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Annual Radiological Environmental Operating Report
	ML18131A353
Person / Time
Site:	Palo Verde
Issue date:	05/10/2018
From:	Dilorenzo M; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-07693-MDD/MSC
	Download: ML18131A353 (80)
	v • d • e

Technical Specification 5.6.2 5 .6.2 Palo Verde Nuclear Generating Station PO Box 52034 102-07693-MDD/MSC Phoenix, Arizona 85072-2034 Mail Station 7636 May 10, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Annual Radiological Environmental Operating Report 2017 In accordance with PVNGS Technical Specification 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2017.

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

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

DN: cn=Dilorenzo, Michael D(Z99838)

D(Z99838) Date: 2018.05.10 16:56:34 -07'00' Michael D. DiLorenzo Department Leader, Regulatory Affairs MDD/MSC/sma

Enclosure:

Palo Verde Nuclear Generating Station Annual Radiological Environmental Operating Report 2017 cc: K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. D. Orneak NRC NRR Project Manager for PVNGS M. M. OBanion NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS T. Morales Arizona Department of Health Services - Bureau of Radiation Controls (ADHS)

A member of the STARS Alliance LLC Callaway Diablo Canyon Palo Verde Wolf Creek

Enclosure Palo Verde Nuclear Generating Station Annual Radiological Environmental Operating Report 2017

(

Reference:

RCTSAI 1643, Legacy Item No. 036843.01)

Comolli, Digitally signed by Comolli, Michelle (Z09567)

Michelle DN: cn=Comolli, Michelle (Z09567)

Reason: I am the author of this document Prepared by: (Z09567) Date: 2018.04.09 08:48:34 -07'00' Hogue, Nathan Digitally (Z14113) signed by Hogue, Nathan (Z14113) DN: cn=Hogue, Nathan (Z14113)

Date: 2018.04.09 13:29:33 -07'00' Reviewed by:

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

(Z09119)

DN: cn=Moeller, Carl (Z09119)

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

Director, Radiation Protection

1. TABLE OF CONTENTS

1. Introduction ............................................................................................................................. 2 Overview ..................................................................................................................................... 2 Radiation and Radioactivity........................................................................................................ 3

2. Description of the Monitoring Program .................................................................................. 4 2.1 Radiological Environmental Monitoring Program ............................................................... 4 2.2 Radiological Environmental Monitoring Program Changes for 2017 .................................. 4 2.3 REMP Deviations/Abnormal Events Summary.................................................................... 4 2.4 Groundwater Protection ........................................................................................................ 6

3. Sample Collection Program .................................................................................................. 14 3.1 Water ................................................................................................................................... 14 3.2 Vegetation ........................................................................................................................... 14 3.3 Milk ..................................................................................................................................... 14 3.4 Air ....................................................................................................................................... 14 3.5 Soil, Sludge, and Sediment ................................................................................................. 14

4. Analytical Procedures ........................................................................................................... 15 4.1 Air Particulate ..................................................................................................................... 15 4.1.1 Gross Beta .................................................................................................................... 15 4.1.2 Gamma Spectroscopy .................................................................................................. 15 4.2 Airborne Radioiodine.......................................................................................................... 15 4.2.1 Gamma Spectroscopy .................................................................................................. 15 4.3 Milk ..................................................................................................................................... 15 4.3.1 Gamma Spectroscopy .................................................................................................. 15 4.3.2 Radiochemical I-131 Separation .................................................................................. 15 4.4 Vegetation ........................................................................................................................... 15 4.4.1 Gamma Spectroscopy .................................................................................................. 15 4.5 Sludge/Sediment ................................................................................................................. 16 4.5.1 Gamma Spectroscopy .................................................................................................. 16 4.6 Water ................................................................................................................................... 16 4.6.1 Gamma Spectroscopy .................................................................................................. 16 4.6.2 Tritium ......................................................................................................................... 16 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page i

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 Groundwater ....................................................................................................................... 29 8.7 Surface Water...................................................................................................................... 29 8.8 Sludge and Sediment........................................................................................................... 30 8.8.1 WR Centrifuge Waste Sludge ...................................................................................... 30 8.8.2 Cooling Tower Sludge ................................................................................................. 30 8.9 Data Trends ......................................................................................................................... 30 8.10 Hard-To-Detect Radionuclide Results .............................................................................. 30

9. Thermoluminescent Dosimeter (TLD) Results and Data ..................................................... 57

10. Land Use Census................................................................................................................ 62 10.1 Introduction ....................................................................................................................... 62 10.2 Census Results .................................................................................................................. 62

11. Summary and Conclusions ................................................................................................ 67

12. References .......................................................................................................................... 71 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page ii

LIST OF TABLES Table 2-1 Sample Collection Locations .......................................................................................... 7 Table 2-2 Sample Collection Schedule ........................................................................................... 8 Table 2-3 Summaries of the REMP Deviations/Abnormal Events ................................................ 9 Table 6-1 ODCM Required Lower Limits of Detection (a priori) ............................................... 21 Table 6-2 ODCM Required Reporting Levels .............................................................................. 22 Table 6-3 Typical MDA Values ................................................................................................... 23 Table 7-1 Interlaboratory Comparison Results ............................................................................. 25 Table 8-1 Particulate Gross Beta in Air 1st-2nd Quarter .............................................................. 31 Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter .............................................................. 32 Table 8-3 Gamma in Air Filter Composites ................................................................................. 33 Table 8-4 Radioiodine in Air 1st-2nd Quarter .............................................................................. 34 Table 8-5 Radioiodine in Air 3rd-4th Quarter .............................................................................. 35 Table 8-6 Vegetation..................................................................................................................... 36 Table 8-7 Milk .............................................................................................................................. 37 Table 8-8 Drinking Water ............................................................................................................. 38 Table 8-9 Groundwater ................................................................................................................. 40 Table 8-10 Surface Water ............................................................................................................. 41 Table 8-11 Sludge/Sediment ......................................................................................................... 46 Table 8-12 Hard -To-Detect Radionuclide Results ...................................................................... 48 Table 9-1 TLD Site Locations ...................................................................................................... 58 Table 9-2 Environmental TLD Results ......................................................................................... 59 Table 10-1 Land Use Census ........................................................................................................ 63 Table 11-1 Environmental Radiological Monitoring Program Annual Summary........................ 68 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page iii

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

....................................................................................................................................................... 52 Figure 8-5 Gross Beta in Drinking Water ..................................................................................... 53 Figure 8-6 Evaporation Pond Tritium Activity (Pre-Op- 2008) ................................................... 54 Figure 8-7 Evaporation Pond Tritium Activity (2009-2017)........................................................ 55 Figure 8-8 Sedimentation Basin 2 Cs-137 .................................................................................... 56 Figure 9-1 Network Environmental TLD Exposure Rates ........................................................... 60 Figure 9-2 Environmental TLD Comparison: Pre-Operational versus 2017 ................................ 61 Figure 10-1 Historical Comparison of Nearest Resident Dose ..................................................... 64 Figure 10-2 Historical Comparison of Nearest Milk Animal Dose .............................................. 65 Figure 10-3 Historical Comparison of Nearest Garden Dose ....................................................... 66 TABLE OF APPENDICIES Appendix A ................................................................................................................................... 72 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page iv

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

Broadleaf vegetation Groundwater Drinking water Surface water Airborne particulate and radioiodine Goat milk Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmental gamma radiation.

The Environmental TLD program is also conducted by APS.

The Arizona Department of Health Services, Bureau of Radiation Control (BRC) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by BRC include onsite samples from the Reservoirs, Evaporation Ponds, and two (2)

Deep Wells. Offsite samples analyzed by BRC include two (2) local resident wells. BRC also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring locations, eighteen (18) of which are duplicates of APS locations.

A comparison of pre-operational and operational data indicates no changes to environmental radiation levels.

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 1

1. Introduction This report presents the results of the operational Radiological Environmental Monitoring Program conducted by Arizona Public Service Company (APS). The Radiological Environmental Monitoring Program (REMP) was established for the Palo Verde Nuclear Generating Station (PVNGS) by APS in 1979.

This report contains the measurements and findings for 2017. All references are specifically identified in Section 12.

Overview The Radiological Environmental Monitoring Program ( R E M P ) provides representative measurements of radiation and radioactive materials in exposure pathways. REMP measures radionuclides that lead to the highest potential radiation exposures to members of the public resulting from station operation. This monitoring program implements Title 10 of the Code of Federal Regulations (CFR) Part 50, Appendix I,Section IV.B.2., and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the US Nuclear Regulatory Commission (USNRC) in their Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (incorporated into NUREG 1301). Results from the REMP help to evaluate sources of elevated levels of radioactivity in the environment (i.e. atmospheric nuclear detonations or abnormal plant releases).

The Land Use Census ensures that changes in the use of areas at, and beyond the site boundary, are identified and that modifications to the REMP are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

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

Results of the PVNGS pre-operational environmental monitoring program are presented in Reference 1.

The initial criticality of Unit 1 occurred May 25, 1985. Initial criticality for Units 2 and 3 were April 18, 1986, and October 25, 1987, respectively. PVNGS operational findings (historical) are presented in Reference 2.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 2

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

Atmospheric conditions, the Earths magnetic field, and differences in elevation can affect the amount, or dose, of cosmic radiation an individual receives. The Earth is a source of terrestrial radiation. Uranium, thorium, and radium exist naturally in rock and soil. All organic matter contains carbon and potassium, and water contains small amounts of dissolved uranium and thorium. The largest contributor of dose to Americans from natural sources is attributed to radon which is found in air. All people are a source of internal radiation. Potassium-40 and carbon-14 are radioactive nuclides and inside all people from birth, making people a source of exposure.

Man-made sources of radiation include: consumer products, nuclear medicine, and medical procedures. There are a number of occupational areas which result in exposure to individuals of varying amounts of radiation such as: radiography, radiology, radiation oncology, power generation, and research laboratories. The Nuclear Regulatory Commission (NRC) requires licensees to monitor exposure to workers and limit occupational exposure to 5,000 millirem.

Several consumer products contain radioactive material such as: some ceramics, thorium lantern mantles, luminous watches containing tritium, smoke detectors, and tobacco. Other consumer product sources of radiation can come from building and road construction materials, combustible fuels (i.e. gas, coal), and x-ray security systems. The most significant contributor to radiation exposure from man-made sources is medical procedures. Diagnostic x-rays and nuclear medicine procedures, such as those that use iodine-131 or cesium-137, are examples of man-made medical sources.

The average member of the public receives a total annual dose of approximately 620 millirem from ionizing radiation. Figure 1-1 illustrates the contribution of various sources of radiation to radiation exposure in the United States (NCRP Report No.160 (2009)).

Sources of Radiation Exposure in the United States Consumer Products Nuclear Medicine 2% 12%

Industrial/Occupational 0.1%

Radon and Thoron 37%

Medical Procedures 36%

Cosmic Internal Terrestrial 5%

5% 3%

Figure 1-1 Sources of Radiation Exposure in the United States PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 3

2. Description of the Monitoring Program APS and vendor organizations performed the pre-operational Radiological Environmental Monitoring Program between 1979 and 1985. APS and vendors continued the program into the operational phase.

2.1 Radiological Environmental Monitoring Program The assessment program consists of routine measurements of environmental gamma radiation and of radionuclide concentrations in media such as air, groundwater, drinking water, surface water, vegetation, milk, sludge, and sediment.

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

Analyses for hard-to-detect radionuclides were performed by GEL Laboratories LLC.

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

In addition to monitoring environmental media, a Land Use Census is performed annually to identify the nearest milk animals, residents, and gardens. This information is used to evaluate the potential dose to members of the public for those exposure pathways that are indicated.

2.2 Radiological Environmental Monitoring Program Changes for 2017 There were no changes to the Radiological Environmental Monitoring Program that impacted the Offsite Dose Calculation Manual (ODCM) Revision 27.

2.3 REMP Deviations/Abnormal Events Summary During calendar year 2017, there were fifteen (15) deviations/abnormal events with regards to the monitoring program. Refer to Table 2-3 for more detail and corrective actions taken.

There were four (4) events involving Air sample stations. Palo Verde Nuclear Generating Station has ten (10) Air sample sites: one (1) control, four (4) ODCM required, and five (5) supplemental sites. Supplemental sampling locations were available and produced valid data for any sampling period involving invalid samples from control or required sample locations. Three (3) events were due to reduced sample volume, two (2) of which were confirmed to be the result of power interruption to the sample station. The reduced sample volume was significant enough over the course of four (4) sample periods that the samples in question were determined to be PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 4

invalid. One (1) event was attributed to a small hole in the particulate filter. The filter was found to still have normal loading and deposition; therefore this sample is considered to be valid.

Seven (7) events were due to an inability to meet a LLD. One (1) of the seven (7) events involved the control Milk sample location, Site 53, which did not meet the LLD for I-131 (1 pCi/L); the achieved MDA was 1.05 pCi/L. This event was attributed to a software malfunction.

There was no detectable activity in this sample and the LLD that was achieved was below the action level. Two (2) of the seven (7) events were due to samples not meeting the LLD for La-140 (15 pCi/L). The event for Site 48 was attributed to input error of the sample date. The event for Site 49 was attributed to excessive time between sample acquisition and sample analysis.

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

Sedimentation Basin sample. Two (2) of these events were attributed to incorrect volume input into the analysis software and one (1) was attributed to excessive time between sample acquisition and analysis. The two (2) Influent Water Reclamation Facility Surface Water samples achieved an MDA below the action level, with the exception of I-131, and had no detectable plant-related radioactivity. PVNGS receives waste water from the City of Phoenix and is known to contain the radiopharmaceutical I-131. The influent contains no plant related influent; influent samples are obtained for trending purposes. The Sedimentation Basin had no detectable activity and all MDAs were below action levels.

One (1) event was an abnormally low tritium level for Evaporation Pond 1C. The analysis reported <320 pCi/L. This value was investigated, revealing a reporting error. Due to the inability to reanalyze, this sample was determined to be invalid. Correction to the reporting file was made. The following sample results were within historically normal values.

Two (2) events involved deviation from procedural guidance. One (1) of the two (2) events was a failure to collect the sample within the procedurally directed sampling frequency for Milk sample site 54. The sample was taken 40 days following the previous sample collection. The procedure directs that samples be collected within a 125% surveillance period; samples should be collected no more than 37 days apart. The sample was collected within the current applicable month and analysis confirmed that there was no plant related impact via the milk ingestion pathway. One (1) event of the two (2) was a failure to collect the procedurally required mass for the October vegetation samples collected at the control location, Site 62. The procedural requirement is to collect a minimum of 0.6 kg of each vegetation sample. Three vegetation types were collected of 0.519 kg, 0.413 kg, and 0.372 kg. There was no impact to the requirements of the ODCM as these are control samples with no resident samples available, as well as supplemental air samples collected weekly as a contingency. Additionally, the mass of the vegetation collected was adequate to obtain valid analysis results, which have been included in Table 8-6.

