Text

Annual Radiological Environmental Operating Report 2019
	ML20100N742
Person / Time
Site:	Palo Verde
Issue date:	04/09/2020
From:	Dilorenzo M; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-08088-MDD/MSC
	Download: ML20100N742 (77)
	v • d • e

Technical Specification 5.6.2 5 .6.2 Palo Verde Nuclear Generating Station PO Box 52034 102-08088-MDD/MSC Phoenix, Arizona 85072-2034 Mail Station 7636 April 9, 2020 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 2019 In accordance with PVNGS Technical Specification 5.6.2, enclosed, please find the Annual Radiological Environmental Operating Report for 2019.

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) Reason: I am approving this document Date: 2020.04.09 13:33:02 -07'00' Michael D. DiLorenzo Department Leader, Regulatory Affairs MDD/MSC/mg

Enclosure:

Palo Verde Nuclear Generating Station Annual Radiological Environmental Operating Report 2019 cc: S. A. Morris NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS B. Goretzki 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 2019

PALO VERDE NUCLEAR GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2019

(

Reference:

RCTSAI 1643, Legacy Item No.036843.01)

Comolli, Digitally signed by Comdli. Mchelle (Z09567)

Michelle DN: cn=Comolli, Michelle (209567)

Reason; I am an author of this document Prepared by:_

(Z09567) Date: 2020.03.20 15:05:57 -07'00' Digitally signed by Gmsecki. Lori Grusecki, Lori i'l>, DN: cn=Gruseckl. Lori J(Z39643)

Reason: 1 have reviewed this J(Z39643) document Reviewed by:. Date; 2020.03.25 05:19:16 -07'00' Digitally signed by Hogue, HOCIIIP Mofhon nuyue, INdUldn dn cn=Hogue, Nathan (Z14113)

(Z14113) Date: 2020.03.25 09:32:18 Approved by:_ -07'00' Director, Radiation Protection

1. TABLE OF CONTENTS

1. Introduction........................................................................................................................ 2 1.1 Overview..................................................................................................................... 2 1.2 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 2019............................ 4 2.3 REMP Deviations/Abnormal Events Summary.............................................................4 2.4 Groundwater Protection............................................................................................... 5

3. Sample Collection Program...............................................................................................12 3.1 Water......................................................................................................................... 12 3.2 Vegetation..................................................................................................................12 3.3 Milk............................................................................................................................12 3.4 Air.............................................................................................................................. 12 3.5 Soil, Sludge, and Sediment......................................................................................... 12

4. Analytical Procedures....................................................................................................... 13 4.1 Air Particulate............................................................................................................13 4.1.1 Gross Beta................................................................................................................ 13 4.1.2 Gamma Spectroscopy...............................................................................................13 4.2 Airborne Radioiodine..................................................................................................13 4.2.1 Gamma Spectroscopy...............................................................................................13 4.3 Milk............................................................................................................................13 4.3.1 Gamma Spectroscopy...............................................................................................13 4.3.2 Radiochemical 1-131 Separation............................................................................... 13 4.4 Vegetation.................................................................................................................. 13 4.4.1 Gamma Spectroscopy...............................................................................................13 4.5 Sludge/Sediment........................................................................................................ 14 4.5.1 Gamma Spectroscopy...............................................................................................14 4.6 Water..........................................................................................................................14 4.6.1 Gamma Spectroscopy...............................................................................................14 4.6.2 Tritium.....................................................................................................................14 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Pagei

4.6.3 Gross Beta................................................................................................................14 4.7 Soil............................................................................................................................. 14 4.7.1 Gamma Spectroscopy...............................................................................................14

5. Nuclear Instrumentation.................................................................................................... 15 5.1 Gamma Spectrometer.................................................................................................. 15 5.2 Liquid Scintillation Spectrometer............................................................................... 15 5.3 Gas Flow Proportional Counter................................................................................... 15

6. Isotopic Detection Limits and Reporting Criteria...............................................................16 6.1 Lower Limits of Detection...........................................................................................16 6.2 Data Reporting Criteria...............................................................................................16 6.3 LLD and Reporting Criteria Overview....................................................................... 16

7. Interlaboratory Comparison Program................................................................................22 7.1 Quality Control Program............................................................................................. 22 7.2 Intercomparison Results............................................................................................. 22

