added to the ODCM as a required sampling location. This location was identified as part of the 2014 Land Use Census; however, due to the garden not meeting the required size of 500 square feet, it was sampled as a Supplemental sample. In 2015, the garden was identified as meeting the minimum 500 square foot size and added to the ODCM. Dose calculations indicated the highest dose to be 0.321 mRem. See Table 10-1for 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 2014 N 1.55 3.10 3.66 Resident Garden Milk 7.24E-2 1.66E-1 1.57E-1 NNE 1.52 3.30 3.05 Resident Garden Milk 1.35E-1 3.21E-1 3.99E-1 NE 2.16 NONE NONE Resident 1.49E-1 ENE 2.05 4.84 4.84 Resident Garden Milk 1.52E-1 2.05E-1 2.05E-1 Garden location added. E 2.81 NONE NONE Resident 1.15E-1 ESE 1.95 NONE NONE Resident 2.48E-1 SE 3.36 NONE NONE Resident 2.23E-1 SSE NONE NONE NONE NA S NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.71E-1 WSW 0.75 NONE NONE Resident 1.26E-1 W 0.70 NONE NONE Resident 7.09E-2 WNW NONE NONE NONE NA NW 0.93 NONE NONE Resident 7.70E-2 NNW 1.30 NONE NONE Resident 6.21E-2 Comments: Dose calculations were performed using GASPAR code and 2015 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual organ dose identified.

11. Summary and Conclusions The conclusions are based on a review of the radio assay results and environmental gamma radiation measurements for the 2015 calendar year. Where possible, the data were compared to pre-operational sample data. All sample results for 2015 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, WRF Influent, WRF 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. There was no measurable radiological impact on the environment in 2015 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 2015 Medium or Pathway Sampled Lower Limit of Detection (LLD) All Indicator Locations Location with Highest Annual Mean Control Locations (Unit of Measurement) Type and Total Number of Analyses Performed (from Table 6.1) Mean (f)a Name Mean (f)a Mean (f)a Number of Nonroutine Reported Measurements Range Distance and Range Direction Range Direct Radiation (mrem/std. qtr.) TLD - 200 NA 25.2 (187/188) Site #35 31.9 (4/4) 24.9(8/8) 1 18.3 - 33.9 8 miles 330° 29.9 - 33.9 22.8 - 28.0 Air Particulates (pCi/m3) Gross Beta - 519 0.01 0.035 (545/552) Site # 29 0.035 (52/52) 0.035 (52/52) 7 0.016 - 0.059 1 mile 270º 0.018 - 0.059 0.016 - 0.058 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/m3) Gamma Spec. - 519 I-131 0.07 <LLD NA <LLD <LLD 4 <LLD NA <LLD <LLD Broadleaf Vegetation (pCi/Kg-wet) Gamma Spec. - 10 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 8 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 3.9 (29/48) Site #55 4.5 (11/12) NA 0 2.0 - 6.1 3 miles 214° 3.4 -6.5 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 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 1 Gamma Spec. - 27 Milk I-131 1 <LLD NA <LLD <LLD 0 (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. - 30 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 15 (7/36) Site #59 21 (2/12) NA 0 13-23 Onsite 180° 18-23 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 20 3000 865 (26/36) Site #59 1107 (10/12) NA 0 433 - 2341 Onsite 180° 433 - 2341 (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. 1985-2013 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 26, 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, 17 Oct. 2014. Web. 08 Apr. 2016. 10. "NCRP Report No. 160: Ionizing Radiation Exposure of the Population of the United States." Journal of Radiological Protection J. Radiol. Prot. 29.3 (2009): 465. Web.