The last event involved environmental dosimeter Site 6. Upon 4th Quarter change-out, it was discovered that the environmental dosimetry and stanchion were missing at Site 6. Site 6 stanchion and dosimetry were replaced for the 1st Quarter 2018 sampling period.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 5

2.4 Groundwater Protection PVNGS has implemented a groundwater protection initiative developed by the Nuclear Energy Institute (NEI). The implementation of this initiative, NEI 07-07 (Industry Ground Water Protection Initiative - Final Guidance Document, August 2007), provides added assurance that groundwater will not be adversely affected by PVNGS operations.

Several monitoring wells have been installed to monitor the subsurface water and shallow aquifer at Units 1, 2, and 3. These wells are sampled monthly and quarterly for chemical and radiological parameters. The State of Arizona Aquifer Protection Permit (Area-Wide) No. P-100388 (APP) provides agreed upon monitoring parameters and reporting thresholds. Sample results for the shallow aquifer wells are reported in the PVNGS Annual Radioactive Effluent Release Report (ARERR). The State of Arizona APP provides specific regulatory criteria for groundwater protection.

Three subsurface samples were obtained, one each from Units 2 and 3 tritium monitoring wells, and one from the shallow aquifer outside of the Unit 1 Radiologically Controlled Area (RCA).

These samples were analyzed for hard-to-detect radionuclides (e.g. C-14, Fe-55, Ni-63, Sr-90) as verification that there are no underground leaks from plant systems that may affect groundwater. All results were <MDA. Refer to Table 8-12 for sample results.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 6

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 371st Ave. and Buckeye-Salome Rd.

15 Air NE2 NE Site Boundary 17A Air E3 351st Ave.

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

Designates a control site (a) Distances and direction are from the center-line of Unit 2 containment and rounded to the nearest mile Air sample sites designated with the letter A are sites that have the same site number as a TLD location, but are not in the same location (e.g. site #6 TLD location is different from site

6A air sample location; site #4 TLD location is the same as site #4 air sample location)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 7

Table 2-2 Sample Collection Schedule SAMPLE AIRBORNE AIRBORNE GROUND DRINKING SURFACE SITE # PARTICULATE MILK RADIOIODINE VEGETATION WATER WATER WATER 4 W W 6A W W 7A W W 14A W W 15 W W 17A W W 21 W W 29 W W 35 W W 40 W W 46 W 47 M/AA 48 W 49 W 51 M/AA M/AA 53 M/AA 54 M/AA 55 W 57 Q 58 Q 59 Q 60 Q 61 Q 62 M/AA 63 Q 64 Q W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 8

Table 2-3 Summaries of the REMP Deviations/Abnormal Events Deviation/Abnormal Actions Taken Event Air Sample Station, Site 35, had excessively low run time for Week

1. Air Sample Site 35 had 1 of 2017. Pump was running at beginning and end of sampling reduced pump runtime; period, but runtime indicates a sample volume of 238 m3. This sample INVALID for volume is <55% of normal volume. Sample is considered INVALID sample period for sample period 12/27/2016-1/3/2017 due to low sample volume.

12/27/2016-1/3/2017 Event documented through CR 18-03209 (Table 8-1 and 8-4, Note 1)

2. Air Samples Site 15 Air Sample Site 15 particulate filter paper was found to have small Particulate Filter had hole, which is contrary from a normal intact filter. Sample volume, small hole for sample filter loading, and filter deposition is normal. This sample is period 1/10/2017- considered VALID. Event documented through CR 17-00760 1/17/2017 (Table 8-1 and 8-4, Note 2)

Air Sample Site 6A pump found not running. Troubleman corrected

3. Air Sample Site 6A power issue, returning pump to service. Normal volume per sample found not running due period is approximately 433 m3. Volume for this sampling period to lack of power was 209 m3. Sample determined to be INVALID for sample period 4/26/2017 4/18/2017-4/26/2017, due to insufficient sample volume. Event documented through CR 17-06259 (Table 8-1and 8-4, Note 3).

Air Sample Site 6A was found to have no power at the pole.

Troubleman was dispatched and power was restored. Normal volume per sample period is approximately 433 m3. Volume for this

4. Air Sample Site 6A sampling period was 270 m3 for sample period 7/18/17-7/25/2017 found with no power at and pump was inoperable for sample period 7/25/2017-8/1/2017.

the pole 7/25/2017 Sample was determined to be INVALID for sample periods 7/18/17-8/1/2017, due to insufficient sample volume. Event documented through CR 17-10693 (Table 8-2 and 8-5, Note 4).

5. Milk Sample Site 53 An error in the Multi-channel Analyzer software, causing a reduced analysis did not achieve count time, resulted in a MDA of 1.05 pCi/L for I-131 in the June required Lower Limits Milk Sample for Site 53. This is contrary to the ODCM required of Detection for I-131 LLD for I-131 of 1 pCi/L. No activity was detected in this sample.

for June sample Event documented through CR 17-10463 (Table 8-7, Note 1).

Drinking Water Sample for Site 48 did not reach the ODCM

6. Drinking Water Sample required LLD due to sample collection date input error into analysis Site 48 did not achieve software. The ODCM required LLD for La-140 is 15 pCi/L.

required Lower Limits Analysis of sample reported a MDA of 22 pCi/L for La-140. No of Detection for La-140 activity was detected in this sample. Event documented through CR for April sample 17-10476 (Table 8-8, Note 1).

Drinking Water Sample for Site 46, 49, and 55 did not reach the

7. Drinking Water Sample ODCM required LLD due to sample collection date input error into Site 46, 49, and 55 did analysis software. The ODCM required LLD for I-131 and La-140 not achieve required is 15 pCi/L. Analysis of sample reported a MDA of 17 pCi/L for I-Lower Limits of 131 and 185 pCi/L (Site 46), 17 pCi/L for I-131 and 200 pCi/L for Detection for I-131 and La-140 (Site 49), and 19 pCi/L for I-131 and 22 pCi/L for La-140 La-140 for April sample (Site 55). No activity was detected in this sample. Event documented through CR 17-10476 (Table 8-8, Note 2).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 9

Drinking Water Sample for Site 49 did not reach the ODCM

8. Drinking Water Sample required LLD due to excessive time between sample acquisition and Site 49 did not achieve analysis. The ODCM required LLD for La-140 is 15 pCi/L.

required Lower Limits Analysis of sample reported a MDA of 150 pCi/L for La-140. No of Detection for La-140 activity was detected in this sample. Event documented through CR for July sample 18-00109 (Table 8-8, Note 4).

Evaporation Pond 1C, 2nd Quarter Tritium sample had abnormally low tritium results (<320 pCi/L). Investigation of this sample

9. Evaporation Pond 1C, analysis revealed a reporting error. Sample could not be reanalyzed.

2nd Quarter Tritium Sample results determined to be INVALAD due to reporting error.

sample INVALID due Correction to the reporting file was made and the 3rd Quarter results to reporting error.

for this location were consistent with historical trends. Event is documented for trending with CR 18-00638 (Table 8-10, Note 1).

Water Reclamation Facility Influent sample volume incorrectly

10. Water Reclamation entered into analysis software, resulting in several missed LLDs.

Facility Influent sample PVNGS receives waste water from the City of Phoenix. Water analysis did not achieve samples of the Influent are analyzed for trending purposes and do several Lower Limits of not contain plant related effluents. Event documented for trending Detection 1/24/2017 purposes with CR 17-17823 (Table 8-10, Note 3).

Water Reclamation Facility Influent did not achieve several LLDs

11. Water Reclamation due to delay in sample analysis. PVNGS receives waste water from Facility Influent sample the City of Phoenix. Water samples of the Influent are analyzed for analysis did not achieve trending purposes and do not contain plant related effluents. Event several Lower Limits of documented for trending purposes with CR 17-04054 (Table 8-10, Detection 3/14/2017 Note 4).

Sedimentation Basin sample volume incorrectly entered into analysis

12. Sedimentation Basin software, resulting in several missed LLDs. PVNGS is a zero liquid sample analysis did not release plant; water in this basin is the result of rain water and rain achieve several Lower runoff. Water samples of this basin are confirmatory and are Limits of Detection analyzed for trending purposes. Event documented for trending 1/24/2017 purposes with CR 17-17823 (Table 8-10, Note 3).

The July Site 54 Milk was not collected within required frequency, per procedural guidance. The June sample was collected on 6/9/17 and the July sample was not collected until 7/20/17 due to

13. Site 54 Milk sample was unavailability the week before. Per the ODCM, the sample needs to not collected within the be collected monthly; procedural guidance and the ODCM directs required frequency for that sample be collected within the 125% surveillance test time period July 2017 of 38 days, 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months . All samples were collected and analyzed to the ODCM required LLD, confirming that there was no plant related impact via the milk ingestion pathway. Event documented through CR 17-10466.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 10

Procedural guidance directs that vegetation samples obtained be a

14. Vegetation control minimum of 0.6 kg. The October 2017 samples for Site 62 (REMP locations, Site 62, did Control Location) did not satisfy this requirement; 3 vegetation types not collect of 0.519kg, 0.413kg, and 0.372kg were collected. There was no procedurally required impact to the requirements of the ODCM as these are control samples mass for each with no resident samples available, as well as supplemental air vegetation sample for samples collected weekly as a contingency. Additionally, the mass of October 2017. vegetation was adequate to obtain valid analysis results, which are included in Table 8-6. Event documented through CR 17-15048.

During the 4th Quarter Environmental Dosimetry change-out, it was

15. Site 6 Environmental discovered that the Site 6 dosimetry and stanchion was missing and Dosimetry missing for could not be located. The stanchion and dosimetry were replaced for 4th Quarter 2017. the 1st Quarter 2018 sampling period. Event documented through CR 17-18260.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 11

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3. Sample Collection Program APS Personnel, using PVNGS procedures, collected all samples.

3.1 Water Weekly samples were collected from four (4) residence wells for monthly and quarterly composites. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. The samples were analyzed for gross beta, gamma-emitting radionuclides, and tritium.

Quarterly grab samples were collected from the 45 and 85 acre Reservoirs, Evaporation Ponds 1A/B/C, 2A/B, and 3A/B, and onsite wells 34abb and 27ddc. Samples were collected in one-gallon containers (plastic cubitainers) and 500 mL glass bottles. Samples were analyzed for gamma-emitting radionuclides and tritium.

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

3.2 Vegetation Vegetation samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides.

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

3.4 Air Air particulate filters and charcoal cartridges were collected at ten (10) sites on a weekly basis. Particulate filters were analyzed for gross beta. Charcoal cartridges were analyzed for Iodine-131. Particulate filters were composited quarterly, by location, and analyzed for gamma-emitting radionuclides.

3.5 Soil, Sludge, and Sediment Sludge samples were obtained weekly from the WR waste centrifuge (during operational periods) and analyzed for gamma-emitting radionuclides. Cooling tower sludge was analyzed for gamma-emitting radionuclides prior to disposal in the WR sludge landfill.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 14

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

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

4.2 Airborne Radioiodine 4.2.1 Gamma Spectroscopy The charcoal cartridge is counted on a multichannel analyzer equipped with a HPGe detector. The resulting spectrum is analyzed by a computer for Iodine-131.

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

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

4.4 Vegetation 4.4.1 Gamma Spectroscopy The sample is pureed in a food processor, placed in a one liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector. The PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 15

resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

4.5 Sludge/Sediment 4.5.1 Gamma Spectroscopy The wet/dry sample is placed in a one-liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

4.6 Water 4.6.1 Gamma Spectroscopy The sample is placed in a one-liter plastic marinelli beaker and counted on a multichannel analyzer equipped with a HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

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

4.6.3 Gross Beta A 200-250 milliliter sample is placed in a beaker. Five (5) milliliters of concentrated nitric (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 and verified by trained technicians.

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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.

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6. Isotopic Detection Limits and Reporting Criteria 6.1 Lower Limits of Detection The lower limits of detection (LLD) and the method for calculation are specified in the PVNGS ODCM, Reference 4. The ODCM required a priori LLDs are presented in Table 6-1.

6.2 Data Reporting Criteria All results that are greater than the Minimum Detectable Activity (MDA) (a posteriori LLD) are reported as positive activity with its associated 2counting error. All results that are less than the MDA are reported as less than values at the associated MDA. For example, if the MDA is 12 pCi/liter, the value is reported as <12.

Typical MDA values are presented in Table 6-3.

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

Background fluctuations

Unavoidably small sample sizes

The presence of interfering radionuclides

Self-absorption corrections

Decay corrections for short half-life radionuclides

Other uncontrollable circumstances In these instances, the contributing factors will be noted in the table where the data are presented. A summary of deviations/abnormal events is presented in Table 2-3 Summaries of the REMP Deviations/Abnormal Events and includes a description of any sample results that did not meet a priori LLD requirements.

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

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BACKGROUND GROSS If a sufficient number of replicate analyses are run, it is expected that the results would fall in a normal Gaussian distribution. Standard statistics allow an estimate of the probability of any particular deviation from the mean value. It is common practice to report the mean +/-

one or two standard deviations as the result. In routine analysis, such replication is not carried out, and it is not possible to report a Gaussian standard deviation. With counting procedures, however, it is possible to estimate a Poisson standard deviation directly from the count. Data are commonly reported as the measured value +/- one or two Poisson standard deviations. The reported values are then considered to give some indication of the range in which the true value might be expected to occur.

LLD is the smallest amount of sample activity that will yield a net count for which there is confidence at a predetermined level that activity is present. LLDs are calculated values for individual radionuclides based on a number of different factors including sample size, counting efficiency and background count rate of the instrument, the background and sample counting time, the decay time, and the chemical recovery of the analytical procedures. A minimum detectable activity value (MDA) is the smallest amount of activity that can be detected in an actual sample and uses the values obtained from the instrument and outcome of the analytical process. Therefore, the MDA values may differ from the calculated LLD values if the sample size and chemical recovery, decay values, or the instrument efficiency, background, or count time differed from those used in the LLD calculation.

The factors governing the calculation of the LLD and MDA values are discussed below:

1. Sample Size: The number of observations included in a statistical analysis.

Sample size dictates the amount of information available about a studied subject to make accurate inferences.

2. Counting Efficiency: The fundamental quantity in the measurement of a radioactive substance is the number of disintegrations per unit time. As with most physical measurements in analytical chemistry, an absolute measurement of the disintegration rate is seldom possible, rather it is necessary to compare the sample with one or more standards. The standards determine the counter efficiency that may then be used to convert sample counts per minute (cpm) to disintegrations per minute (dpm).