8. Data Interpretation and Conclusions..................................................................................27 8.1 Air Particulates........................................................................................................... 27 8.2 Airborne Radioiodine................................................................................................. 27 8.3 Vegetation..................................................................................................................27 8.4 Milk........................................................................................................................... 28 8.5 Drinking Water...........................................................................................................28 8.6 Groundwater...............................................................................................................28 8.7 Surface Water.............................................................................................................28 8.8 Sludge and Sediment.................................................................................................. 29 8.8.1 WR Centrifuge Waste Sludge...................................................................................29 8.8.2 Cooling Tower Sludge............................................................................................. 29 8.9 Data Trends................................................................................................................29 8.10 Hard-To-Detect Radionuclide Results..................................................................... 29

9. Thermoluminescent Dosimeter (TLD) Results and Data................................................... 56

10. Land Use Census............................................................................................................61 10.1 Introduction............................................................................................................61 10.2 Census Results.........................................................................................................61

11. Summary and Conclusions............................................................................................. 66

12. References..................................................................................................................... 70 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page ii

LIST OF TABLES Table 2-1 Sample Collection Locations.......................................................................................6 Table 2-2 Sample Collection Schedule........................................................................................7 Table 2-3 Summaries of the REMP Deviations/Abnormal Events.............................................. 8 Table 6-1 ODCM Required Lower Limits of Detection (a priori)..............................................19 Table 6-2 ODCM Required Reporting Levels........................................................................... 20 Table 6-3 Typical MDA Values............................................................................................... 21 Table 7-1 Interlaboratory Comparison Results.......................................................................... 23 Table 8-1 Particulate Gross Beta in Air lst-2nd Quarter............................................................30 Table 8-2 Particulate Gross Beta in Air 3rd-4th Quarter............................................................31 Table 8-3 Gamma in Air Filter Composites..............................................................................32 Table 8-4 Radioiodine in Air lst-2nd Quarter........................................................................... 33 Table 8-5 Radioiodine in Air 3rd-4th Quarter........................................................................... 34 Table 8-6 Vegetation................................................................................................................ 35 Table 8-7 Milk......................................................................................................................... 36 Table 8-8 Drinking Water.........................................................................................................37 Table 8-9 Groundwater.............................................................................................................39 Table 8-10 Surface Water.........................................................................................................40 Table 8-11 Sludge/Sediment..................................................................................................... 45 Table 8-12 Hard -To-Detect Radionuclide Results................................................................... 47 Table 9-1 TLD Site Locations.................................................................................................. 57 Table 9-2 Environmental TLD Results......................................................................................58 Table 10-1 Land Use Census.................................................................................................... 62 Table 11-1 Environmental Radiological Monitoring Program Annual Summary....................... 67 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 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)....................................................................10 Figure 2-2 REMP Sample Sites- Map (10-35 Miles).................................................................11 Figure 8-1 Gross Beta in Air, lst-2nd Quarter.......................................................................... 48 Figure 8-2 Gross Beta in Air, 3rd-4th Quarter........................................................................... 49 Figure 8-3 Historical Gross Beta in Air (Weekly System Average)......................................... 50 Figure 8-4 Historical Gross Beta in Air (Annual Site to Site Comparisons) Compared to Pre-Op

................................................................................................................................................. 51 Figure 8-5 Gross Beta in Drinking Water.................................................................................52 Figure 8-6 Evaporation Pond Tritium Activity (Pre-Op- 2008)................................................. 53 Figure 8-7 Evaporation Pond Tritium Activity (2009-2018)......................................................54 Figure 8-8 Sedimentation Basin 2 Cs-137.................................................................................55 Figure 9-1 Network Environmental TLD Exposure Rates........................................................59 Figure 9-2 Environmental TLD Comparison: Pre-Operational versus 2019...............................60 Figure 10-1 Historical Comparison of Nearest Resident Dose..................................................63 Figure 10-2 Historical Comparison of Nearest Milk Animal Dose........................................... 64 Figure 10-3 Historical Comparison of Nearest Garden Dose....................................................65 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Pageiv

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 2019, 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- 2019 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 2019. All references are specifically identified in Section 12.

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

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

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

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

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 2

1.2 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 per year. 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%

Industrial/Occupational 0.1%

Radon and Thoron 37%

Cosmic Terrestrial 5%

3%

Figure 1-1 Sources of Radiation Exposure in the United States PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 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 process personnel ionizing radiation dosimeters.

