Text

Annual Radiological Environmental Operating Report 2016
	ML17115A496
Person / Time
Site:	Palo Verde
Issue date:	04/21/2017
From:	Weber T; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-07486-TNW/MDD/TMJ
	Download: ML17115A496 (78)
	v • d • e

Qaps Technical Specification 5.6.2 Palo Verde Nuclear Generating Station PO Box 52034 Phoenix, Arizona 85072-2034 Maii Station 7636 102-07486-TNW/MDD/TMJ April 21, 2017 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, and 3 Docket Nos. STN 50-528/529/530 Annual Radiological Environmental Operating Report 2016 In accordance with PVNGS Technical Specification 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2016.

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

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

Reason: I am approving this document Date: 2017.04.21 10:14:43-0700' Weber, Thomas N(Z00499)

Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/TMJ/sma

Enclosure:

Palo Verde Nuclear Generating Station Annual Radiological Environmental Operating Report 2016 cc: K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency (ARRA)

Arizona Radiation Regulatory Agency (ARRA)

M. M. Watford C. A. Peabody A. V. Godwin T. Morales 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 2016

PALO VERDE NUCLEAR GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2016

(

Reference:

RCTSAI 1643, Legacy Item No. 036843.01)

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!£ Prepared by:_

Comolli, Michelle (Z09567)

Digitally signed by Comolli, Michelle (Z09567)

DN: cn=Comolli, Michelle (Z09567)

Date: 2017.04.13 19:34:55 -07'00' Routolo, Robert ar"'°"°

Reviewed by:.

M(Z99739)

DN: cn=Routolo, Robert M(Z99739)

Reason: I have reviewed this document Date: 2017.04.13 20:00:46 -07'00' Moeller, Carl Approved by: (Z09119)

Digitally signed by Moeller, Carl

{Z09119)

DN:cn=Moeller,Carl {Z09119)

Date: 2017.04.14 12:24:28 -07'00' Manager, Radiation Protection

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 2016..................................4 2.3 REMP Deviations/Abnormal Events Summary..................................................................5 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 4.3 Milk.................................................................................................................................15 4.3.1 Gamma Spectroscopy...............................................................................................15 4.3.2 Radiochemical 1-131 Separation................................................................................15 4.4 Vegetation....................................................................................................................... 15 4.4.1 Gamma Spectroscopy......................... 15 4.5 Sludge/Sediment..............................................................................................................16 4.5.1 Gamma Spectroscopy........................ 16 4.6 Water................................... 16 4.6.1 Gamma Spectroscopy............................................................................................... 16 4.6.2 Tritium..................................................................................................................... 16 4.6.3 Gross Beta................................................................................................................ 16 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page i

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 WRF Centrifuge Waste Sludge................................................................................. 30 8.8.2 Cooling Tower Sludge..............................................................................................30 8.9 Data Trends.....................................................................................................................30 8.10 Hard-To-Detect Radionuclide Results........................................................................... 30

9.

Thermoluminescent Dosimeter (TLD) Results and Data................................................... 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-2016 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 lst-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 lst-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-2016 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, lst-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 (2009-2016)...................................................... 55 Figure 8-8 Sedimentation Basin 2 Cs-137................................................................................. 56 Figure 9-1 Network Environmental TED Exposure Rates.........................................................60 Figure 9-2 Environmental TLD Comparison-Pre-Operational versus 2016................................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 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 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 2016, 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 Radiation Regulatory Agency (ARRA) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by ARRA include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) Deep Wells. Offsite samples analyzed by ARRA include two (2) local resident wells. ARRA also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring locations, eighteen (18) of which are duplicates of APS locations.

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

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 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 2016. All references are specifically identified in Section 12.

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

The Land Use Census ensures that changes in the use of areas at, and beyond the site boundary, are identified and that modifications to the REMP are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR Part 50.

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

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

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 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: occupations, consumer products, nuclear medicine, and medical procedures. There are a number of occupational areas which result in exposure to individuals of varying amounts of radiation such as: radiography, radiology, radiation oncology, power generation, and research laboratories. The Nuclear Regulatory Commission (NRC) requires licensees to monitor exposure to workers and limit occupational exposure to 5,000 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 2%

Industrial/Occupational 0.1%

Nuclear Medicine 12%

Thoron 37%

rocedures 36%

Internal 5%

Cosmic Terrestrial 3%

Figure 1-1 Sources of Radiation Exposure in the United States PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 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 2.1, 2.2 and 9.1. Additional onsite sampling (outside the scope of the ODCM) is performed to supplement the REMP. All results are included in this report. Routine sample analyses were performed at the onsite Central Chemistry Laboratory and Operating Unit laboratories.