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3. Background Count Rate: Any counter will show a certain counting rate without a sample in position. This background counting rate comes from several sources: 1) natural environmental radiation from the surrounding materials, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background counting rate will depend on the amounts of these types of radiation and the sensitivity of the counter to the radiation.

4. Background and Sample Counting Time: The amount of time devoted to the counting of the background depends on the level of activity being measured. In general, with low level samples, this time should be about equal to that devoted to counting a sample.

5. Time Interval between Sample Collection and Counting: Decay measurements are useful in identifying certain short-lived nuclides. The disintegration constant is one of the basic characteristics of a specific radionuclide and is readily determined, if the half-life is sufficiently short.

To ensure the required LLDs are achieved, appropriate decay correction values are used to account for radioactive decay during transit time and sample processing.

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Table 6-1 ODCM Required Lower Limits of Detection (a priori)

Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/I) or Gas (pCl/m-) (pCid) (pCi/kg. wet)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 Fe-59 30 Co-58, -60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-I3I p* 0.07 1 60 Cs-134 15 0.05 15 60 Cs-137 18 0.06 18 80 Ba-140 60 60 U-140 15 15

If no drinking water pathway exists, a value of 3000 pCi/liter may be used

- If no drinking water pathway exists, a value of 15 pCi/liter may be used NOTES:

This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

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Table 6-2 ODCM Required Reporting Levels Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/1) or Gas (pCi/m^) (pCid) (pCi/kg, wet)

H-3 20,000*

Mn-54 1,000 Fe-59 400 Co-58 1,000 Co-60 300 Zn-65 300 Zr-Nb-95 400 1-131 2** 0.9 3 100 Cs-134 30 10 60 1,000 Cs-137 50 20 70 2,000 Ba-U-140 200 300

For drinking water samples. This is a 40 CFR 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

- If no drinking water pathway exists, a reporting level of 20 pCi/L may be used.

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Table 6-3 Typical MDA Values Water Milk Airborne Particulate or Vegetation Analysis/Nuclide (pCi/liter) (pCi/liter) Gas (pCi/m3) (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 0.04b 49 Cs-134 9 1 0.003b 47 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 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 23

7. Interlaboratory Comparison Program 7.1 Quality Control Program APS maintains an extensive QA/QC Program to provide assurance that samples are collected, handled, tracked, and analyzed to specified requirements. This program includes appropriate elements of USNRC Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, Revision 1. Included in the program are procedures for sample collection, preparation and tracking, sample analysis, equipment calibration and checks, and ongoing participation in an interlaboratory comparison program. Duplicate/replicate samples are analyzed to verify analytical precision and sample methodology. Comprehensive data reviews are performed including trending of data where appropriate.

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

Beta/Gamma/ in Air Filter

I-131 in Air

Beta in Water

Gamma in Water

Tritium in Water

Gamma in Milk 7.2 Intercomparison Results APS participates in a crosscheck program using vendor supplied blind radionuclide samples. Results for the interlaboratory comparison program are presented in Table 7-1.

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Table 7-1 Interlaboratory Comparison Results Sample Analysis Nuclide Units Known PVNGS 1 sigma Resolution* Ratio NRC Results ID Type Value Value Error Range E11759 Gamma Water I-131 pCi/L 9.78E+01 1.05E+02 1.10E+01 10 1.07 0.60 - 1.66 Acceptable Ce-141 pCi/L 1.45E+02 1.51E+02 6.00E+00 25 1.04 0.75 - 1.33 Acceptable Cr-51 pCi/L 2.91E+02 2.65E+02 2.50E+01 11 0.91 0.60 - 1.66 Acceptable Cs-134 pCi/L 1.20E+02 1.14E+02 3.10E+00 37 0.95 0.75 - 1.33 Acceptable Cs-137 pCi/L 1.40E+02 1.46E+02 5.30E+00 28 1.04 0.75 - 1.33 Acceptable Co-58 pCi/L 1.50E+02 1.56E+02 6.60E+00 24 1.04 0.75 - 1.33 Acceptable Mn-54 pCi/L 1.65E+02 1.68E+02 6.30E+00 27 1.02 0.75 - 1.33 Acceptable Fe-59 pCi/L 1.29E+02 1.37E+02 5.50E+00 25 1.06 0.75 - 1.33 Acceptable Zn-65 pCi/L 2.00E+02 2.12E+02 8.80E+00 24 1.06 0.75 - 1.33 Acceptable Co-60 pCi/L 1.83E+02 1.90E+02 4.50E+00 42 1.04 0.75 - 1.33 Acceptable E11760 Beta Filter G. Beta pCi/ea 9.71E+01 1.00E+02 2.30E+00 43 1.03 0.75 - 1.33 Acceptable E11761 I-131 Cartridge I-131 pCi/ea 9.80E+01 9.91E+01 5.10E+00 19 1.01 0.75 - 1.33 Acceptable E11762 Gamma Filter Ce-141 pCi/ea 9.81E+01 1.04E+02 2.40E+00 43 1.06 0.75 - 1.33 Acceptable Cr-51 pCi/ea 1.96E+02 2.02E+02 9.30E+00 22 1.03 0.75 - 1.33 Acceptable Cs-134 pCi/ea 8.11E+01 7.50E+01 1.20E+00 63 0.92 0.80 - 1.25 Acceptable Cs-137 pCi/ea 9.46E+01 1.04E+02 2.90E+00 36 1.10 0.75 - 1.33 Acceptable Co-58 pCi/ea 1.01E+02 1.07E+02 2.80E+00 38 1.06 0.75 - 1.33 Acceptable Mn-54 pCi/ea 1.11E+02 1.25E+02 3.00E+00 42 1.13 0.75 - 1.33 Acceptable Fe-59 pCi/ea 8.71E+01 9.74E+01 2.30E+00 42 1.12 0.75 - 1.33 Acceptable Zn-65 pCi/ea 1.35E+02 1.52E+02 3.80E+00 40 1.13 0.75 - 1.33 Acceptable Co-60 pCi/ea 1.24E+02 1.31E+02 2.10E+00 62 1.06 0.80 - 1.25 Acceptable E11763 Gamma Milk I-131 pCi/L 4.06E+01 4.13E+01 2.80E+00 15 1.02 0.60 - 1.66 Acceptable Ce-141 pCi/L 2.04E+01 2.31E+01 1.40E+00 17 1.13 0.75 - 1.33 Acceptable Cr-51 pCi/L 4.08E+01 3.28E+01 4.60E+00 7 0.80 0.50 - 2.00 Acceptable Cs-134 pCi/L 1.69E+01 1.65E+01 5.00E-01 33 0.98 0.75 - 1.33 Acceptable Cs-137 pCi/L 1.97E+01 2.04E+01 1.10E+00 19 1.04 0.75 - 1.33 Acceptable Co-58 pCi/L 2.10E+01 2.26E+01 1.30E+00 17 1.08 0.75 - 1.33 Acceptable Mn-54 pCi/L 2.31E+01 2.40E+01 1.40E+00 17 1.04 0.75 - 1.33 Acceptable Fe-59 pCi/L 1.81E+01 2.02E+01 1.40E+00 14 1.12 0.60 - 1.66 Acceptable Zn-65 pCi/L 2.80E+01 3.11E+01 1.50E+00 21 1.11 0.75 - 1.33 Acceptable Co-60 pCi/L 2.57E+01 2.26E+01 9.00E-01 25 0.88 0.75 - 1.33 Acceptable PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 25

Table 7-1 Interlaboratory Comparison Results (Continued)

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

calculated from PVNGS value/1 sigma error value

- Eckert & Ziegler Analytics, Inc. NIST-traceable known value NRC Acceptance Criteria 1 Resolution Ratio 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.80-1.25

>200 0.85-1.18 1

From NRC Inspection Manual, procedure #84750, "Radioactive Waste Treatment, and Effluent and Environmental Monitoring" PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 26

Table 7-1 Interlaboratory Comparison Results (Continued)

Sample Analysis ERA PT Nuclide Units PVNGS Assigned Value 1 Acceptance Limit 2 Results Type Type Study Value Water Tritium RAD-111 H-3 pCi/L 5,910 6,250 5390-6880 Acceptable Water Gamma RAD-111 Ba-133 pCi/L 73.3 73.7 61.7-81.1 Acceptable Cs-134 pCi/L 45.7 53 42.8-58.3 Acceptable Cs-137 pCi/L 51.5 52.9 47.6-61.1 Acceptable Co-60 pCi/L 68.1 69.5 62.6-78.9 Acceptable Zn-65 pCi/L 374 348 313-406 Acceptable 1

The ERA assigned values are established per the guidelines contained in the National Environmental Laboratory Accreditation Conference (NELAC) program criteria as applicable.

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

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

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

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

Most samples contain radioactivity associated with natural background/cosmic radioactivity (e.g. K-40, Th-234, Be-7). Gross beta results for drinking water and air are due to natural background. Gamma-emitting radionuclides, which can be attributed to natural background sources, are not indicated in this report.

Results and interpretation of the data for all of the samples analyzed during 2017 are presented in the following sections.

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

No plant-related activity was identified 8.2 Airborne Radioiodine Table 8-4 and Table 8-5 present the quarterly radioiodine results. Radioiodine was not observed in any samples.

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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 6.84 pCi/liter. The gross beta activity is attributable to natural (background) radioactive materials.

8.6 Groundwater Groundwater samples were analyzed from two onsite wells (regional aquifer) for tritium and gamma-emitting radionuclides. Results obtained from the analysis of the samples are presented in Table 8-9.

No tritium or gamma-emitting radionuclides were observed in any of the samples.

8.7 Surface Water Surface water samples from the Reservoirs and Evaporation Ponds were analyzed for tritium and gamma-emitting radionuclides. The two Reservoirs contain processed sewage water from the City of Phoenix and are approximately 45 and 85 acres in size. The three Evaporation Ponds receive mostly circulating water from main turbine condenser cooling and are about 200-250 acres each.

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

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

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

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

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8.8 Sludge and Sediment 8.8.1 WR Centrifuge Waste Sludge Sludge samples were obtained from the WR centrifuge and analyzed by gamma spectroscopy. I-131 activity in the sludge is consistent with historical values and, as previously discussed, is due to radiopharmaceuticals in the WR Influent. The concentration of I-131 ranged from no detectable to 959 pCi/kg.

Results for WR centrifuge waste sludge can be found in Table 8-11.

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

8.9 Data Trends Figure 8-1 through Figure 8-8 present data in graphical format. Historical data are displayed for comparison where practical.

8.10 Hard-To-Detect Radionuclide Results Table 8-12 shows the results of the three subsurface samples obtained from 3 tritium monitoring points.

These samples were analyzed for hard-to-detect radionuclides (e.g. C-14, Fe-55, Ni-63, Sr-90) and all results were <MDA. These results indicate that no leaks from plant systems have affected groundwater.

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Table 8-1 Particulate Gross Beta in Air 1st-2nd Quarter PARTICULATE GROSS BETA IN AIR 1st QUARTER ODCM required samples denoted by

units are pCi/m3 (control)

START STOP Site Site Site Site Site Site Site Site Site Site RSD Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Mean (%) Note 1 27-Dec-16 3-Jan-17 0.026 0.023 0.029 0.027 0.029 0.026 0.028 0.027 0.0363 0.028 0.027 6.4 1 2 3-Jan-17 10-Jan-17 0.033 0.032 0.034 0.029 0.024 0.033 0.033 0.029 0.027 0.027 0.030 11.0 3 10-Jan-17 17-Jan-17 0.027 0.023 0.027 0.025 0.025 0.026 0.028 0.026 0.024 0.026 0.025 6.0 2 4 17-Jan-17 24-Jan-17 0.024 0.022 0.023 0.024 0.023 0.025 0.026 0.020 0.020 0.022 0.023 8.7 5 24-Jan-17 31-Jan-17 0.017 0.020 0.021 0.019 0.019 0.022 0.019 0.019 0.019 0.018 0.019 7.7 6 31-Jan-17 7-Feb-17 0.035 0.034 0.031 0.041 0.028 0.029 0.038 0.023 0.034 0.037 0.033 15.8 7 7-Feb-17 14-Feb-17 0.024 0.024 0.023 0.021 0.020 0.025 0.023 0.021 0.021 0.022 0.022 7.1 8 14-Feb-17 21-Feb-17 0.019 0.020 0.022 0.021 0.021 0.023 0.023 0.023 0.025 0.023 0.022 7.9 9 21-Feb-17 28-Feb-17 0.019 0.017 0.014 0.018 0.017 0.018 0.016 0.017 0.015 0.017 0.017 8.8 10 28-Feb-17 7-Mar-17 0.026 0.026 0.023 0.025 0.023 0.029 0.025 0.024 0.023 0.025 0.025 6.9 11 7-Mar-17 14-Mar-17 0.027 0.028 0.029 0.028 0.025 0.033 0.030 0.027 0.028 0.027 0.028 6.8 12 14-Mar-17 21-Mar-17 0.040 0.045 0.042 0.036 0.040 0.045 0.041 0.039 0.042 0.039 0.041 6.9 13 21-Mar-17 27-Mar-17 0.021 0.020 0.020 0.022 0.019 0.022 0.019 0.023 0.022 0.021 0.021 6.1 Mean 0.026 0.026 0.026 0.026 0.024 0.027 0.027 0.024 0.025 0.026 0.026 3.8 Note 1: CR 18-03209 Site 35 had reduced pump runtime. Volume was 238 m^3. Sample INVALID due to insufficient sample volume Note 2: CR 17-00760 Site 15 Particulate Filter had small hole. Sample volume, filter loading, and filter deposition normal. Sample VALID.