In addition to monitoring environmental media, a Land Use Census is performed annually to identity 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 2019 Two (2) onsite groundwater wells. Site 58A (Well 27dcb) and Site 65 (Well 34aab) were added to the ODCM. These wells were sampled as supplemental sites prior to the July 2019 revision of the ODCM, at which time they were added to the Radiological Environmental Monitoring Program. There were no other changes to the Radiological Environmental Monitoring Program that impacted the Offsite Dose Calculation Manual (ODCM) Revision 28.

2.3 REMP Deviations/Abnormal Events Summary During calendar year 2019, there were eleven (11) deviations/abnormal events with regards to the monitoring program. Refer to Table 2-3 for more detail and corrective actions taken.

There was eight (8) events involving Air Sample data. Six (6) events involved reduced sampling period due to pump failure, either due to pump malfunction or loss of power to the pump. Two (2) events were due to failure of the Elapsed Time Meter (ETM). Three (3) of these eight (8) events resulted in sufficient data to obtain VALID results for the sampling period, while five (5) events resulted in the determination that the sample was INVALID. Palo Verde Nuclear PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 4

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 the sampling period involving an invalid sample from a required sample location.

Two (2) events were due to the inability to obtain a Drinking Water Sample, resulting from an inoperable well pump at the donor location. One (1) event impacted the ability to meet the required Lower Limit of Detection for La-140. One (1) event resulted in the inability to collect the drinking water sample from the location for the month of December.

There was one (1) event involving environmental dosimetry; dosimetry at Site 47 was identified as missing during the 2"*^ Quarter TLD change-out. Data for this location was unavailable for the 1* quarter.

2.4 Groundwater Protection PVNGS has implemented a groundwater protection initiative developed by the Nuclear Energy Institute (NEI). The implementing guidance of this initiative, NEI 07-07 (Industry Ground Water Protection Initiative - Final Guidance Document, August 2007), and later revised in March of 2019, 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. Many of these wells were previously monitored in accordance with the State of Arizona Aquifer Protection Permit (Area-Wide) No. P-100388 (APP), which provided agreed upon monitoring parameters and reporting thresholds. The APP was revised in 2018, which included the removal of several of the wells from mandated sampling. These wells are now referred to as Legacy Wells and continue to be sampled for data continuity and in support of the Groundwater Protection Initiative. The frequency of sampling of the wells varies and may be done monthly, quarterly, and or annually for chemical and radiological parameters.

Sample results for the shallow aquifer wells are reported in the PVNGS Annual Radioactive Effluent Release Report (ARERR).

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- 2019 Pages

Table 2-1 Sample Collection Locations LOCATION DESCmPTlOI0^>

HAMt'Lh SITE# SAMPLE TYPE LOCATION {2L) 4 Air E16 APS Office 6A* Air SSE13 Old US 80 7A Air ESE3 Arlington School 14A Air NNE2 371* Ave. and Buckeye-Salome Rd.

15 Air NE2 NE Site Boundary 17A Air E3 351* 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 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 SW3 Local resident (Supplemental) 57 Groundwater ONSITE Well 27ddc 58 Groundwater ONSITE Well 34abb 58A Groundwater ONSITE Well 27dcb 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 65 Groundwater ONSITE Well 34aab NOTES:

Designates a control site (a) Distances and direction are from the center-line of Unit 2 containment and rounded to the nearest mile PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 6

Air sample sites designated with the letter A are sites that have the same site number as a TLD location, but are not in the same location (e.g. site #6 TLD location is different from site

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

Table 2-2 Sample Collection Schedule 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 1 55 w 57 1 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- 2019 Page 7

Table 2-3 Summaries of the REMP Deviations/Abnormal Events Deviation/Abnormal Event V^ctions Taken Pump failure resulted in insufficient data for statistical analysis for

1. Air Sample Site 17A sample period 4/16/2019- 4/23/2019 (Week 16). Data for Week INVALK) due to pump 16 is INVALID and data is for INFO only. Pump was replaced failure for sample period during sample period 4/23/2019-4/30/2019 (Week 17), providing 4/16/2019-4/23/2019 and sufficient data for a VALID sample. Event documented through 4/23/2019-4/30/2019.