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

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

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

2.2 Radiological Environmental Monitoring Program Changes for 2016 New Vegetation Sample Location The 2015 Land Use Census results identified a new Radiological Environmental Monitoring Program (REMP) garden sample location. Per the Land Use Census procedure, 74RM-0EN07 Revision 14, a Condition Report shall be generated if a new sample location is identified that yields a 20% greater dose to an indicator location than current indicator locations. The new vegetation indicator location's calculated dose is 2.05E-01 mrem versus a criterion of 1.99E-01 mrem. This sampling location was included as supplemental data for 2015 and was included in the 2015 AREOR. This sampling location is included in the REMP, as a required location as annotated in the ODCM, Revision 27, beginning in 2016.

Surface Water Sampling Frequency In March, 2016, the quarterly grab samples of the onsite Evaporation Ponds were reduced. It is no longer required to sample from the cells within an onsite Evaporation Pond if the Evaporation Pond has not received any influent since the time of the last PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 4

sample collection. This reduction does not reduce the effectiveness of the REMP because no exposure pathway is being monitored through the collection of this sample. Thirty years of operational data have shown that the radioactive effluent controls in place sufficiently limit the amount of radioactivity being released to the Evaporation Ponds.

Reporting Methods for Direct Radiation Monitoring Revision 1 of Regulatory Guide 4.13 (July 1977) endorsed, with exceptions, American National Standards Institute (ANSI) N545 (1975) "Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), which has since been superseded by the American National Standards Institute/Health Physics Society (ANSI/HPS) N13.37 (2014),

"Environmental Dosimetry. While Palo Verde is not committed to Regulatory Guide 4.13, the proposed revision and ANSI N13.37 were evaluated to identify programmatic improvements.

To gain alignment with the most current industry guidance, the following changes were made for reporting TLD results in the Annual Radiological Environmental Operating Report:

Baseline: Pre-operational data was the method used to establish baseline background dose, which is not in alignment with the guidance outlined in ANSI N13.37. Additionally, it has been recognized that changes to geographical conditions at various direct radiation monitoring locations have occurred. Baseline dose rates for each TLD location based on recent data, not to exceed a 10 year data set, to be updated periodically, not to exceed a periodicity of every 10 years.

Reporting Data: Environmental TLD data was reported in units of rem/hour.

To align with reporting harmonization efforts, data is now converted and reported in units of mrem/quarter and mrem per year for the Annual Radiological Environmental Operating Report (AREOR).

Deviation Identification: The recommended Minimum Detectable Dose (MDD) is 5 mrem. The investigation level for TLD locations is defined as a field TLD result greater than 5 mrem more than baseline quarterly or 10 mrem annual.

2.3 REMP Deviations/Abnormal Events Summary During calendar year 2016, there were nineteen (19) deviations/abnormal events with regards to the monitoring program. Refer to Table 2-3 for more detail and corrective actions taken.

There were eight (8) 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. Five (5) events were due to reduced sample volume resulting from power interruption to the sample station. The reduced sample volume was significant enough in two of the sampling periods that the two samples in question were determined to be invalid. One (1) event was attributed to defective pump vanes which were discovered due to the failure of pumps following routine PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 5

maintenance in which the pump vanes had been replaced. The defective vanes in inventory have been identified and pulled from the supply and replaced. Two (2) of the events were attributed to equipment age. Six new pumps have been purchased to replace pumps that have lengthy service time and have begun showing signs of degradation. All events have been evaluated and corrective measures have been taken when necessary to prevent recurrence.

Six (6) events were in inability to meet a LTD. Three (3) of these events involved the control Milk sample location. Site 53, which did not meet the LTD for 1-131 (1 pCi/L). These events were attributed to a software malfunction and power disruption. There was no detectable activity in this sample and the LTD that was achieved, with the exception of one event, was below the action level. Three (3) events were samples did not meet the LTD for La-140 (15 pCi/L). The Drinking Water sample from Site 49 had no detectable activity, and the MDA achieved was below the action level. The Influent Water Reclamation Facility Surface Water samples achieved an MDA below the action level and had no detectable plant-related radioactivity.

Two (2) events were an exceedance of the quarterly 1-131 reporting level of 20 pCi/L. One event occurred at Evaporation Pond 2B, third calendar quarter. The other event occurred at the 45 Acre Reservoir, third calendar quarter. The source is radiopharmaceutical 1-131 that originates in the Phoenix sewage effluent that supplies makeup to the Reservoirs and Circulating Water system. This water is wasted to the Evaporation Ponds. This is not a plant effluent.

Two (2) events involved environmental TED locations. Site 16 was temporarily relocated approximately 140 feet, due to construction activities. Site 50 TED housing was found damaged; however, the TLDs inside the housing were undamaged and the data was obtainable and valid.

The last event was an inability to obtain a drinking water sample due to the residents well pump being out of service. Volume for the monthly composite was achieved.

2.4 Groundwater Protection PVNGS has implemented a groundwater protection initiative developed by the Nuclear Energy Institute (NEl). The implementation of this initiative, NEl 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-2016 Page 6

Table 2-1 Sample Collection Locations SITE#

SAMPLE TYPE 1

K LOCATION (a)

LOCATION DESCRIPTION 4

Air E16 APS Office 6A*

Air SSE13 Old US 80 7A Air ESE3 Arlington School 14A Air NNE2 37U* Ave. and Buckeye-Salome Rd.