PARTICULATE GROSS BETA IN AIR 2nd QUARTER ODCM required samples denoted by

units are pCi/m3 (control)

START STOP Site Site Site Site Site Site Site Site Site Site RSD Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Mean (%) Note 14 27-Mar-17 4-Apr-17 0.016 0.018 0.019 0.017 0.016 0.020 0.020 0.018 0.017 0.019 0.018 8.2 15 4-Apr-17 11-Apr-17 0.024 0.029 0.020 0.020 0.018 0.021 0.022 0.029 0.019 0.024 0.023 16.9 16 11-Apr-17 18-Apr-17 0.033 0.030 0.031 0.030 0.032 0.034 0.031 0.031 0.032 0.030 0.031 4.4 17 18-Apr-17 26-Apr-17 0.027 0.0181 0.022 0.025 0.024 0.028 0.021 0.024 0.023 0.024 0.024 9.1 3 18 26-Apr-17 2-May-17 0.026 0.022 0.024 0.023 0.022 0.024 0.021 0.020 0.024 0.020 0.023 7.9 19 2-May-17 9-May-17 0.029 0.022 0.026 0.027 0.027 0.025 0.027 0.027 0.027 0.026 0.026 6.4 20 9-May-17 16-May-17 0.027 0.027 0.028 0.029 0.029 0.031 0.028 0.027 0.028 0.023 0.028 7.4 21 16-May-17 23-May-17 0.023 0.023 0.023 0.022 0.022 0.025 0.023 0.024 0.023 0.024 0.023 3.8 22 23-May-17 30-May-17 0.023 0.026 0.027 0.026 0.026 0.031 0.031 0.029 0.029 0.030 0.028 9.2 23 30-May-17 6-Jun-17 0.037 0.037 0.037 0.036 0.037 0.034 0.036 0.034 0.036 0.038 0.036 3.8 24 6-Jun-17 13-Jun-17 0.026 0.024 0.025 0.025 0.026 0.030 0.028 0.027 0.026 0.027 0.026 6.1 25 13-Jun-17 20-Jun-17 0.035 0.035 0.035 0.031 0.033 0.033 0.036 0.033 0.033 0.031 0.034 4.8 26 20-Jun-17 27-Jun-17 0.040 0.037 0.040 0.037 0.039 0.045 0.041 0.040 0.042 0.043 0.040 6.3 Mean 0.028 0.028 0.027 0.027 0.027 0.029 0.028 0.028 0.028 0.028 0.028 2.6 Note 3: CR 17-06259 Site 6 pump found not running due to power supply to pole severed. Runtime 81.2 hrs of typical 168 hrs. Sample INVALID due to insufficient runtime.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 31

Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter PARTICULATE GROSS BETA IN AIR 3rd QUARTER ODCM required samples denoted by

units are pCi/m3 3rd Quarter (control)

START STOP Site Site Site Site Site Site Site Site Site Site RSD Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Mean (%) Note 27 27-Jun-17 3-Jul-17 0.040 0.030 0.037 0.035 0.032 0.035 0.034 0.034 0.037 0.037 0.035 8.1 28 3-Jul-17 11-Jul-17 0.032 0.036 0.035 0.037 0.034 0.037 0.037 0.037 0.037 0.036 0.036 5.0 29 11-Jul-17 18-Jul-17 0.028 0.027 0.030 0.030 0.029 0.031 0.031 0.030 0.031 0.034 0.030 6.5 30 18-Jul-17 25-Jul-17 0.029 0.027 0.032 0.029 0.027 0.032 0.028 0.025 0.029 0.026 0.028 8.7 4 31 25-Jul-17 1-Aug-17 0.031 0.030 0.030 0.028 0.031 0.027 0.028 0.029 0.028 0.029 4.8 4 32 1-Aug-17 8-Aug-17 0.029 0.030 0.027 0.028 0.029 0.025 0.029 0.029 0.023 0.025 0.027 8.7 33 8-Aug-17 15-Aug-17 0.034 0.028 0.032 0.036 0.032 0.033 0.032 0.030 0.031 0.034 0.032 6.9 34 15-Aug-17 22-Aug-17 0.030 0.025 0.026 0.028 0.027 0.026 0.023 0.025 0.022 0.022 0.025 10.0 35 22-Aug-17 29-Aug-17 0.035 0.032 0.029 0.034 0.032 0.034 0.032 0.032 0.032 0.032 0.032 4.4 36 29-Aug-17 5-Sep-17 0.042 0.039 0.036 0.037 0.040 0.035 0.035 0.040 0.039 0.035 0.038 6.6 37 5-Sep-17 12-Sep-17 0.044 0.035 0.039 0.042 0.041 0.044 0.041 0.038 0.041 0.041 0.041 7.0 38 12-Sep-17 19-Sep-17 0.034 0.027 0.030 0.028 0.032 0.031 0.030 0.018 0.032 0.027 0.029 15.9 39 19-Sep-17 26-Sep-17 0.029 0.031 0.028 0.026 0.026 0.026 0.027 0.030 0.026 0.032 0.028 8.0 Mean 0.034 0.031 0.032 0.032 0.031 0.032 0.031 0.030 0.032 0.031 0.032 3.2 Note 4: CR 17-10693 Site 6 pump found not running due to power failure at pole. Sample voulme 270m^3 of expected 433m^3. Sample INVALID due to insufficient sample volume PARTICULATE GROSS BETA IN AIR 4th QUARTER ODCM required samples denoted by

units are pCi/m3 (control)

START STOP Site Site Site Site Site Site Site Site Site Site RSD Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Mean (%) Note 40 26-Sep-17 3-Oct-17 0.042 0.043 0.044 0.043 0.044 0.049 0.049 0.044 0.040 0.042 0.044 6.7 41 3-Oct-17 10-Oct-17 0.041 0.038 0.038 0.038 0.038 0.042 0.040 0.039 0.038 0.038 0.039 3.8 42 10-Oct-17 17-Oct-17 0.040 0.038 0.039 0.032 0.036 0.041 0.034 0.040 0.037 0.027 0.037 11.9 43 17-Oct-17 24-Oct-17 0.033 0.033 0.034 0.035 0.035 0.035 0.034 0.034 0.034 0.035 0.034 2.2 44 24-Oct-17 31-Oct-17 0.035 0.040 0.034 0.033 0.030 0.033 0.038 0.032 0.040 0.038 0.035 10.2 45 31-Oct-17 6-Nov-17 0.036 0.033 0.031 0.034 0.035 0.033 0.031 0.035 0.031 0.032 0.033 5.5 46 6-Nov-17 14-Nov-17 0.032 0.033 0.027 0.028 0.030 0.027 0.026 0.029 0.026 0.025 0.028 9.8 47 14-Nov-17 20-Nov-17 0.046 0.038 0.028 0.027 0.034 0.029 0.030 0.026 0.032 0.031 0.032 18.3 48 20-Nov-17 28-Nov-17 0.048 0.039 0.041 0.041 0.040 0.030 0.040 0.043 0.040 0.042 0.040 11.4 49 28-Nov-17 5-Dec-17 0.057 0.053 0.053 0.047 0.056 0.050 0.054 0.052 0.050 0.052 0.052 5.6 50 5-Dec-17 12-Dec-17 0.031 0.026 0.028 0.023 0.024 0.033 0.027 0.030 0.027 0.024 0.027 11.8 51 12-Dec-17 19-Dec-17 0.048 0.047 0.048 0.045 0.042 0.043 0.045 0.047 0.046 0.045 0.046 4.5 52 19-Dec-17 26-Dec-17 0.052 0.045 0.042 0.039 0.043 0.047 0.046 0.040 0.043 0.045 0.044 8.6 Mean 0.041 0.039 0.037 0.036 0.038 0.038 0.038 0.038 0.037 0.037 0.038 4.1 Annual Average 0.03227 0.03081 0.03059 0.03013 0.02998 0.03164 0.03096 0.03009 0.03044 0.03032 0.0307 7.9144 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 32

Table 8-3 Gamma in Air Filter Composites GAMMA IN AIR FILTER COMPOSITES ODCM required samples denoted by

units are pCi/m3 (control)

QUARTER Site Site Site Site Site Site Site Site Site Site ENDPOINT NUCLIDE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Note 27-Mar-17 Cs-134 <0.002 <0.001 <0.004 <0.003 <0.003 <0.005 <0.003 <0.001 <0.006 <0.003 1, 2 Cs-137 <0.002 <0.002 <0.005 <0.003 <0.002 <0.004 <0.003 <0.002 <0.002 <0.002 27-Jun-17 Cs-134 <0.002 <0.006 <0.001 <0.004 <0.002 <0.002 <0.001 <0.004 <0.001 <0.001 3

Cs-137 <0.003 <0.008 <0.002 <0.002 <0.001 <0.002 <0.001 <0.004 <0.002 <0.001 26-Sep-17 Cs-134 <0.002 <0.004 <0.0007 <0.003 <0.002 <0.003 <0.002 <0.003 <0.002 <0.002 Cs-137 <0.002 <0.005 <0.0009 <0.002 <0.002 <0.004 <0.0009 <0.004 <0.003 <0.002 26-Dec-17 Cs-134 <0.003 <0.001 <0.0007 <0.002 <0.001 <0.004 <0.002 <0.002 <0.002 <0.001 Cs-137 <0.003 <0.002 <0.0009 <0.0005 <0.0009 <0.002 <0.002 <0.006 <0.002 <0.006 Note 1: Site 35, See Note 1 from 1st Quarter Gross Beta Note 2: Site 15, See Note 2 from 1st Quarter Gross Beta Note 3: Site 6A, See Note 3 from 2nd Quarter Gross Beta PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 33

Table 8-4 Radioiodine in Air 1st-2nd Quarter RADIOIODINE IN AIR 1st QUARTER ODCM required samples denoted by

units are pCi/m3 (control) required LLD <0.070 START STOP Site Site Site Site Site Site Site Site Site Site Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Note 1 27-Dec-16 3-Jan-17 <0.039 <0.031 <0.045 <0.031 <0.046 <0.0340 <0.045 <0.008 <0.044 <0.052 1 2 3-Jan-17 10-Jan-17 <0.024 <0.029 <0.042 <0.026 <0.033 <0.030 <0.033 <0.028 <0.018 <0.042 3 10-Jan-17 17-Jan-17 <0.036 <0.028 <0.040 <0.028 <0.041 <0.036 <0.053 <0.034 <0.017 <0.042 2 4 17-Jan-17 24-Jan-17 <0.013 <0.042 <0.013 <0.030 <0.007 <0.062 <0.034 <0.019 <0.063 <0.039 5 24-Jan-17 31-Jan-17 <0.036 <0.026 <0.027 <0.018 <0.054 <0.018 <0.034 <0.039 <0.036 <0.034 6 31-Jan-17 7-Feb-17 <0.038 <0.026 <0.042 <0.026 <0.042 <0.037 <0.055 <0.024 <0.026 <0.034 7 7-Feb-17 14-Feb-17 <0.040 <0.032 <0.032 <0.018 <0.033 <0.037 <0.061 <0.020 <0.029 <0.050 8 14-Feb-17 21-Feb-17 <0.024 <0.018 <0.047 <0.022 <0.042 <0.034 <0.012 <0.035 <0.023 <0.042 9 21-Feb-17 28-Feb-17 <0.031 <0.027 <0.034 <0.026 <0.042 <0.044 <0.033 <0.027 <0.028 <0.012 10 28-Feb-17 7-Mar-17 <0.039 <0.017 <0.037 <0.022 <0.032 <0.030 <0.041 <0.028 <0.022 <0.040 11 7-Mar-17 14-Mar-17 <0.035 <0.041 <0.044 <0.024 <0.041 <0.036 <0.028 <0.033 <0.045 <0.020 12 14-Mar-17 21-Mar-17 <0.037 <0.024 <0.036 <0.024 <0.053 <0.041 <0.036 <0.0360 <0.025 <0.013 13 21-Mar-17 27-Mar-17 <0.029 <0.032 <0.059 <0.031 <0.040 <0.041 <0.040 <0.050 <0.035 <0.067 Note 1: CR 18-03209 Site 35 had reduced pump runtime. Volume was 238 m^3. Sample INVALID due to insufficient sample volume Note 2: CR 17-00760 Site 15 Particulate Filter had small hole. Sample volume, filter loading, and filter deposition normal. Sample VALID.

RADIOIODINE IN AIR 2nd QUARTER ODCM required samples denoted by

units are pCi/m3 (control) required LLD <0.070 Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Note 14 27-Mar-17 4-Apr-17 <0.023 <0.021 <0.021 <0.035 <0.026 <0.032 <0.032 <0.038 <0.047 <0.047 15 4-Apr-17 11-Apr-17 <0.030 <0.051 <0.035 <0.035 <0.027 <0.043 <0.029 <0.056 <0.036 <0.034 16 11-Apr-17 18-Apr-17 <0.054 <0.031 <0.042 <0.019 <0.031 <0.042 <0.012 <0.039 <0.034 <0.043 17 18-Apr-17 26-Apr-17 <0.036 <0.065 <0.042 <0.028 <0.043 <0.030 <0.043 <0.025 <0.028 <0.030 3 18 26-Apr-17 2-May-17 <0.054 <0.049 <0.022 <0.067 <0.052 <0.008 <0.065 <0.033 <0.037 <0.066 19 2-May-17 9-May-17 <0.031 <0.007 <0.037 <0.037 <0.026 <0.033 <0.034 <0.050 <0.037 <0.033 20 9-May-17 16-May-17 <0.018 <0.033 <0.031 <0.026 <0.040 <0.018 <0.019 <0.007 <0.040 <0.022 21 16-May-17 23-May-17 <0.034 <0.023 <0.042 <0.023 <0.033 <0.032 <0.023 <0.027 <0.037 <0.023 22 23-May-17 30-May-17 <0.036 <0.019 <0.035 <0.024 <0.063 <0.046 <0.013 <0.050 <0.028 <0.046 23 30-May-17 6-Jun-17 <0.035 <0.022 <0.049 <0.018 <0.033 <0.033 <0.054 <0.031 <0.024 <0.035 24 6-Jun-17 13-Jun-17 <0.044 <0.025 <0.027 <0.018 <0.023 <0.031 <0.031 <0.032 <0.024 <0.029 25 13-Jun-17 20-Jun-17 <0.020 <0.024 <0.034 <0.034 <0.042 <0.039 <0.039 <0.028 <0.034 <0.039 26 20-Jun-17 27-Jun-17 <0.030 <0.026 <0.042 <0.026 <0.054 <0.040 <0.042 <0.034 <0.018 <0.035 Note 3: CR 17-06259 Site 6A pump found not running due to power supply to pole severed. Runtime 81.2 hrs of typical 168 hrs. Sample INVALID due to insufficient runtime.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 34