CR 19-06328 (Table 8-5, Note 2).__________________________

Site 35 lost power during Week 21; however the Elapsed Time

2. Air Sample site 35 INVALID Meter continued recording time. Week 22 experienced a pump due to power loss and pump failure once the power was restored and had a shortened sampling failure for sample period run time. Samples are INVALID due to unknown volume of 5/21/2019-5/28/2019 and sample. Event documented through CR 19-08404 (Table 8-5, 5/28/2019-6/4/2019.

Note 3).___________________________________________ ___

Pump failed with Elapsed Time Meter still running, resulting in

3. Air Sample Site 40 INVALID inability to determine sample flow volume. Sample is INVALID due to failed pump for sample and data is for INFO only. Event documented through CR 19-period 6/18/2019- 6/25/2019.

09504 (Table 8-5, Note 4)._______________________________

ETM did not reflect expected run time (actual 141.9 hrs. vs

4. Air Sample Site 40 Elapsed expected 167.2 hrs.). Upon testing, ETM was functioning Time Meter (ETM) did not properly. Possible cause was due to power outage. Sample have expected run time for appeared to have normal dust loading. Sample run time sufficient sample period 7/9/2019-for data collection and statistical analysis; sample is VALID.

7/16/2019.

Event documented through CR 19-10403 (Table 8-5, Note 5).

5. Air Sample Site 6A Pump failed with Elapsed Time Meter still running resulted in INVALID due to pump inability to determine sample flow volume. Sample is INVALID failure for sample period and data is for INFO only. Event documented through CR 19-8/13/2019- 8/20/2019. 12139 (Table 8-5, Note 6). _____________

6. Air Sample Site 6A Elapsed ETM failed to operate as expected. Pump was running Time Meter (ETM) failed to satisfactorily and collection on filter had normal distribution.

operate as expected run time Sample run time was calculated; sample is VALID. Event for sample period 8/20/2019-documented through CR 19-12487 (Table 8-5, Note 7).

8/27/2019.

7. Air Sample Site 29 INVALID Pump failed with Elapsed Time Meter still running resulted in due to failed pump and inability to determine sample flow volume. Sample is INVALID inability to estimate volume and data is for INFO only. Event documented through CR 19-of sample for sample period 16553 (Table 8-5, Note 8).

10/30/2019- 11/5/2019.

8. Air Sample Site 29 INVALID Pump failed with Elapsed Time Meter still running resulted in due to failed pump and inability to determine sample flow volume. Sample is INVALID inability to estimate volume and data is for INFO only. Event documented through CR 19-of sample for sample period 16890 (Table 8-5, Note 9).

11/5/2019- 11/12/2019.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 8

Composite drinking water sample achieved an MDA of 46 pCi/L,

9. Drinking Water Site 55 did versus the required LLD of 15 pCi/L, due to inability to collect not meet LLD for La-140 for sample for final week of sampling period. Event documented November.

through CR 19-17596 and 19-17770 (Table 8-8, Note 2).

Donors pump failed to operate. As a result, no sample could be

10. No sample available for obtained from Site 55 for the sampling period of December.

Drinking Water Site 55 for Event documented through CR 19-17897 and 20-000862 (Table December.

8-8, Note 3).

During the 2"'* Quarter TLD change-out, TLD Site 47 was

11. Direct Radiation TLD Site 47 identified as missing. Data for this location was unavailable; data unavailable for 1* however, dosimetry was replaced for 2"** Quarter data collection.

Quarter.

Event documented through CR 19-04547 (Table 9-2, Note 1).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 9

N

, NNE NE IV 10 fi ^5 :4 r.

ANJtnrm juxtir

!r '

KEY TO MAP Sample Site Q5 Sc^ool ^

A Air Airstrip -f Radiological Environmental V Vegetation Monitraing Sanple Sites w water T TLD 0-10 miles M Milk Figure 2-1 REMP Sample Sites- Map (0-10 miles)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 10

/ SE / 25 mites 10 mites KEY TO MAP Sample Site School t A Air Airstrip gg Radiological Emwonmental V Vegetation Ih-ogram Sample Sites VU Water T UO 10-35 Miles M Milk Figure 2-2 REMP Sample Sites- Map (10-35 Miles)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 11

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, active Evaporation Ponds 1A/B/C, 2A/B, and 3A/B, and onsite wells 34abb, 27ddc, 34aab, and 27dcb.

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 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 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- 2019 Page 12

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 an 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 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 phase 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 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 13

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 Beclanan 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 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.