15 Air NE2 NE Site Boundary 17A Air E3 35UAve.

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 SWl Local resident 49 Drinking Water N2 Local resident 51 Milk NNE3 Local resident-goats Vegetation NNE3 Local resident 53*

Milk NE30 Local resident-goats 54 Milk NNE4 Local resident-goats 55 Drinking Water (Supplemental)

SW3 Local resident 57 Groundwater ONSITE Well 27ddc 58 Groundwater ONSITE Well 34abb 59 Surface Water ONSITE Evaporation Pond 1 60 Surface Water ONSITE 85 Acre Reservoir 61 Surface Water ONSITE 45 Acre Reservoir 62*

Vegetation ENE26 Commercial Farm 63 Surface Water ONSITE Evaporation Pond 2 64 Surface Water ONSITE Evaporation Pond 3 NOTES:

Designates a control site (a) Distances and direction are from the center-line of Unit 2 containment and rounded to the nearest mile Air sample sites designated with the letter A are sites that have the same site number as a TLD location, but are not in the same location (e.g. site #6 TLD location is different from site #6A air sample location; site #4 TLD location is the same as site #4 air sample location)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 7

Table 2-2 Sample Collection Schedule SAMPLE SITE#

AIR PARTICULATE MILK AIRBORNE RADIOIODINE VEGETATION GROUND WATER drinking WATER SURFACE 1 4

W W

6A W

W 7A W

W 14 A 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-2016 Page 8

Table 2-3 Summaries of the REMP Deviations/Abnormal Events 1 Deviation/Abnormal

\\

Event Actions Taken

1. Air Sample Site 15 sample found inoperable sample period 12/28/2016-1/5/2016.

Air Sample Site 15 pump was found inoperable. Event documented through CR 16-00293 and cause determined to be due to pump vane failures limited to recent shipment of rebuild kits Results for these samples found to be fNVALID for sample period 12/28/2015-1/5/2016. Pump not in service for sample period 1/5/2016-1/12/2016, for repairs. Pump returned to service 1/12/2016; no further issues for this sample location. Event documented through CR 16-00293 (Table 8-1 and Table 8-4, Note 1 and 2)

2. Air Samples Site 35 lost power during sample period 3/22/2016-3/29/2016.

Technician discovered approximately half the sampling period was not logged in the Elapse Time Meter. This meter runs any time there is power to it and the equipment was functional at time of discovery. APS corporate and Buckeye office was contacted for a cause for loss of power. It was verified that breakers were tripped and power was out much of the week to sample location. Sample fNVALID due to duration. Event documented through CR 16-05393 (Table 8-1, Note 4 and Table 8-4, Note 3).

3. Air Sample Site 6A found with no power to the pole 4/26/2016.

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

Troubleman found disconnection above the transformer in the open position. Configuration corrected. Normal volume per sample period is approximately 433 m^. Volume for this sampling period was 371 m^. Sample determined to be VALID for sample period 4/19/2016-4/26/2016. Event documented through CR 16-07039 (Table 8-1, Note 5 and Table 8-4, Note 4).

4. Air Sample Site 40 found with no power at the pole 4/26/2016 Air Sample Site 40 was found to have no power at the pole.

Troubleman was dispatched and configuration was corrected.

Normal volume per sample period is approximately 433 m^

Volume for this sampling period was 122 m^. Pump ran for 47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months and sample was determined to be INVALID for sample period 4/19/2016-4/26/2016, due to duration. Event documented through CR 16-07041 (Table 8-1, Note 6 and Table 8-4, Note 5).

5. Air Sample Site 17A had reduced volume due to loss of power for sample period 4/26/2017-5/10/2016.

Technician found Air Sample Site 17A without power on 5/3/2016.

Problem corrected during following sampling period. Normal volume per sample period is approximately 433 m^. Sample period 4/26/2016-5/3/2016 sample volume was 398 m^. Sample period 5/3/2016-5/10/2016 sample volume was 482 m\\ Sample determined to be VALID. Event documented through CR 16-07547 (Table 8-1, Note 7 and Table 8-4, Note 6).

6. Air Sample Site 6A had reduced volume due to loss of power for sample period 7/26/2016-8/2/2016.

Air Sample Pump at Site 6A had less than normal volume.

Technician verified with APS that there was power loss due to a storm during the sample period. Volume for this sampling period was 278 m^. Sample is VALID. Event documented through CR 16-15958 (Table 8-2, Note 8 and Table 8-5, Note 7).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 9

7. Air Sample Site 40 found energized but not running 8/9/2016.

Technician found REMP Air Sample Pumps at Site 40 energized but not running. Carbon vanes had catastrophic damage. Vanes determined to be correct QC vanes. Pump removed from service.