Table 8-5 Radioiodine in Air 3rd-4th Quarter RADIOIODINE IN AIR 3rd QUARTER ODCM required samples denoted by

units are pCi/m3 (control) required LLD <0.070 START STOP Site Site Site Site Site Site Site Site Site Site Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Note 27 27-Jun-17 3-Jul-17 <0.0216 <0.0472 <0.0261 <0.0384 <0.0381 <0.0484 <0.0449 <0.0263 <0.0487 <0.0081 28 3-Jul-17 11-Jul-17 <0.0525 <0.0366 <0.0230 <0.0108 <0.0058 <0.0292 <0.0230 <0.0428 <0.0232 <0.0292 29 11-Jul-17 18-Jul-17 <0.0067 <0.0319 <0.0413 <0.0218 <0.0405 <0.0308 <0.0121 <0.0254 <0.0468 <0.0065 30 18-Jul-17 25-Jul-17 <0.0189 <0.0609 <0.0479 <0.0253 <0.0469 <0.0334 <0.0138 <0.0207 <0.0386 <0.0338 4 31 25-Jul-17 1-Aug-17 <0.0265 <0.0118 <0.0471 <0.0064 <0.0471 <0.0261 <0.0422 <0.0225 <0.0180 4 32 1-Aug-17 8-Aug-17 <0.0484 <0.0309 <0.0666 <0.0234 <0.0452 <0.0256 <0.0690 <0.0325 <0.0337 <0.0297 33 8-Aug-17 15-Aug-17 <0.0288 <0.0404 <0.0584 <0.0315 <0.0415 <0.0186 <0.0515 <0.0219 <0.0417 <0.0333 34 15-Aug-17 22-Aug-17 <0.0070 <0.0427 <0.0590 <0.0183 <0.0494 <0.0260 <0.0393 <0.0078 <0.0574 <0.0267 35 22-Aug-17 29-Aug-17 <0.0415 <0.0554 <0.0261 <0.0339 <0.0318 <0.0418 <0.0228 <0.0334 <0.0066 <0.0596 36 29-Aug-17 5-Sep-17 <0.0069 <0.0422 <0.0350 <0.0185 <0.0501 <0.0265 <0.0433 <0.0070 <0.0502 <0.0234 37 5-Sep-17 12-Sep-17 <0.0487 <0.0478 <0.0327 <0.0492 <0.0328 <0.0121 <0.0262 <0.0540 <0.0182 <0.0553 38 12-Sep-17 19-Sep-17 <0.0480 <0.0254 <0.0116 <0.0063 <0.0462 <0.0174 <0.0567 <0.0251 <0.0531 <0.0222 39 19-Sep-17 26-Sep-17 <0.0236 <0.0320 <0.0268 <0.0442 <0.0233 <0.0329 <0.0504 <0.0235 <0.0444 <0.0240 Note 4: CR 17-10693 Site 6A pump found not running due to power failure at pole. Sample voulme 270m^3 of expected 433m^3. Sample INVALID due to insufficient sample volume RADIOIODINE IN AIR 4th QUARTER ODCM required samples denoted by

units are pCi/m3 (control) required LLD <0.070 START STOP Site Site Site Site Site Site Site Site Site Site Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40* Note 40 26-Sep-17 3-Oct-17 <0.0287 <0.0330 <0.0419 <0.0179 <0.0542 <0.0188 <0.0326 <0.0176 <0.0123 <0.0321 41 3-Oct-17 10-Oct-17 <0.0230 <0.0179 <0.0293 <0.0227 <0.0233 <0.0227 <0.0323 <0.0265 <0.0265 <0.0181 42 10-Oct-17 17-Oct-17 <0.0231 <0.0226 <0.0232 <0.0263 <0.0294 <0.0233 <0.0288 <0.0181 <0.0181 <0.0177 43 17-Oct-17 24-Oct-17 <0.0325 <0.0200 <0.0319 <0.0248 <0.0321 <0.0294 <0.0250 <0.0203 <0.0203 <0.0251 44 24-Oct-17 31-Oct-17 <0.0221 <0.0319 <0.0281 <0.0218 <0.0247 <0.0321 <0.0230 <0.0219 <0.0349 <0.0235 45 31-Oct-17 6-Nov-17 <0.0292 <0.0391 <0.0407 <0.0322 <0.0516 <0.0445 <0.0400 <0.0502 <0.0278 <0.0599 46 6-Nov-17 14-Nov-17 <0.0222 <0.0276 <0.0469 <0.0233 <0.0364 <0.0168 <0.0359 <0.0270 <0.0197 <0.0359 47 14-Nov-17 20-Nov-17 <0.0482 <0.0377 <0.0075 <0.0378 <0.0361 <0.0139 <0.0443 <0.0335 <0.0656 <0.0384 48 20-Nov-17 28-Nov-17 <0.0436 <0.0062 <0.0219 <0.0232 <0.0425 <0.0291 <0.0264 <0.0064 <0.0270 <0.0311 49 28-Nov-17 5-Dec-17 <0.0286 <0.0280 <0.0072 <0.0315 <0.0249 <0.0314 <0.0325 <0.0073 <0.0071 <0.0251 50 5-Dec-17 12-Dec-17 <0.0185 <0.0412 <0.0583 <0.0218 <0.0396 <0.0195 <0.0315 <0.0333 <0.0322 <0.0219 51 12-Dec-17 19-Dec-17 <0.0478 <0.0390 <0.0457 <0.0320 <0.0382 <0.0311 <0.0595 <0.0339 <0.0281 <0.0534 52 19-Dec-17 26-Dec-17 <0.0390 <0.0349 <0.0523 <0.0132 <0.0524 <0.0478 <0.0630 <0.0436 <0.0677 <0.0457 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 35

Table 8-6 Vegetation VEGETATION ODCM required samples denoted by

units are pCi/kg, wet

<60 <60 <80 DATE LOCATION TYPE COLLECTED I-131 Cs-134 Cs-137 Note Sample Not Available for January LOCAL Lettuce 16-Feb-17 <33 <35 <40 RESIDENCE Lettuce 16-Mar-17 <35 <21 <43 (Site #47)* Lettuce 20-Apr-17 <30 <22 <59 Lettuce 18-May-17 <52 <59 <40 Lettuce 15-Jun-17 <51 <56 <56 Sample Not Available for July Sample Not Available for August Sample Not Available for September Sample Not Available for October Sample Not Available for November Broccolli Leaf 21-Dec-17 <48 <48 <77 Lettuce 20-Jan-17 <54 <54 <47 Lettuce 16-Feb-17 <31 <39 <54 Lettuce 16-Mar-17 <23 <35 <39 Lettuce 20-Apr-17 <42 <38 <50 Spinach 20-Apr-17 <37 <35 <46 Sample Not Available for May COMMERCIAL Sample Not Available for June FARM Sample Not Available For July (Site #62)* Sample Not Available for August Sample Not Available for September Spinach 19-Oct-17 <55 <55 <47 Kale 19-Oct-17 <45 <45 <48 Arugula 19-Oct-17 <47 <51 <63 Kale 16-Nov-17 <56 <45 <42 Spinach 16-Nov-17 <44 <40 <39 Arugula 16-Nov-17 <50 <47 <76 Tango Lettuce 21-Dec-17 <60 <48 <54 Grean Oak Lettuce 21-Dec-17 <44 <39 <14 Red Leaf Lettuce 21-Dec-17 <35 <46 <69 Sample Not Available for January Sample Not Available for February Sample Not Available for March Lettuce 20-Apr-17 <54 <50 <49 Lettuce 18-May-17 <56 <44 <59 LOCAL Lettuce 16-Jun-17 <46 <59 <48 RESIDENCE Sample Not Available for July (Site #51) Sample Not Available for August Sample Not Available for September Sample Not Available for October Sample Not Available for November Sample Not Available for December PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 36

Table 8-7 Milk ODCM required samples denoted by

units are pCi/liter SAMPLE DATE LOCATION COLLECTED I-131 Cs-134 Cs-137 Ba-140 La-140 Note No Sample Available for January Local Resident No Sample Available for February Goats No Sample Available for March (Site #51)* No Sample Available for April No Sample Available for May 16-Jun-17 <1 <1 <1 <3 <1 20-Jul-17 <1 <1 <1 <3 <1 17-Aug-17 <1 <1 <1 <3 <1 21-Sep-17 <1 <1 <1 <3 <1 19-Oct-17 <1 <1 <1 <3 <1 16-Nov-17 <1 <1 <1 <3 <1 21-Dec-17 <1 <1 <1 <3 <1 26-Jan-17 <1 <1 <1 <3 <1 23-Feb-17 <1 <1 <1 <3 <1 23-Mar-17 <1 <1 <1 <3 <1 Local Resident 27-Apr-17 <1 <1 <1 <3 <1 Goats 25-May-17 <1 <1 <1 <3 <1 (Site #53)* 22-Jun-17 <1 <1 <1 <3 <1 1 27-Jul-17 <1 <1 <1 <3 <1 24-Aug-17 <1 <1 <1 <3 <1 No Sample Available for September No Sample Available for October No Sample Available for November No Sample Available for December 13-Jan-17 <1 <1 <1 <3 <1 Local Resident 09-Feb-17 <1 <1 <1 <3 <1 Goats 09-Mar-17 <1 <1 <1 <3 <1 (Site #54)* 13-Apr-17 <1 <1 <1 <3 <1 11-May-17 <1 <1 <1 <3 <1 09-Jun-17 <1 <1 <1 <3 <1 20-Jul-17 <1 <1 <1 <3 <1 10-Aug-17 <1 <1 <1 <3 <1 14-Sep-17 <1 <1 <1 <3 <1 13-Oct-17 <1 <1 <1 <3 <1 09-Nov-17 <1 <1 <1 <3 <1 14-Dec-17 <1 <1 <1 <3 <1 Note 1: CR 17-10463 Due to software malfunction, Site 53 MDA achived for I-131 was 1.05 pCi/L, 0.05 above the required 1 pCi/L LLD PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 37

Table 8-8 Drinking Water DRINKING WATER ODCM required samples denoted by

units are pCi/liter

<2000 SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 Qtrly <4.0 LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Gross Beta Note 31-Jan-17 <5 <5 <11 <5 <10 <5 <10 <6 <5 <5 <19 <12 5.04s

28-Feb-17 <6 <6 <11 <6 <12 <6 <11 <5 <6 <6 <17 <10 3.87s1.95 27-Mar-17 <12 <10 <28 <12 <27 <12 <18 <9 <11 <11 <28 <14 <323 <1.88 26-Apr-17 <9 <7 <20 <10 <16 <12 <20 <14 <7 <9 <38 <22 6.26s2.07 1 LOCAL 30-May-17 <9 <12 <21 <12 <26 <12 <19 <9 <11 <9 <29 <14 5.33s1.92 RESIDENCE 27-Jun-17 <12 <12 <20 <7 <24 <15 <21 <11 <11 <10 <35 <13 <326 4.03s2.01 (Site #48)

25-Jul-17 <1 <1 <2 <1 <2 <2 <2 <2 <0.9 <1 <5 <14 5.56s1.95 3 29-Aug-17 <7 <8 <17 <8 <18 <9 <15 <8 <8 <10 <23 <15 4.37s1.92 26-Sep-17 <12 <12 <23 <15 <29 <13 <22 <11 <14 <10 <40 <13 <205 <3.29 31-Oct-17 <8 <5 <16 <7 <18 <7 <13 <7 <6 <8 <25 <14 5.55s1.79 28-Nov-17 <15 <10 <25 <13 <28 <13 <19 <10 <12 <12 <31 <9 6.07s1.78 26-Dec-17 <12 <12 <21 <13 <26 <14 <22 <11 <13 <15 <39 <14 <306 <3.09 31-Jan-17 <7 <6 <13 <7 <13 <7 <10 <6 <6 <7 <21 <12 5.93s1.91 28-Feb-17 <7 <7 <17 <6 <17 <9 <14 <8 <7 <8 <24 <11 2.27s0.95 27-Mar-17 <15 <15 <23 <14 <29 <13 <24 <13 <12 <13 <37 <11 <323 <1.99 26-Apr-17 <13 <9 <21 <9 <19 <11 <20 <18 <9 <12 <46 <211 5.72s1.93 2 LOCAL 30-May-17 <9 <10 <17 <11 <17 <11 <19 <9 <9 <12 <33 <11 5.40s1.85 RESIDENCE 27-Jun-17 <9 <8 <15 <9 <20 <8 <19 <9 <7 <10 <32 <14 <329 6.84s2.02 (Site #55) 25-Jul-17 <0.9 <1 <.2 <0.9 <2 <2 <.2 <.2 <0.8 <0.8 <5 <15 3.55s1.78 3 29-Aug-17 <8 <7 <15 <5 <15 <6 <12 <7 <6 <7 <25 <12 5.63s1.85 26-Sep-17 <8 <6 <13 <7 <17 <7 <13 <7 <7 <7 <23 <14 <200 3.27s1.95 31-Oct-17 <11 <9 <21 <9 <20 <10 <11 <9 <9 <13 <37 <14 <3.90 28-Nov-17 <10 <11 <21 <6 <24 <12 <18 <8 <8 <9 <27 <12 <3.91 26-Dec-17 <7 <9 <16 <7 <16 <8 <15 <9 <8 <8 <29 <15 <363 4.19s1.90 5 Note 1: CR 17-10476 LLD for La-140 not met due to error in sample collection date input into analysis software Note 2: CR 17-10476 LLD for I-131 and La-140 not met due to error in sample collection date input into analysis software Note 3: Long count time to achieve LLDs resulted in lower than typical MDAs on most nuclides. Long count time due to extensive time between sample acquisition and analysis time Note 5: CR 18-01383 Oringal analysis indicated possible Co-58 activity. Confirmatory count was done; verified no Co58 activity present.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 38

Table 8-8 Drinking Water (Continued)

DRINKING WATER ODCM required samples denoted by

units are pCi/liter

<2000 SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 Qtrly <4.0 LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Gross Beta Note 31-Jan-17 <5 <5 <8 <4 <9 <4 <8 <4 <4 <4 <15 <8 2.85s1.37 28-Feb-17 <13 <13 <21 <13 <26 <14 <23 <13 <11 <13 <42 <7 2.62s1.33 27-Mar-17 <11 <9 <23 <12 <17 <11 <16 <9 <8 <10 <29 <12 <325 3.65s1.54 26-Apr-17 <12 <9 <23 <12 <29 <13 <19 <17 <8 <10 <50 <185 3.14s1.47 2 30-May-17 <10 <8 <23 <7 <17 <9 <17 <8 <8 <6 <34 <14 2.32s1.34 LOCAL 27-Jun-17 <9 <9 <17 <6 <19 <11 <15 <9 <8 <7 <26 <14 <327 3.77s1.88 RESIDENCE 25-Jul-17 <1 <1 <3 <1 <3 <1 <2 <3 <1 <1 <7 <15 <2.19 3 (Site #46)