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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/l> or Gas (pCi/m^) (pCld) (pCl/kfi, 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 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- 2019 Page 19

Table 6-2 ODCM Required Reporting Levels Airborne Particulate Fresli Milk Food Products Analysis Water (pCi/l) or Gas (pCi/nr) (pCi/1) (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.

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Table 6-3 Typical MDA Values Water Milk Airborne Particulate or Vegetation Analysis/Nuclide Gas (pCi/m3)

(pCi/liter) (pCi/liter) (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 1-131 10 1 0.04' 49 Cs-134 9 1 0.003' 47 Cs-137 10 1 0.003' 61 Ba-140 33 3 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- 2019 Page 21

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 2018, APS analyzed the following sample types under the interlaboratory comparison program:

Beta/Gamma/ in Air Filter

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- 2019 Page 22

Table 7-1 Interlaboratory Comparison Results Sanple Analysis Known PVNCB 1 sigma Ratio NRC Nuclide Units Resolution* Results ID Type Value Value Error Range E12511 Oamm Water 0-141 pCVL 1.13E+02 1.12EHH 1.20E+01 9 0.99 0.60- 1.66 Acceptable CLDetl Co-38 pG/L 139EHE 1.43E+02 1.49E+01 10 1.04 0.60- 1.66 Acceptable Co-60 pCVL 2.90E+02 Z87Et02 1.87EH11 13 0.99 0.60- 166 Acceptable