Six new pumps purchased to replace pumps showing signs of degrading performance. Results for these samples found to be INVALID for sample period 8/2/2016-8/9/2016. Event documented through CR 16-12915 (Table 8-2, Note 9 and Table 8-5, Note 8).

8. Air Sample Site 29 found not running 10/18/2016 Air Sample Pumps at Site 29 was found not running. Carbon vanes had catastrophic damage. Failure of pup attributed to age. Pump was removed from service. Six new pumps purchased to replace pumps showing signs of degrading performance as a result of previous pump failure. Results for these samples found to be INVALID for sample period 10/11/2016-10/18/2016. Event documented through CR 16-16919 (Table 8-2, Note 10 and Table 8-5, Note 9).

9. Missed 1-131 LLD for Control Location Site 53 Milk Sample 2/25/2016 Analysis of Milk Sample from Site 53 did not meet 1-131 LLD of 1 pCi/L (achieved MDA of 1.3 pCi/L). Due to long count time, milk samples are analyzed over the weekend. Missed LLD attributed to APEX malfunction resulting in insufficient count time. Event documented through CR 16-03398 (Table 8-7, Note 1).

10. Missed 1-131 LLD for Control Location Site 53 Milk Sample 8/18/2016 Analysis of Milk Sample from Site 53 did not meet 1-131 LLD of 1 pCi/L (achieved MDA of 1.1 pCi/L). Due to long count time, milk samples are analyzed over the weekend. Missed LLD attributed to power outage due to storm, resulting in computer reboot and prior to sufficient count time. Event documented through CR 16-13413 (Table 8-7, Note 2).

11. Missed 1-131 LLD for Control Location Site 53 Milk Sample 11/17/2016 Analysis of Milk Sample from Site 53 did not meet 1-131 LLD of 1 pCi/L (achieved MDA of 4.5 pCi/L). Due to long count time, milk samples are analyzed over the weekend. Missed LLD attributed to power outage due to storm, resulting in insufficient count time.

Attempt to obtain another sample was unsuccessful. Evaluation of the equipment identified faulty USB cable. Cable was replaced.

Event documented through CR 16-18989 (Table 8-7, Note 3).

12. Missed La-140 LLD for Drinking Water Sample Site 49 2/23/2016.

Analysis of Drinking Water Sample from Site 49 did not meet La-140 LLD of 15 pCi/L (achieved MDA of 17 pCi/L). Event documented through CR 16-12485 (Table 8-8, Note 1).

13. Evaporation Pond 2B exceeded 3rd Quarter I-131 reporting level of 20 pCi/L and Tritium value of 1058 pCi/L, resulting in a unity value of greater than 1.0 (one).

The 3rd Quarter 2016 Evaporation Pond 2B sample had detectable I-1313 activity (initial count of 16.6 pCi/L, recount concentration of 23.6 pCi/L). The sample also had detectable Tritium level of 1058 pCi/L, which did not exceed the reporting level of 20,000 pCi/L.

The Unity value for the two detectable radionuclides was calculated to be 1.10, with 1-131 accounting for 95% of the unity value. The elevated 1-131 concentrations, originate from radiopharmaceuticals in Phoenix Influent (CRDR 4568037). This occurrence is documented through CR 16-20205 (Table 8-10, Note 1).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 10

14. A 45 Acre Reservoir 3^

Quarter sample exceeded the 1-131 reporting level of 20 pCi/L.

15. Missed La-140 LLD for Influent Water Sample 12/6/2016.

16. Delayed Influent Sample resulted in not being included in composite analysis and missed La-140 LLD 12/28/2016.

17. Site 16 TLD location temporarily relocated

18. Site 50 TLD case found damaged during 3^

Quarter change-out.

19. Site 55 Drinking Water sample not collected due to resident well pump not functioning 8/23/2016 The 45 Acre Reservoir had an initial detectable activity that did not exceed the ODCM Reporting Level, and a validating sample which did exceeded the 1-131 action/reporting level of 20 pCi/liter (15.3 pCi/L 1-13, and recount concentration of 30.3 pCi/L). The elevated 1-131 concentrations, originating from radiopharmaceuticals in Phoenix Influent (CRDR 4568037). This occurrence is documented through CR 16-20205 (Table 8-10, Note 1).____________________

Analysis of Surface Water Sample for Water Reclamation Influent did not meet La-140 LLD of 15 pCi/L (achieved MDA of 16 pCi/L). This location is not an ODCM required sampling site; it is sampled for trending purposes. Event documented through CR 17-00810 (Table 8-10, Note 1).

A weekly sample of WRF influent water was collected on 12/28/16, after the normal weekly 12/27/16 sample collection run. The sample was not identified as missing until 1/10/17. Due to the decay time, the La-140 LLD of 15 pCi/L (achieved MDA of 79 pCi/L) was not met. This sample was also not included in the monthly composite analysis. This location is not an ODCM required sampling site; it is sampled for trending purposes. Event documented through CR 17-00435 (Table 8-10, Note 2 and 3).