29-Aug-17 <5 <7 <12 <5 <13 <6 <10 <5 <6 <6 <19 <15 4.57s1.79 26-Sep-17 <12 <8 <18 <9 <24 <11 <17 <8 <9 <11 <33 <13 <209 3.35s1.92 31-Oct-17 <7 <6 <11 <6 <12 <5 <11 <6 <5 <6 <21 <12 <3.83 28-Nov-17 <9 <10 <20 <10 <25 <12 <16 <8 <9 <12 <39 <6 <3.80 26-Dec-17 <11 <12 <20 <11 <22 <10 <19 <9 <10 <11 <34 <12 <365 3.35s1.81 31-Jan-17 <7 <7 <11 <7 <14 <7 <13 <8 <7 <8 <26 <13 3.44s1.38 28-Feb-17 <9 <8 <17 <7 <20 <9 <15 <8 <7 <8 <26 <13 2.87s1.33 27-Mar-17 <7 <8 <13 <7 <16 <8 <13 <7 <7 <6 <22 <12 <324 <1.41 26-Apr-17 <12 <12 <27 <11 <21 <14 <19 <17 <12 <11 <50 <200 <2.13 2 30-May-17 <11 <11 <19 <10 <27 <11 <17 <11 <10 <12 <36 <14 2.94s1.36 LOCAL 27-Jun-17 <10 <10 <15 <11 <23 <10 <17 <7 <9 <13 <30 <15 <327 <2.89 RESIDENCE 25-Jul-17 <0.9 <0.9 <2 <1 <2 <0.9 <1 <2 <0.7 <1 <5 <150 <2.10 3 and 4 (Site #49)

29-Aug-17 <9 <10 <20 <9 <20 <9 <15 <9 <10 <11 <34 <12 3.30s1.72 26-Sep-17 <7 <5 <13 <7 <14 <8 <11 <6 <5 <7 <22 <14 <194 <2.98 31-Oct-17 <9 <10 <15 <10 <22 <10 <18 <8 <7 <9 <29 <14 <3.76 28-Nov-17 <8 <8 <16 <11 <21 <12 <17 <9 <8 <11 <33 <14 <3.75 26-Dec-17 <6 <6 <13 <5 <12 <6 <11 <5 <5 <6 <17 <11 <365 <2.79 Note 2: CR 17-10476 LLD for I-131 and La-140 not met due to error in sample collection date input into analysis software Note 3: Long count time to achieve LLDs resulted in lower than typical MDAs on most nuclides. Long count time due to extensive time between sample acquisition and analysis time Note 4: CR 18-00109 LLD for La-140 not met due to extensive time between sample acquisition and analysis PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 39

Table 8-9 Groundwater GROUNDWATER ODCM required samples denoted by

units are pCi/liter SAMPLE DATE <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 <2000 LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Notes 1-Feb-17 **Out of Service**

WELL 27ddc 25-Apr-17 <13 <11 <19 <12 <28 <14 <23 <11 <11 <13 <37 <8 <322 (Site #57)* 25-Jul-17 <7 <7 <13 <8 <14 <8 <12 <7 <5 <7 <22 <15 <363 26-Sep-17 <13 <10 <23 <12 <26 <14 <18 <10 <12 <11 <35 <12 <341 19-Dec-17 <9 <8 <16 <8 <18 <8 <15 <7 <7 <10 <27 <13 <364 1-Feb-17 <10 <9 <18 <8 <20 <12 <16 <9 <8 <7 <34 <15 <335 WELL 34abb 25-Apr-17 **Out of Service** 1 (Site #58)* 27-Jun-17 <13 <11 <20 <13 <26 <13 <23 <12 <10 <13 <38 <13 <328 25-Jul-17 <7 <7 <16 <7 <17 <8 <12 <7 <6 <8 <24 <14 <369 26-Sep-17 <13 <14 <22 <11 <27 <14 <20 <11 <12 <12 <38 <15 <341 19-Dec-17 <11 <9 <17 <10 <22 <13 <19 <9 <11 <12 <34 <14 <370

- Not in Service**

Well 34aab 27-Jun-17 <14 <11 <23 <12 <26 <13 <19 <9 <12 <13 <37 <13 <328 1 25-Jul-17 <9 <11 <19 <12 <21 <13 <18 <11 <8 <11 <34 <13 <370 19-Dec-17 <8 <8 <12 <8 <16 <8 <14 <7 <7 <7 <25 <12 <368 Note 1: On Site deep wells under construction. Site 58 was out of service during sampling period. Supplemental sampling occurred in June for Site 58 and new deep well under construction PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 40

Table 8-10 Surface Water ODCM re quire d sample s de note d by

units are pCi/lite r SAMPLE DATE LOCATION COLLECTED Mn-54 Co-58 Fe -59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Note s 1-Feb-17 <11 <10 <13 <10 <16 <10 <18 13s9 <9 <11 <31 <11 <335 45 ACRE 25-Apr-17 <10 <11 <21 <10 <23 <10 <16 <9 <10 <11 <26 <13 <323 RESERVOIR 25-Jul-17 <10 <10 <23 <13 <26 <11 <20 <13 <9 <14 <42 <14 <371 (Site #61)

26-Sep-17 <10 <8 <18 <11 <17 <9 <16 <13 <8 <7 <24 <11 <344 19-Dec-17 <8 <8 <15 <8 <17 <8 <16 <9 <8 <9 <24 <14 <362 1-Feb-17 <12 <10 <14 <8 <23 <10 <19 <15 <9 <12 <33 <15 <334 85 ACRE 25-Apr-17 <10 <10 <16 <9 <23 <12 <19 <10 <9 <13 <35 <13 <323 RESERVOIR 25-Jul-17 <8 <9 <23 <10 <24 <10 <18 <14 <10 <13 <30 <14 <371 (Site #60)

26-Sep-17 <10 <10 <19 <11 <17 <10 <16 <10 <10 <9 <31 <13 <341 19-Dec-17 <9 <10 <16 <9 <23 <11 <18 8s8 <10 <12 <30 <11 <363 1-Feb-17 <6 <6 <15 <7 <14 <7 <10 8s5 <6 <7 <20 <10 1342s223 EVAP POND 1 25-Apr-17 <11 <12 <22 <14 <29 <12 <21 <12 <13 <11 <40 <14 1680s220 (Site #59)

25-Jul-17 <10 <8 <11 <10 >19 <11 <14 <12 <8 <11 <33 <13 1212s219 CELL 1A 26-Sep-17 <13 <9 <26 <13 <25 <10 <21 <9 <12 <13 <33 <13 1263s200 19-Dec-17 **No Influent Since Last Sample**

1-Feb-17 **No Influent Since Last Sample**

25-Apr-17 **No Influent Since Last Sample**

CELL 1B 25-Jul-17 **No Influent Since Last Sample**

19-Dec-17 <10 <10 <17 <10 <19 <13 <19 <12 <9 <12 <30 <9 402s218 1-Feb-17 **No Influent Since Last Sample**

25-Apr-17 <12 <10 <29 <11 <26 <12 <19 <9 <7 <12 <34 <9 <320 1 CELL 1C 25-Jul-17 <5 <5 <11 <6 <13 <5 <10 <6 <6 <6 <21 <15 1363s220 19-Dec-17 **No Influent Since Last Sample**

1-Feb-17 <9 <8 <19 <10 <20 <7 <15 <7 <5 <6 <30 <13 1168s220 EVAP POND 2 25-Apr-17 **No Influent Since Last Sample**

(Site #63)

25-Jul-17 **No Influent Since Last Sample**

CELL 2A 26-Sep-17 <10 <10 <21 <11 <30 <10 <19 <10 <10 <9 <35 <7 505s200 19-Dec-17 <11 <11 <27 <12 <24 <11 <17 <10 <8 <8 <28 <9 673s211 1-Feb-17 **No Influent Since Last Sample**

25-Apr-17 **No Influent Since Last Sample**

CELL 2B 25-Jul-17 **No Influent Since Last Sample**

19-Dec-17 <10 <10 <23 <10 <24 <11 <19 <9 <8 <11 <34 <9 720s215 2 1-Feb-17 **No Influent Since Last Sample**

EVAP POND 3 **No Influent Since Last Sample**

25-Apr-17 (Site #64)

25-Jul-17 **No Influent Since Last Sample**

CELL 3A 19-Dec-17 <10 <11 <24 <11 <29 <11 <17 <7 <9 <12 <27 <7 505s210 1-Feb-17 **No Influent Since Last Sample**

25-Apr-17 <13 <9 <27 <15 <24 <12 <21 <10 <10 <14 <32 <8 464s198 CELL 3B 25-Jul-17 <11 <9 <24 <14 <23 <10 <19 <8 <10 <14 <28 <11 577s206 19-Dec-17 **No Influent Since Last Sample**

Note 1: H-3 results abnormally low. Sample unavailable for reanalysis. Similar results found in subsequent sample led to discovery of reporting error.

Results considered INVALID. CR 18-00638 Note 2: Tritium sample duplicated and averaged.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 41

Table 8-10 Surface Water (Continued)

SURFACE WATER ODCM required samples denoted by

units are pCi/liter SAMPLE DATE LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Notes 3-Jan-17 <8 <7 <19 <9 <18 <10 <15 17s9 <7 <7 <29 <14 10-Jan-17 <10 <10 <21 <8 <23 <11 <21 8s6 <9 <11 <32 <10 17-Jan-17 <7 <7 <16 <9 <17 <6 <12 18s9 <6 <7 <23 <7 24-Jan-17 <15 <22 <19 <23 <39 <21 <32 30s22 <22 <26 <84 <12 3 31-Jan-17 <10 <7 <14 <8 <24 <10 <15 <11 <5 <9 <24 <9 <350 7-Feb-17 <11 <11 <22 <10 <18 <10 <18 17s6 <10 <10 <32 <13 14-Feb-17 <6 <6 <11 <6 <13 <6 <10 21s8 <5 <7 <23 <13 21-Feb-17 <11 <9 <18 <8 <22 <11 <16 13s9 <8 <7 <27 <14 28-Feb-17 <12 <9 <20 <12 <24 <12 <20 <12 <9 <12 <33 <15 <357 7-Mar-17 <4 <5 <10 <6 <10 <6 <10 26s7 <5 <5 <18 <10 14-Mar-17 <13 <13 <44 <17 <48 <21 <22 <32 <16 <22 <79 <32 4 21-Mar-17 <9 <8 <21 <10 <21 <9 <17 33s11 <8 <10 <28 <7 28-Mar-17 <10 <8 <16 <8 <20 <8 <15 24s9 <7 <8 <29 <12 <337 WRF 4-Apr-17 <13 <13 <20 <12 <29 <12 <22 40s12 <10 <13 <36 <11 INFLUENT 11-Apr-17 <11 <11 <20 <11 <23 <10 <15 17s9 <10 <12 <32 <6 18-Apr-17 WRF OUTAGE- No Sample 25-Apr-17 <8 <7 <14 <10 <21 <7 <13 11s8 <7 <7 <26 <11 <342 2-May-17 <11 <10 <20 <10 <25 <13 <21 16s9 <12 <10 <36 <14 9-May-17 <9 <11 <14 <11 <20 <11 <17 24s10 <9 <11 <30 <12 16-May-17 <8 <9 <15 <8 <16 <8 <14 18s10 <8 <8 <29 <10 23-May-17 <8 <9 <14 <7 <23 <6 <12 15s9 <7 <7 <27 <14 <342 30-May-17 <11 <10 <15 <10 <22 <10 <16 18s8 <9 <11 <31 <10 <349 6-Jun-17 <10 <10 <19 <10 <27 <9 <15 <12 <10 <10 <37 <15 13-Jun-17 <10 <10 <20 <9 <17 <8 <15 <10 <10 <9 <31 <12 20-Jun-17 <9 <11 <18 <7 <14 <11 <17 <10 <9 <10 <27 <13 27-Jun-17 <9 <9 <13 <7 <25 <10 <16 <11 <7 <8 <28 <12 <341 3-Jul-17 <10 <11 <17 <8 <21 <10 <16 <10 <7 <9 <25 <8 11-Jul-17 <9 <11 <18 <9 <21 <11 <18 9s8 <8 <10 <30 <15 18-Jul-17 <11 <11 <16 <11 <14 <11 <18 <12 <8 <10 <29 <10 Note 3: Several LLDs not achieved due to incorrect volume entered into analysis system. CR 17-17823 Note 4: Several LLDs not achieved due to delay in sample analysis. CR 17-04054 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 42

Table 8-10 Surface Water (Continued)

SURFACE WATER ODCM required samples denoted by

units are pCi/liter SAMPLE DATE <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 <3000 LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Note 25-Jul-17 <11 <9 <17 <9 <21 <9 <14 18s10 <7 <9 <31 <12 <372 1-Aug-17 <10 <11 <18 <10 <17 <8 <15 <10 <9 <10 <33 <8 8-Aug-17 <9 <8 <13 <7 <20 <9 <15 <13 <9 <7 <31 <10 15-Aug-17 <10 <9 <20 <10 <15 <11 <15 15s9 <8 <9 <30 <15 22-Aug-17 <12 <10 <18 <12 <24 <10 <18 9s8 <8 <10 <24 <13 29-Aug-17 <11 <11 <20 <11 <24 <12 <19 <12 <10 <12 <28 <9 <354 5-Sep-17 <10 <8 <18 <7 <22 <10 <17 <12 <7 <9 <29 <10 12-Sep-17 <10 <10 <20 <7 <22 <10 <13 36s11 <9 <9 <25 <12 19-Sep-17 <11 <12 <21 <9 <24 <9 <19 <13 <8 <9 <30 <12 26-Sep-17 <8 <7 <13 <10 <21 <8 <15 20s10 <7 <8 <28 <10 <350 3-Oct-17 <10 <9 <17 <11 <23 <12 <15 13s8 <7 <7 <29 <14 10-Oct-17 WRF OUTAGE- No Sample WRF 17-Oct-17 WRF OUTAGE- No Sample INFLUENT 24-Oct-17 <11 <11 <22 <9 <25 <14 <21 12s <11 <12 <36 <9 31-Oct-17 <9 <11 <21 <10 <26 <8 <16 14s9 <8 <9 <33 <12 <359 7-Nov-17 <6 <6 <11 <6 <11 <6 <10 11s6 <5 <6 <18 <15 14-Nov-17 <8 <11 <15 <10 <24 <9 <16 <19s9 <9 <7 <31 <12 21-Nov-17 <11 <11 <18 <8 <20 <9 <21 45s12 <12 <10 <35 <8 28-Nov-17 <10 <9 <24 <11 <17 <11 <18 <13 <9 <11 <31 <14 <350 5-Dec-17 <12 <8 <18 <8 <22 <9 <16 14s7 <8 <9 <24 <10 12-Dec-17 <9 <5 <14 <8 <15 <7 <15 11s9 <6 <7 <29 <9 19-Dec-17 <7 <8 <24 <14 <23 <10 <15 9s9 <7 <7 <29 <14 26-Dec-17 <9 <10 <18 <9 <19 <9 <17 <11 <7 <7 <33 <10 <380 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 43

Table 8-10 Surface Water (Continued)

SURFACE WATER ODCM required samples denoted by

units are pCi/liter SAMPLE DATE LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Note 3-Jan-17 <11 <9 <19 <9 <21 <10 <17 <9 <8 <10 <31 <15 <350 10-Jan-17 EMPTY- No Sample 17-Jan-17 EMPTY- No Sample 24-Jan-17 <20 <20 <33 <5 <32 <16 <42 <20 <16 <23 <69 <20 <356 3 31-Jan-17 EMPTY- No Sample 7-Feb-17 EMPTY- No Sample 14-Feb-17 EMPTY- No Sample 21-Feb-17 <11 <11 <19 <9 <28 <11 <16 <10 <9 <10 <40 <14 595s218 28-Feb-17 <9 <10 <17 <7 <28 <11 <17 <8 <9 <11 <38 <13 <352 7-Mar-17 EMPTY- No Sample 14-Mar-17 EMPTY- No Sample 21-Mar-17 EMPTY- No Sample 28-Mar-17 EMPTY- No Sample SEDIMENTATION BASIN #2 4-Apr-17 EMPTY- No Sample 11-Apr-17 EMPTY- No Sample 18-Apr-17 EMPTY- No Sample 25-Apr-17 EMPTY- No Sample 2-May-17 EMPTY- No Sample 9-May-17 EMPTY- No Sample 16-May-17 EMPTY- No Sample 23-May-17 EMPTY- No Sample 30-May-17 EMPTY- No Sample 6-Jun-17 EMPTY- No Sample 13-Jun-17 EMPTY- No Sample 20-Jun-17 EMPTY- No Sample 27-Jun-17 EMPTY- No Sample Note 3: Several LLDs not achieved due to incorrect volume entered into analysis system. CR 17-17823 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 44

Table 8-10 Surface Water (Continued)

ODCM required samples denoted by

units are pCi/liter SAMPLE DATE LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Note 3-Jul-17 EMPTY- No Sample 11-Jul-17 EMPTY- No Sample 18-Jul-17 EMPTY- No Sample 25-Jul-17 <6 <6 <12 <5 <13 <5 <11 <6 <6 <6 <20 <14 <330 1-Aug-17 EMPTY- No Sample 8-Aug-17 EMPTY- No Sample 15-Aug-17 EMPTY- No Sample 22-Aug-17 <14 <11 <27 <12 <29 <13 <24 <10 <10 <10 <9 <349 29-Aug-17 EMPTY- No Sample 5-Sep-17 EMPTY- No Sample 12-Sep-17 EMPTY- No Sample 19-Sep-17 EMPTY- No Sample SEDIMENTATION 26-Sep-17 EMPTY- No Sample BASIN #2 3-Oct-17 EMPTY- No Sample 10-Oct-17 EMPTY- No Sample 17-Oct-17 EMPTY- No Sample 24-Oct-17 EMPTY- No Sample 31-Oct-17 EMPTY- No Sample 7-Nov-17 EMPTY- No Sample 14-Nov-17 EMPTY- No Sample 21-Nov-17 EMPTY- No Sample 28-Nov-17 EMPTY- No Sample 5-Dec-17 EMPTY- No Sample 12-Dec-17 EMPTY- No Sample 19-Dec-17 EMPTY- No Sample 26-Dec-17 EMPTY- No Sample PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 45

Table 8-11 Sludge/Sediment SLUDGE/SEDIMENT ODCM required samples denoted by

units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED I-131 Cs-134 Cs-137 In-111 Notes 3-Jan-17 <68 <106 10-Jan-17 482s163 <118 <168 17-Jan-17 291s156 <80 <114 24-Jan-17 192s138 <40 <135 31-Jan-17 <137 <168 7-Feb-17 788s229 <148 <155 14-Feb-17 695s184 <107 <118 21-Feb-17 200s133 <127 <178 28-Feb-17 277s163 <61 <143 7-Mar-17 <94 <141 14-Mar-17 469s152 <109 <93 21-Mar-17 <102 <171 WR 28-Mar-17 632s165 <117 <102 CENTRIFUGE 4-Apr-17 331s91 <51 <81 WASTE SLUDGE 11-Apr-17 562s186 <128 <180 18-Apr-17 WR OUTAGE 25-Apr-17 <116 <102 2-May-17 <100 <111 9-May-17 724s169 <109 <162 16-May-17 891s195 <109 <123 23-May-17 919s186 <106 <146 30-May-17 467s151 <137 <120 6-Jun-17 959s215 <145 <148 13-Jun-17 654s201 <140 <159 20-Jun-17 679s176 <90 <144 27-Jun-17 348s131 <90 <158 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 46

Table 8-11 Sludge/Sediment (Continued)

ODCM required samples denoted by

units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED I-131 Cs-134 Cs-137 In-111 Notes 3-Jul-17 351s147 <146 <162 11-Jul-17 487s151 <35 <30 18-Jul-17 359s144 <126 <143 25-Jul-17 353s44 <23 <23 1-Aug-17 498s191 <146 <143 8-Aug-17 323s137 <106 <163 15-Aug-17 <108 <155 22-Aug-17 314s128 <113 <169 29-Aug-17 364s162 <129 <321 5-Sep-17 415s177 <143 <51 12-Sep-17 481s162 <32 <178 19-Sep-17 264s143 <143 <177 WR 26-Sep-17 427s143 <109 <305 CENTRIFUGE WASTE SLUDGE 3-Oct-17 510s164 <147 <155 10-Oct-17 423s161 <115 <42 17-Oct-17 WR OUTAGE 24-Oct-17 510s138 <81 <80 31-Oct-17 481s141 <65 <30 7-Nov-17 375s139 <74 <162 14-Nov-17 646s161 <94 <82 21-Nov-17 523s161 <93 <177 28-Nov-17 302s122 <122 <116 5-Dec-17 363s139 <146 <145 12-Dec-17 <125 <151 19-Dec-17 299s169 <139 <119 26-Dec-17 215s120 <146 <169 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 47

Table 8-11 Sludge/Sediment (Continued)

Cooling Tower Sludge Unit Cycle Approximate Volume Isotope Activity Range (pCi/g) Sample Type (yd3)

All principal gamma-U2R20 302 <MDA Towers/Canal Sludge emitters All principal gamma-U1R20 512 <MDA Towers/Canal Sludge emitters Table 8-12 Hard -To-Detect Radionuclide Results Hard-To-Detect Radionuclide (pCi/Liter)

Sample Location Well number Sample Date C-14 Fe-55 Ni-63 Sr-90 Unit 1 (outside RCA) APP-12 11/9/2017 <66.7 <18.3 <2.39 <1.58 Unit 2 (inside RCA) H0A 11/3/2017 <67.1 <21.5 <2.68 <1.06 Unit 3 (inside RCA) H11 10/24/2017 <67.9 <19.9 <3.19 <1.03 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 48

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9. Thermoluminescent Dosimeter (TLD) Results and Data The environmental TLD used at PVNGS is the Panasonic Model 812 Dosimeter. The Model 812 is a multi-element dosimeter combining two elements of lithium borate and two elements of calcium sulfate under various filters.
TLDs were placed in fifty locations from one to thirty-five miles from the PVNGS. TLD locations are shown in Figure 2-1 and Figure 2-2 and are described in Table 9-1. TLD results for 2017 are presented in Table 9-2. Definitions for Table 9-2 are as follows:
MDDQ: Minimum differential dose, quarterly, 3 times 90th percentile sQ determined from analysis (mRem).
MDDA: Minimum differential dose, annual, 3 times 90th percentile sA determined from analysis (mRem).
BQ: Quarterly baseline (mRem) (average of previous 5 years)
MQ: Locations 91 day standard quarter normalized dose (mRem per standard quarter)
LQ: Quarterly investigation level dose (mRem)
BA: Baseline background dose (mRem) (annual)
MA: Annual monitoring data - MA determined by normalizing available quarterly data to 4 full quarters LA: Annual investigation level dose (mRem)
ND: Non Detectable The baseline is calculated as the average of the previous 5 year measurements. The minimum differential dose (MDD) is calculated as 3times the 90th percentile standard deviation of the data from the previous 5 years; quarterly MDD is calculated using the quarterly data and annual MDD is calculated using the annual summation of the quarterly data. Investigation level is calculated by the difference of the data measurement and the baseline; results less than, or equal to the MDD are Non Detectable (ND) and any result exceeding the MDD meets the threshold for the investigation level.
Locations exceeding the investigation level will be evaluated for cause and impact to the public and environment.
Historical environmental gamma radiation results for 1985 through 2017 are presented in graphical form on Figure 9-1 (excluding transit control TLD #45). Figure 9-2 depicts the environmental TLD results from 2017 as compared to the pre-operational TLD results (excluding sites #41 and #43, as they were deleted and later assigned to a new location, and #46-50, as they had no pre-op TLD at the location for comparison). The site to site comparisons indicate a direct correlation with respect to pre-operational results. It is indicated that the offsite dose, as measured by TLDs, has not changed since Palo Verde became operational.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 57
Table 9-1 TLD Site Locations (Distance and direction are relative to Unit 2 in miles)
Distance Distance Distance TLD# Location TLD# Location TLD# Location firom Unit 2 from Unit 2 from Unit 2 1 E30 29.13 18 ESE2 1.48 35 NNVV'8 7.86 2 ENE24 24.18 19 SE2 1.35 36 N5 4.32 3 E21 21.87 20 SSE2 2.04 37 NNE5 4.69 4 E16 16.05 21 S3 2.68 38 NE5 4.21 5 ESEll 11.14 22 SSW3 2.74 39 ENE5 4.71 6 SSE31 31.47 23 W5 4.17 40 N2 2.37 7 SE7 6.87 24 SW4 3.75 41 ESE3 3.39 8 SSE4 4.33 25 WSW5 4.88 42 N8 7.24 9 S5 4.63 26 SSW4 4.13 43 NE5 4.60 10 SE5 3.91 27 SWl 0.93 44 ENE35 35.00 11 ESE5 5.14 28 WSWl 0.66 45 Onsite 0.18 12 E5 4.85 29 W1 0.64 46 ENE30 7.23 13 N1 0.85 30 WWVl 0.74 47 E35 32.35 14 NNE2 155 31 NWl 1.03 48 E24 22.76 15 NE2 1.63 32 NNWl 0.90 49 ENEll 11.32 16 ENE2 1.59 33 NW4 4.05 50 WNW^5 4.24 17 E2 1.39 34 NNW5 4.84
~~Site #6 and site #44 are the control locations.~~
~~Site #45 is the transit control TLD (stored in lead pig).~~
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 58
Table 9-2 Environmental TLD Results Palo Verde 2017 MDDQ: 5 mrem Palo Verde 2017 MDDA: 10 mrem Quarterly (mrem) Annual (mrem)
Site BQ MQQ1 MQQ2 MQQ3 MQQ4 LQQ1 LQQ2 LQQ3 LQQ4 BA MA LA 1 25.1 25.9 25.1 25.8 25.5 ND ND ND ND 100.4 102.3 ND 2 22.5 23.2 22.4 22.4 21.4 ND ND ND ND 89.9 89.4 ND 3 24.3 25.1 24.7 23.2 23.3 ND ND ND ND 97.2 96.3 ND 4 24.8 26.9 23.6 25.5 24.4 ND ND ND ND 99.3 100.5 ND 5 22.2 20.4 19.6 20.1 19.6 ND ND ND ND 89.0 79.8 ND 6 27.0 28.3 28.0 27.8 - ND ND ND - 107.8 84.0 ND 7 25.8 26.5 26.6 25.2 26.8 ND ND ND ND 103.3 105.1 ND 8 24.1 24.8 24.9 24.6 24.6 ND ND ND ND 96.5 98.9 ND 9 28.6 29.2 27.9 28.6 28.9 ND ND ND ND 114.5 114.5 ND 10 24.2 25.2 24.5 24.7 23.6 ND ND ND ND 96.6 97.9 ND 11 25.3 25.4 24.9 24.8 26.3 ND ND ND ND 101.3 101.4 ND 12 23.7 23.2 24.6 24.0 24.1 ND ND ND ND 94.8 95.9 ND 13 26.0 26.2 25.7 26.0 25.5 ND ND ND ND 104.1 103.5 ND 14 25.3 25.4 25.7 25.7 25.0 ND ND ND ND 101.3 101.8 ND 15 23.9 24.2 23.7 23.3 24.5 ND ND ND ND 95.6 95.7 ND 16 22.7 23.7 23.4 23.5 23.2 ND ND ND ND 91.0 93.8 ND 17 25.0 26.1 25.5 24.5 25.0 ND ND ND ND 100.2 101.1 ND 18 23.7 24.4 23.2 22.6 23.4 ND ND ND ND 94.7 93.6 ND 19 25.8 26.0 24.9 24.9 25.3 ND ND ND ND 103.4 101.1 ND 20 24.6 25.5 25.0 24.4 24.8 ND ND ND ND 98.5 99.6 ND 21 26.1 26.0 27.7 26.0 25.3 ND ND ND ND 104.3 105.0 ND 22 26.5 26.9 25.5 25.9 26.3 ND ND ND ND 106.1 104.7 ND 23 23.6 23.8 24.0 23.0 22.9 ND ND ND ND 94.3 93.7 ND 24 23.1 23.9 22.4 22.0 22.7 ND ND ND ND 92.3 91.1 ND 25 23.8 24.4 23.1 23.8 23.5 ND ND ND ND 95.1 94.8 ND 26 27.9 28.5 28.3 28.8 28.0 ND ND ND ND 111.6 113.6 ND 27 27.3 28.2 28.7 27.4 26.7 ND ND ND ND 109.0 111.0 ND 28 26.2 27.8 26.7 25.7 25.2 ND ND ND ND 104.7 105.4 ND 29 24.7 24.8 24.1 25.1 25.2 ND ND ND ND 98.6 99.2 ND 30 26.1 26.7 26.9 26.0 26.3 ND ND ND ND 104.5 106.0 ND 31 23.7 24.3 23.8 23.1 23.5 ND ND ND ND 94.6 94.6 ND 32 25.9 25.4 26.0 25.9 25.4 ND ND ND ND 103.5 102.8 ND 33 26.3 26.2 26.3 26.3 25.7 ND ND ND ND 105.3 104.4 ND 34 28.1 29.0 28.5 27.5 28.3 ND ND ND ND 112.5 113.4 ND 35 31.4 32.5 33.9 30.9 30.8 ND ND ND ND 125.6 128.2 ND 36 26.6 26.6 27.6 25.6 25.4 ND ND ND ND 106.3 105.1 ND 37 24.3 25.3 24.4 23.6 23.7 ND ND ND ND 97.2 96.9 ND 38 27.8 28.9 27.0 28.0 28.4 ND ND ND ND 111.1 112.2 ND 39 24.7 25.8 24.8 24.0 23.7 ND ND ND ND 98.6 98.2 ND 40 25.4 26.1 25.0 25.6 24.6 ND ND ND ND 101.5 101.4 ND 41 26.9 27.4 26.7 27.8 26.0 ND ND ND ND 107.7 107.9 ND 42 27.8 29.0 27.6 27.4 26.5 ND ND ND ND 111.2 110.5 ND 43 27.9 29.0 28.6 28.8 27.0 ND ND ND ND 111.5 113.4 ND 44 23.8 24.4 25.2 23.7 23.6 ND ND ND ND 95.3 96.9 ND 45 5.9 6.2 5.9 5.9 5.3 ND ND ND ND 23.5 23.3 ND 46 24.4 24.5 24.4 24.5 24.3 ND ND ND ND 97.5 97.8 ND 47 24.2 24.1 24.7 24.0 23.3 ND ND ND ND 96.7 96.1 ND 48 24.7 25.4 24.1 24.5 23.6 ND ND ND ND 98.7 97.6 ND 49 23.1 23.2 23.2 23.3 22.0 ND ND ND ND 92.4 91.8 ND 50 19.9 20.4 19.2 19.6 19.6 ND ND ND ND 79.7 78.9 ND PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 59
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~~10. Land Use Census 10.1 Introduction In accordance with the PVNGS ODCM, Section 6.2, the field portion of the annual Land Use Census was performed by June 2017.~~
Observations were made in each of the 16 meteorological sectors to determine the nearest milking animals, residences, and gardens of greater than 500 square feet. This census was completed by driving the roads and speaking with residents.
The results of the Land Use Census are presented in Table 10-1 and discussed below. The directions and distances listed are in sectors and miles from the Unit 2 containment.
10.2 Census Results The 2017 Land Use Census results have identified a new potential Radiological Effluent Release Report dose receptor location. Condition Report 18-04530 was generated to document the changes identified since the 2016 Land Use Census. Each location was evaluated. Below describes the changes identified and the evaluation results.
Nearest Resident There was one ( 1 ) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.590 mrem.
Milk Animal There were three ( 3 ) c h a n ge s in milk animal status from the previous year. The locations were visited by the REMP manager to evaluate program participation potential. As of December 2017, none of the locations had goats. Dose calculations indicated the highest dose to be 0.660 mrem.
Vegetable Gardens There were three (3) changes in nearest garden status from the previous year. One garden had a calculated dose lower than gardens currently in REMP. One garden location was removed due to absence of garden.
One garden was evaluated and found to not currently meet the ODCM required size of 500 square feet, nor growing broadleaf vegetation; however, this location is being monitored for possible future inclusion in REMP. Dose calculations indicated the highest dose to be 0.590 mrem.
See Table 10-1 for a summary of the specific results and Table 2-1 for current sample locations.
Figure 10-1through Figure 10-3 provide graphs depicting historical calculated doses for nearest residents, nearest milk receptor, and nearest garden receptor locations in each sector.
Differences in calculated doses are the result of many variables, including; Changes in receptor locations from year to year (proximity to the power plant)
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 62
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)
Nearest Milk Nearest Nearest Calculated Dose Change from Sector Animal Resident Garden (mrem) 2016 (Cow/Goat)
Resident 5.50E-2 Garden N 1.55 1.71 1.94 Garden 2.77E-1 Milk Milk 2.49E-1 Resident 7.87E-2 Garden NNE 1.52 NONE 3.05 Milk 2.86E-1 Resident 5.90E-1 Garden NE 2.16 2.16 4.40 Garden 5.90E-1 Milk Milk 2.53E-1 Resident 1.03E-1 ENE 2.05 4.84 4.84 Garden 1.85E-1 Milk 1.85E-1 E 2.81 NONE NONE Resident 7.68E-2 ESE 1.95 NONE NONE Resident 1.85E-1 Resident 1.22E-1 Resident SE 3.40 NONE 3.99 Milk 6.60E-1 Milk SSE NONE NONE NONE NA S NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.37E-1 WSW 0.75 NONE NONE Resident 1.43E-1 W 0.70 NONE NONE Resident 8.48E-2 WNW NONE NONE NONE NA NW 0.93 NONE NONE Resident 7.02E-2 Resident 6.93E-2 NNW 1.30 4.34 NONE Garden 8.03E-2 Comments:
Dose calculations were performed using GASPAR code and 2016 meteorological data and source term.
Dose reported for each location is the total for all three PVNGS Units and is the highest individual critical organ dose identified.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 63
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11. Summary and Conclusions Summary The conclusions are based on a review of the radioassay results and environmental gamma radiation measurements for the 2017 calendar year. Where possible, the data were compared to pre-operational sample data.
All sample results for 2017 are presented in Table 8-1 through Table 8-12 and do not include observations of naturally occurring radionuclides, with the exception of gross beta in air and gross beta in drinking water. Table 11-1 summarizes the ODCM required samples and is in the format required by the NRC BTP on Environmental Monitoring.
I-131 identified in the evaporation ponds, Water Resources influent, Water Resources centrifuge sludge, and reservoirs is the result of offsite sources and appears in the effluent sewage from Phoenix. The levels of I-131 detected in these locations are consistent with levels identified in previous years.
Tritium concentrations identified in surface water onsite have been attributed to PVNGS permitted gaseous effluent releases and secondary plant releases. These concentrations are consistent with historical values.
Environmental radiation levels are consistent with measurements reported in previous Pre-operational and Operational Radiological Environmental annual reports, References 1 and 2.
Conclusion There was no measurable radiological impact on the environment in 2017 resulting from the operation of PVNGS.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 67
Table 11-1 Environmental Radiological Monitoring Program Annual Summary TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
~~SUMMARY~~
Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530 Maricopa County, Arizona Calendar Year 2017 Medium or Type and Lower Limit All Location with Highest Control Number of Pathway Total Number of Detection Indicator Annual Mean Locations Nonroutine Sampled of Analyses (LLD) (from Locations Reported (Unit of Performed Table 6.1) Measurements Measurement) Mean (f)a Name Mean (f)a Mean (f)a Range Distance and Range Range Direction Direct TLD - 199 NA 25.3 Site #35 32.1 (4/4) 25.8(8/8) 1 Radiation (187/188)
(mrem/std. 19.2 - 33.9 8 miles 30.8 - 33.9 23.6 - 28.3 qtr.) 330° Air Gross Beta - 0.01 0.031 Site # 4 0.033 0.031 (49/52) 5 Particulates 519 (467/468) (52/52)
(pCi/m3) 0.014 - 16 miles 0.016 - 0.017 - 0.053 0.057 92º 0.053 Gamma Spec Composite -
40 Cs-134 0.05 <LLD NA <LLD <LLD 0 (quarterly)
<LLD NA <LLD <LLD Cs-137 0.06 <LLD NA <LLD <LLD 0 (quarterly)
<LLD NA <LLD <LLD Air Gamma Spec. -
Radioiodine 519 (pCi/m3) I-131 0.07 <LLD NA <LLD <LLD 5
<LLD NA <LLD <LLD