During E* Quarter Change-out, it was discovered the Site 16 TLD had been moved by persons unknown about 140 feet north of its previous location. The old location shows signs of pre-construction.

The TLD was returned to original location during the following Quarter. The TLD remained in the same sampling sector. Event was documented through CR 16-05408._______________________

The case holding the two TLDs used for monitoring location 50 has damage and appears to have been shot. The TLDs were not damaged. Processing results appear normal and are consistent with historical readings. Event documented through CR 16-10552._____

Weekly residential drinking water sample was not collected for Site 55 during the 4* week of August. Drinking Water is analyzed monthly and is a composite of weekly sampling. August had 5 weeks in 2016. Due to a sample collected the following week, the August Drinking Water sample for Site 55 was analyzed per the normal process. Event was documented through CR 16-13516.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 11

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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 Reclamation Facility (WRF), and analyzed for gamma-emitting radionuclides.

A monthly composite was analyzed for tritium.

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

3.3 Milk Goat milk samples were collected monthly, as available, and were analyzed for gamma-emitting radionuclides, including low level 1-131.

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 WRF 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 WRF sludge landfill.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 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 The charcoal cartridge is counted on a multichannel analyzer equipped with a HPGe detector. The resulting spectrum is analyzed by a computer for lodine-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 1-131 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 Cul. The precipitate is mounted in a planchet and counted for gross beta.

4.4 Vegetation 4.4.1 Gamma Spectroscopy The sample is pureed in a food processor, placed in a one liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides and verified by trained technicians.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 15

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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 16

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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 17

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 2a counting error. All results that are less than the MDA are reported as less than values at the associated MDA. For example, if the MDA is 12 pCi/liter, the value is reported as <12.

Typical MDA values are presented in Table 6-3.

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

Background fluctuations Unavoidably small sample sizes The presence of interfering radionuclides Self-absorption corrections Decay corrections for short half-life radionuclides Other uncontrollable circumstances In these instances, the contributing factors will be noted in the table where the data are presented. A summary of deviations/abnormal events is presented in Table 2-3 Summaries of the REMP Deviations/Abnormal Events and includes a description of any sample results that did not meet a priori LLD requirements.

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 18

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.

LTD 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

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).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 19

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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 20

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

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(pCid)

(pCi/kg, wet)

Gross Beta 4

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Mn-54 15 Fe-59 30 Co-58,-60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 1**

0.07 1

60 Cs-134 15 0.05 15 60 Cs-137 18 0.06 18 80 Ba-140 60 60 La-140 15 15

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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 21

Table 6-2 ODCM Required Reporting Levels Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/I) or Gas (pCi/m*i (pCiA)

(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-La-140 200 300

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

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 22

Table 6-3 Typical MDA Values Analysis/Nuclide Water (pCi/liter)

Milk (pCi/liter)

Airborne Particulate or Gas (pCi/m^)

Vegetation (pCi/kg, wet)

Gross Beta 2.08 0.004 H-3 326 Mn-54 10 Fe-59 20 Co-58 9

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La-140 13 1

NOTES:

a - low level 1-131 is not required since there is no drinking water pathway b - Based on 433 m^ the normal weekly sample volume PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 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 2016, APS analyzed the following sample types under the interlaboratory comparison program:

Beta/Gamma/ in A ir F ilter 1-131 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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 24

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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.

Random errors are beyond the control of the analyst.

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

The "plus or minus value" reported with each analytical result represents the counting error associated with the result and gives the 95% confidence (2a) 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 2016 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 0.013 to 0.058 pCi/m^ 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. Radio iodine was not observed in any samples.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 28

8.3 Vegetation Table 8-6 presents gamma isotopic data for the vegetation samples. No gamm'a-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 6.24 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. 1-131 was observed in both reservoirs and Evaporation Pond lA The 1-131 levels ranged from 6 pCi/L-23 pCi/L. 1-131 in these surface water locations is a result of radiopharmaceutical 1-131 in the Phoenix sewage effluent and is not attributable to plant effluents.

Tritium was routinely observed in the Evaporation Ponds. The highest concentration was 2197 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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 29

8.8 Sludge and Sediment 8.8.1 WRF Centrifuge Waste Sludge Sludge samples were obtained from the WRF centrifuge and analyzed by gamma spectroscopy. 1-131 activity in the sludge is consistent with historical values and, as previously discussed, is due to radiopharmaceuticals in the WRF Influent. The concentration of 1-131 ranged from no detectable to 1220 pCi/kg.

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

8.8.2 Cooling Tower Sludge Sludge/sediment originating from the Unit 1 and Unit 3 Cooling Towers and Circulating Water canals was disposed of in the WRF sludge landfill during 2016. 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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 30

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Table 8-6 Vegetation ODCM required samples denoted by units are pCi/kg, wet LOCATION TYPE DATE COLLECTED 1-131 Cs-134 Cs-137 LOCAL RESIDENCE (Site #47)*
Lettuce Lettuce Red Cabbage Green Cabbage Green Cabbage Green Cabbage Green Cabbage COMMERCIAL FARM (Site #62)*
LOCAL RESIDENCE (Site #51)
No Sample Available for January No Sample Available for February No Sample Available for March 14-Apr-16
<35
<48 12-May-16
<58
<58 No Sample Available for June No Sample Available for July No Sample Available for August No Sample Available for September No Sample Available for October No Sample Available for November No Sample Available for December
<44
<55
<35
<37
<38
<28
<47
<35
<35
<34 21-Jan-16 21-Jan-16 25-Feb-16 24-Mar-16 21-Apr-16 No Sample Available for May No Sample Available for June No Sample Available for July No Sample Available for August No Sample Available for September No Sample Available for Juty No Sample Available for August No Sample Available for September No Sample Available for October No Sample Available for November No Sample Available for December
<37
<56
<77
<54
<49
<50
<62 Arugula Arugula 27-Oct-16 18-N0V-16 15-Dec-16
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<35
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<50
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<58 Swiss Chard 17-Jun-16
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<38 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 36
Table 8-7 Milk ODCM required samples denoted by units are pCi/liter DATE LOCATION COLLECTED 1-131 Cs-134 Cs-137 Ba-140 La-140
-i-Note No Sample Available For January Local Resident No Sample Available for February Goats 24-Mar-16
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Note 2; CR16-13413 Power outage led to system re-boot, LLD of 1 pCi/L for 1-131 not met Note 3" CR 16-18989 LLD for 1-131 not met due to power failure. Recount performed; LLD still not met. LLDs averaged_______
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 37
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<110 Notes PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 46
Table 8.11 Sludge/Sediment SAMPLE LOCATION ODCM required samples denoted by
units are pCi/kg, wet DATE milECTED 1-131 Cs-134 Cs-137 In-111 Notes 23-Aug-16 489+/-150
<102
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PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 47
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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 2016 are presented in Table 9-2. Definitions for Table 9-2 are as follows:
MDDq: Minimum differential dose, quarterly, 3 times 90'* percentile sQ determined from analysis (mRem).
MDDa: Minimum differential dose, annual, 3 times 90^ 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 Historical environmental gamma radiation results for 1985 through 2016 are presented in graphical form on Figure 9-1 (excluding transit control TLD #45). Figure 9-2 depicts the environmental TLD results from 2016 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-2016 Page 57
Table 9-1 TLD Site Locations (Distance and direction are relative to Unit 2 in miles)
TLD#
Location Distance from Unit 2 TLD#
Location Distance from Unit 2 TLD#
Location Distance from Unit 2 1
E30 29.13 18 ESE2 1.48 35 NNW^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 4.1?
40 N2 2.37 7
SE7 6.87 24 SW4 3.75 41 ESE3 3.39 8
SSE4 4J3 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 WNWl 0.74 47 E35 32.35 14 NNE2 155 31 1.03 48 E24 22.76 15 NE2 1.63 32 0.90 49 ENEll 11.32 16 ENE2 1.59 33 W4 4.05 50 WNW5 4.24 17 E2 1.39 34 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-2016 Page 58
Table 9-2 Environmental TLD Results Palo Verde 2016 MDDo: 5 mrem 1
2 3456 78 910 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 Palo Verde 2016 MDDa: lO mrem 24.7 22.3 23.9 24.4 22.4 26.5 25.3 23.7 28.4 23.9 24.8 23.3 25.6 25.0 23.7 22.1 24.8 23.5 25.6 24.4 25.8 26.2 23.2 22.7 23.5 2 7.6 27.1 25.9 24.6 25.7 23.3 25.6 25.9 2 7.8 30.8 2 6.2 24.0 27.3 24.3 25.0 25.4 28.1 27.6 22.7 5.9 24.2 24.4 24.9 23.2 20.1 Quarterly fmRem/Standard Quarter")