Broadleaf Gamma Spec. -
Vegetation 23 (pCi/Kg-wet) I-131 60 <LLD NA <LLD <LLD 0 Cs-134 60 <LLD NA <LLD <LLD 0 Cs-137 80 <LLD NA <LLD <LLD 0 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 68
Groundwater H 12 2000 <LLD NA <LLD NA 0 (pCi/liter)
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 - 4 4.23 (31/48) Site #48 5.12 (9/12) NA 0 48 2.27 - 6.84 1 mile 236° 3.87 -6.26 H 16 2000 <LLD NA <LLD NA 0 Gamma Spec. -
48 Drinking Mn-54 15 <LLD NA <LLD NA 0 Water Fe-59 30 <LLD NA <LLD NA 0 (pCi/liter)
Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 I-131 15 <LLD NA <LLD NA 3 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 5 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 69
Gamma Spec. -
27 Milk I-131 1 <LLD NA <LLD <LLD 1 (pCi/liter) <LLD NA <LLD <LLD Cs-134 15 <LLD NA <LLD <LLD 0
<LLD NA <LLD <LLD
Cs-137 18 <LLD NA <LLD <LLD 0
<LLD NA <LLD <LLD
Ba-140 60 <LLD NA <LLD <LLD 0
La-140 15 <LLD NA <LLD <LLD 0 Gamma Spec. -
24 Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 Surface Water I-131 15 10 (3/36) Site #61 13 (1/4) NA 0 (pCi/liter) 8-13 Onsite 67° 13-13

Cs-134 15 <LLD NA <LLD NA 0
Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 H 25 3000 913 Site #59 1374 (4/4) NA 1 (13/36)
402 - 1680 Onsite 1212-1680
180° (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.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 70
~~12. References~~
~~1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985~~
~~2. 1985-2016 Annual Radiological Environmental Operating Reports, Palo Verde Nuclear Generating Station~~
~~3. Palo Verde Nuclear Generating Station Technical Specifications and Technical Reference Manual~~
~~4. Offsite Dose Calculation Manual, Revision 27, PVNGS Units 1, 2, and 3~~
~~5. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants~~
~~6. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants~~
~~7. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG-1301)~~
~~8. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007~~
~~9. "Sources of Radiation." NRC: Sources of Radiation. Nuclear Regulatory Commission, 2 Oct. 2017.~~
~~Web. 21 Feb. 2018.~~
~~10. "NCRP Report No. 160: Ionizing Radiation Exposure of the Population of the United States."~~
Journal of Radiological Protection J. Radiol. Prot. 29.3 (2009): 465. Web.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 71
Appendix A PaloVerde' M h H I 1 s ; a i 11: 4 Company Correspondence IDl 218-04261-MLC Datei 21 March 2018 To:
Sta #
Ext #
CC; Fromi Michelle Comolli Sta# 7397 Ext # 82-3130
~~Subject:~~
~~Correction to the 2016 "Annual Radiological Environmental Operating Report"~~
~~Dear Sir or Ma'am:
In accordance tiidi Palo Verde Nudear Generating Station (P\'NGS)Tedinical Specification (IS) 5.6^, PM^GS submitted die Annud Radiological Enwomnental Operating Report (ARE0R)for 2016 \ia Reference 1. It was discot-ered diat diete were erroninlbe l*Qiuiter 2016R£MPTLDdata. The retired data is 0^ te 0.4 mrem'standard quarter bigber dm the original rq>ort This deviation was limited d> die first quarter of 2016. This deviation is document dtrough Coarectn'e Action Program document E\*AL 17-08097-001.
Attached << dte corrected Table 9-2 Environmental TLD Restdti firom die 2016 AREOR.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 72
Table 9-2 En^iionmental TLD Results Palo Vcnt>> 2016 MDIV}: Stnran Palo Verde 2016 MDDjc lOmrcm QaartB^ (inremQ
.loQ3 1 24.7 255 255 259 274 ND ND NO NO 988 1052 ND 2 22a 22.7 234 214 248 ND ND ND ND 898 954 ND t 23.9 251 256 238 259 ND ND ND ND 957 1004 ND 4 244 254 268 235 256 ND ND ND NO 975 1052 ND E 224 244 21.9 194 215 ND ND ND ND 894 859 ND 6 26S 252 294 268 284 ND ND ND ND 1050 1124 ND 7 254 27.1 288 258 284 ND ND ND ND 1018 1084 ND 8 23.7 251 254 235 255 ND ND ND ND 957 1004 ND 9 284 251 295 274 304 ND ND ND ND 1134 1157 ND 10 23L9 254 254 235 268 ND ND ND NO 955 1004 ND 11 248 257 278 234 259 ND ND ND NO 994 1044 ND 12 234 24.5 258 22.9 245 ND ND ND ND 934 97.7 ND IS 254 259 274 248 278 ND ND ND NO 1025 104.9 ND 14 258 259 274 244 254 ND ND ND ND 1004 1034 ND 15 23.7 24.3 255 224 257 ND ND ND 957 97.7 ND 16 224 251 248 225 274 ND ND ND 885 956 ND 17 248 255 259 244 264 ND ND ND ND 994 1035 ND 18 255 251 244 228 259 ND ND NO ND 938 978 ND 19 254 257 256 248 274 ND ND ND ND 1053 104.3 ND 20 244 234 264 251 268 ND ND NO ND 978 995 ND 21 258 259 268 254 278 ND ND HO HD 1034 1068 ND 22 264 257 284 25.7 284 ND ND NO ND 1048 108.0 ND 23 254 256 259 257 259 ND ND ND ND 928 988 ND 24 2^7 250 244 224 244 ND ND NO ND 90.7 944 ND 25 255 234 244 234 245 ND ND ND ND 944 954 ND 26 274 251 284 252 304 ND ND HD ND 110.4 1138 ND 27 274 256 298 264 285 ND ND ND ND 1084 1114 ND 28 259 253 258 254 274 ND ND ND ND 103.7 1058 ND 29 244 253 268 224 254 ND ND NO NO 984 988 ND so 257 27.9 294 258 278 ND ND ND NO 1059 109.7 ND 31 253 248 251 22-1 254 ND ND ND ND 934 974 ND 32 256 253 268 259 274 ND ND ND NO 1055 1034 ND 33 259 278 284 257 288 ND ND ND NO 1057 1098 ND 34 278 284 304 278 29.9 ND ND ND ND 1151 1164 ND 35 308 325 352 308 359 ND ND NO NO 1234 130.4 ND 36 264 278 250 254 27.7 ND ND ND ND 1048 1084 ND 37 248 244 254 234 258 ND ND ND ND 964 984 NO 38 274 288 29.9 274 308 ND ND ND ND 1094 116.1 ND 39 244 250 268 234 264 ND ND NO NO 974 1004 ND 40 250 258 253 258 259 ND NO NO NO 1008 1057 ND 41 254 256 252 258 27.9 ND NO NO ND 1057 1085 ND 42 284 253 294 254 294 ND ND HO ND 1153 1153 ND 43 274 288 305 278 288 ND ND NO ND 1105 1144 ND 44 22.7 252 257 238 254 ND ND ND NO 918 1004 NO 45 59 59 64 57 68 ND NO ND ND 234 254 NO 46 244 245 253 248 255 ND NO NO ND 984 994 ND 47 258 256 254 238 254 ND ND ND ND 954 989 ND 48 244 252 274 234 264 ND ND ND ND 974 1028 ND 49 225 234 254 228 254 ND ND ND ND 904 951 ND 50 195 253 259 195 259 NO NO NO NO 784 824 ND Site 16, East Kortfaeast Site Boundaiy znonitoriiig locatLon, has a qaaitedy baseline of 22.1149 mrem and a standanlized fonidi qaaiter reading of27.2641 mrem, for a fouth quarter measurement of5.1492 mrem. This measurement is 0.1492 mrem above die mwn'nTinn detectable dose, occurring onfy at diis location and only during the fourth quarter. This es'ent PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2016 Page 59 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2017 Page 73

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