MqQI MqQ2 MoQ3 MqQ4 25.2 22.5 24.8 24.9 2 3.9 27.9 2 6.8 24.8 2 7.8 25.0 2 6.4 24.3 25.6 25.6 24.0 21.8 25.2 23.8 25.4 23.0 26.6 25.5 23.3 22.7 22.9 25.5 23.4 25.6 26.0 21.9 29.2 28.0 25.1 29.5 25.4 27.0 25.8 2 7.2 27.3 25.5 24.8 26.9 24.2 26.6 26.2 26.8 28.3 25.9 24.4 24.1 23.9 21.3 23.0 23.5 19.4 26.8 25.0 23.5 27.6 23.5 23.6 22.9 24.8 24.3 22.2 22.5 24.6 22.8 24.8 24.1 25.3 25.7 22.7 22.6 23.6 27.3 24.0 26.9 26.6 21.5 28.2 28.3 26.5 30.4 26.0 26.9 24.5 27.0 25.6 25.7 27.3 26.4 25.9 27.2 26.0 2 7.8 28.2 25.9 24.6 24.5 27.8 26.3 26.0 24.0 27.6 24.5 25.0 27.5 28.0 32.2 26.7 23.9 28.5 24.7 25.5 2 6.4 27.9 27.7 25.0 5.9 24.2 24.4 24.9 23.2 20.1 28.4 29.8 26.8 26.0 29.1 25.1 26.8 28.3 30.2 34.2 28.0 25.3 29.9 26.0 26.3 28.2 29.2 30.5 26.7 6.6 25.3 25.3 27.1 25.2 20.9 26.2 26.3 25.3 22.6 25.0 22.1 23.9 25.7 27.8 30.8 25.6 23.3 2 7.4 23.2 24.8 25.8 25.6 27.0 23.0 5.7 24.0 23.8 23.6 22.0 19.5 30.3 28.5 2 7.4 25.1 27.8 25.2 27.3 28.0 29.9 32.9 27.7 25.8 30.0 26.3 26.9 27.9 29.2 28.8 25.2 6.8 25.5 25.2 26.2 25.4 21.9 LqQI LqQ2 LoQ3 LoQ4 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 5.1 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Annual fmRem')
98.8 89.0 95.7 97.5 89.6 106.0 101.0 94.7 113.6 95.5 99.3 93.4 102.5 100.2 94.7 88.5 99.2 93.8 102.3 97.8 103.1 104.8 92.8 90.7 94.2 101.9 91.2 100.3 100.9 86.6 112.1 108.1 99.9 115.4 99.9 103.9 97.5 104.6 102.8 97.4 96.4 103.2 96.7 104.0 99.3 106.5 107.8 97.8 94.3 95.1 110.4 108.2 103.7 98.4 102.9 93.3 102.5 103.7 111.1 123.4 104.8 96.1 109.2 97.2 100.0 101.7 112.3 110.5 91.0 2 3.4 96.8 97.6 99.6 92.8 80.4 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 112.7 110.9 105.5 97.7 109.5 96.9 103.0 109.5 116.0 130.1 108.0 98.3 115.8 100.2 103.4 108.3 111.9 114.0 99.9 25.0 99.0 98.6 101.7 95.9 82.5 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 59
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~~10. Land Use Census 10.1 Introduction In accordance with the PVNGS ODCM, Section 6.2, the annual Land Use Census was performed in June 2016.~~
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 Nearest Resident There was one (1) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.162 mrem.
Milk Animal There was one (1) change in milk animal status from the previous year. This location does not currently have enough milk animals to participate in the REMP; however this location is being monitored for possible future inclusion and is being tracked with AI 16-20188-003. Dose calculations indicated the highest dose to be 1.07 mrem.
Vegetable Gardens There was one (1) change in nearest garden status from the previous year. One garden location was added in the NNW sector. This garden does not currently meet the ODCM required size of 500 square feet; however this location is being monitored for possible future inclusion in REMP. Dose calculations indicated the highest dose to be 0.477 mrem.
See Table 10-1 for a summary of the specific results and Table 2-1 for current sample locations.
Figure 10-lthrough Figure 10-3 provide graphs depicting historical calculated doses for nearest residents, nearest milk receptor, and nearest garden receptor locations in each sector.
Differences in calculated doses are the result of many variables, including;
~~Changes in receptor locations from year to year (proximity to the power plant)~~
~~Changes in local meteorology (wind direction, wind speed, precipitation, and temperature)~~
~~Concurrent meteorology at the time of effluent releases~~
<< Exposure pathways PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 62
Table 10-1 Land Use Census (Distance and direction are relative to Unit 2 in miles)
Sector Nearest Resident Nearest Garden Nearest Milk Animal (Cow/Goat)
Calculated Dose (mrem)
Change from 2015 N
1.55 3.10 3.66 Resident 5.43E-2 Garden 2.57E-1 Milk 2.02E-1 NNE 1.52 3.30 3.05 Resident 1.09E-1 Garden 4.66E-1 Milk 4.83E-1 NE 2.16 NONE NONE Resident 1.27E-1 ENE 2.05 4.84 4.84 Resident 1.18E-1 Garden 4.77E-1 Milk 4.77E-1 E
2.81 NONE NONE Resident 8.19E-2 ESE 1.95 NONE NONE Resident 1.61E-1 SE 3.40 NONE 3.99 Resident 1.20E-1 Milk 1.07E+0 Resident Milk SSE NONE NONE NONE NA S
NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.62E-1 WSW 0.75 NONE NONE Resident 1.25E-1 W
0.70 NONE NONE Resident 8.64E-2 WNW NONE NONE NONE NA NW 0.93 NONE NONE Resident 4.75E-2 NNW 1.30 4.34 NONE Resident 3.87E-2 Garden 1.13E-1 Garden Comments:
Dose calculations were performed using CASPAR code and 2015 meteorological data and source term.
Dose reported for each location is the total for all three PVNGS Units and is the highest individual critical organ dose identified.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 63
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11. Summary and Conclusions The conclusions are based on a review of the radio assay results and environmental gamma radiation measurements for the 2016 calendar year. Where possible, the data were compared to pre-operational sample data.
All sample results for 2016 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.
1-131 identified in the Evaporation Ponds, WRf Influent, WRF Centrifuge sludge, and Reservoirs is the result of offsite sources and appears in the effluent sewage from Phoenix. The levels of 1-131 detected in these locations are consistent with levels identified in previous years.
Tritium concentrations identified in surface water onsite have been attributed to PVNGS permitted gaseous effluent releases and secondary plant releases. These concentrations are consistent with historical values.
Environmental radiation levels are consistent with measurements reported in previous Pre-operational and Operational Radiological Environmental annual reports. References 1 and 2.
There was no measurable radiological impact on the environment in 2016 resulting from the operation of PVNGS.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 67
Table 11-1 Environmental Radiological Monitoring Program Annual Summary lr__y 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 2016 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 68 Medium or Pathway Sampled (Unit of Measurement)
Type and Total Number of Analyses Performed Lower Limit of Detection (LLD)
(from Table 6.1)
All Indicator Locations Mean (f)'
Range Location with Highest Annual Control Mean Locations Name Mean Meanffl^
Number of Nonroutine Reported Measurements Distance and Range Range Direction Direct TLD - 200 NA 25.7 Site #35 32.5 (4/4) 26.5(8/8) 0 Radiation (188/188)
(mrem/std.
19.2-34.2 8 miles 30.8 - 34.2 23.0-29.2 qtr.)
330° Air Gross Beta -
0.01 0.032 Site # 4 0.033 0.032 (52/52) 6 Particulates 519 (462/468)
(52/52)
(pCi/m^)
0.013-16 miles 0.018-0.017-0.058 0.058 92° 0.054 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/m')
1-131 0.07
<LLD NA
<LLD
<LLD 8
<LLD NA
<LLD
<LLD Broadleaf Gamma Spec.
Vegetation
- 16 (pCi/Kg-wet) 1-131 60
<LLD NA
<LLD
<LLD 0
Cs-134 60
<LLD NA
<LLD
<LLD 0
Cs-137 80
<LLD NA
<LLD
<LLD 0
Groundwater H 8 (pCi/liter)
Gamma Spec.
-8 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 2000
<LLD NA
<LLD NA 15
<LLD NA
<LLD NA 0
30
<LLD NA
<LLD NA 0
15
<LLD NA
<LLD NA 0
15
<LLD NA
<LLD NA 0
30
<LLD NA
<LLD NA 0
30
<LLD NA
<LLD NA 0
15
<LLD NA
<LLD NA 0
15
<LLD NA
<LLD NA 0
15
<LLD NA
<LLD NA 0
18
<LLD NA
<LLD NA 0
60
<LLD NA
<LLD NA 0
15
<LLD NA
<LLD NA 0
Gross Beta -
48 4
3.9 (30/48) 2.0-6.2 Site #55 3 miles 214° 4.6(12/12) 2.9 -6.2 NA 0
H 16 Gamma Spec.
-48 2000
<LLD NA
<LLD NA 0
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
1-131 15
<LLD NA
<LLD NA 0
Cs-134 15
<LLD NA
<LLD NA 0
Cs-137 18
<LLD NA
<LLD NA 0
Ba-140 60
<LLD NA
<LLD NA 0
La-140 15
<LLD NA
<LLD NA 1
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT-2016 Page 69
Gamma Spec.
-33 Milk 1-131 1
<LLD NA
<LLD
<LLD 3
(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. -
25 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 1-131 15 13 (7/36)
Site #61 13 (3/4)
NA 0
(pCi/liter) 6-23 Onsite 67° 6-23 Cs-134 15
<LLD NA
<LLD NA 0
Cs-137 18
<LLD NA
<LLD NA 0
Ba-140 60
<LLD NA
<LLD NA 0
La-140 15
<LLD NA
<LLD NA 0
H 25 3000 1092 (17/36)
Site #64 1352 (4/4)
NA 0
576-2197 Onsite 803 -2197 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-2016 Page 70
~~12. References~~
~~1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985~~
~~2. 1985-2013 Annual Radiological Environmental Operating Reports, Palo Verde Nuclear Generating Station~~
~~3. Palo Verde Nuclear Generating Station Technical Specifications and Technical Reference Manual~~
~~4. Offsite Dose Calculation Manual, Revision 26, PVNGS Units 1, 2, and 3~~
~~5. Offsite Dose Calculation Manual, Revision 27, PVNGS Units 1, 2, and 3~~
~~6. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants~~
~~7. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants~~
~~8. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG-1301)~~
~~9. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007~~
~~10. "Sources of Radiation." NRC: Sources of Radiation. Nuclear Regulatory Commission, 17 Oct.~~
~~2014. Web. 03 Feb. 2017.~~
~~11. "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-2016 Page 71

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