&-51 pCVL 2.84Et02 Z73EH12 3.46Et01 3 0.97 0.50- 2.00 Acceptable Cs-134 dCVL 1.53EH)2 1.48Et02 1.03Ert)l 14 0.95 0.60- 1.66 Acceptable a-137 pO/L I.91EH)2 2.02Ef02 106EH)1 10 1.06 0.60- 1.66 Acceptable Fe-59 pQ/L 1.54Ef02 L62E+02 1.52EH)1 11 1.05 0.60- 1.66 Acceptable 1-131 pCVL 8.65E+01 789E401 1.21EH)l 7 0.91 0.50 - 2.00 Acceptable Mn-34 pCi/L 1.39EK)2 1.46E+02 1.47EH)l 10 1.05 0.60- 1.66 Acceptable Zn-65 oCVL 2.14E+02 2.18E402 2.43EH)l 9 1.02 0.60- 1.66 Acceptable E12511 Ckunna Water Ce-141 pO/L U3E402 M3EH)2 LllEH)! 10 1.00 0.60- 1.66 Acceptable CLDet2 Cb-58 pCi/L I.39E+02 131E402 1.27E401 10 0.94 0.60- 1.66 Acceptable Co-60 pCVL 2.90E+02 2.84E+02 1.70E+01 17 0.98 0.73 - 1.33 Acceptable Cr-51 pCVL 2.84E+02 Z69E+02 4.70E+01 6 0.95 0.30- 2.00 Acceptable Cs-134 dCVL 1.55E+02 138E+02 9.02E-KX) 15 0.89 0.60- 1.66 Acceptable a-l37 pCVL 1.91EH)2 1.91E402 1.78E401 11 1.00 0.60- 1.66 Acceptable Fc-59 pCVL I.54E-+02 I.67E-H)2 1.34E+01 12 1.08 0.60- 1.66 Acceptable I-13I pCVL 8.65EH)1 8.16E-H)1 9.49E+O0 9 0.94 0.60- 166 Acceptable Mn-34 pCVL I.3<<+02 1.40E^ 1.34E+01 10 1.01 0.60- 1.66 Acceptable Zn-63 pCVL 2.14E+02 2.18EH12 2.I3E+01 10 1.02 0.60- 1.66 Acceptable E125I1 Gamnm Water Ce-141 pCVL L13E+02 L0^f02 7.I9E+00 13 0.96 0.60- 1.66 Acceptable CLDet3 Co-58 pCVL L39E+02 1.36EHJ2 832E+00 16 0.98 0.75 - 1.33 Acceptable C6-60 pCVL 2.90E+02 2.98EH)2 1.23E401 24 1.03 0.75 - 1.33 Acceptable 0-51 pCVL 2.84E+02 3.I1E+02 2.99E+01 10 1.10 0.60- 1.66 Acceptable dCVL 22 0.92 0-134 1.55E+02 1.43E+02 6.65E+00 0.75 - 1.33 Acceptable 0-137 pCVL I.91E+02 1.97EH)2 134E+01 16 1.03 0.75- !.33 Acceptable Fe-59 pCVL 1.54E+02 1.63EH)2 8.95EHX) 18 1.06 0.75 - 1.33 Acceptable 1-131 pCVL 8.65EK)1 8.74EH)1 7.90E+00 11 1.01 0.60- 1.66 Acceptable Mn-54 pCVL 13^+02 1.45E+02 9.83E-+00 15 1.04 0.60- 1.66 Acceptable Zn-65 pCVL 2.14E+02 2.19E+02 1.37E+01 16 1,02 0.75 - 1.33 Acceptable E12512 Beta FOter GBeta pCi/ca 2.39E-+02 2.49E+02 4.00E-KX) 62 1.04 0.80 - 1.23 Acceptable CLDct 1 E12513 I-I31C^ridRC I-13I pCi/ca 7.54E+01 6.73EH)1 1.I3E+01 6 0.89 0.50 - 2.00 Acceptable CLDet2 E12313 1-131 Cartridae 1-131 pCVea 7.54E+01 7.25EH)1 7.12EfOO 10 0.96 0.60 - 1.66 Acceptable CLDct3 E12513 I-13I Ortridae 1-131 pCVea 7.54E+01 7.39EHH 8.44EH)0 9 0.98 0.60- 1.66 Acceptable EI23I4 Ce-141 pCVea 7.49EH)1 8.00E*01 1.03E*01 8 1.07 0.60- 1.66 Acceptable CLDetl 0>-38 pCVea 9.17E+01 1.03E+02 1.43EH)1 7 1.12 0.30- ZOO Acceptable Cto-60 pCVea 1.91Et02 2,06Et02 1.60E401 13 1.08 0.60- 1.66 Acceptable Q-31 pCVea 187E+02 1.83EH12 S.OTEHll 4 0.98 0.30- ZOO Acceptable a-134 pCVea 1.02E+02 9.74E+01 8.34EHK) 12 0.95 0.60- 1.66 Acceptable a-137 pCVea 126E+02 l.30EH)2 l.75EK)l 7 1.03 0.30- ZOO Acceptable Fe-39 pCVea 1.02Et02 l.OTEHG l.SOEHH 7 1.05 0.30- ZOO Acceptable Mn-34 pCVea 9.13E+01 l.07EH)2 l.46EK)l 7 1.17 0.30- ZOO Acceptable Zn-63 pCVea I.41E+02 l.39EH)2 2.34EK)I 6 0.99 0.30- ZOO Acceptable E12514 Gamna Fiber 0-141 pCVea 7.49E401 7.76EH)1 6.89EH>> 11 1.04 0.60 - 1.66 Acceptabte CLDet2 Co-38 pCVea 9.17EH)1 9.66Ef01 l.lSEfOl 8 1.05 0.60- 1.66 Acceptable Q)-60 pCVea I.91EHI2 1.93EH12 l.llE+01 17 1.01 0.75 - 1.33 Acceptable Cr-31 pCVea 1.87EKI2 1.79E+02 2.91EHH 6 0.96 0.50 - 2.00 Acceptable Cs-134 pCVea I.02EH)2 7.95E+01 5.I7E+W 13 0.78 0.60- 1.66 Acceptable Cs-137 pCVea 1.26E+02 1.38EH)2 2.04E+01 7 1.10 0.50 - 2.00 Acceptable Fe-39 pCVea I.02Ef02 I.19E+02 8.94EHK) 13 1.17 0.60- 1.66 Acceptable Mn-34 pCVea 9.15Ef01 1.04Ef02 U5EH)1 9 1.14 0.60- 1.66 Acceptable Zn-63 pCVea 1.41EH)2 I.60E+02 1.44EHH 11 I.I3 0.60 - 1.66 Acceptable

calculated fiomPVNGB value/1 sigma eiror value

- Eckert & Ziegler Analytics, Inc. NIST-traceable known value NRC Acceptance Criteria Resolution Ratio 4-7 0.3-Z0 8-13 0.6-1.66 16-30 0.73-1.33 31-200 0.80-1.23

>200 0.83-1.18

' From NRC Inspectioa Mamal, procedure #84750, "Radioactive Waste Treatment, and Effluent and Environmental Monitoring" PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 23

Table 7-1 Interlaboratory Comparison Results (Continued)

Saitple Analysis Known PVNGS 1 sigma NRC Nuclide Units Resolution* Ratio Results ID Type Value Value Error Range E12514 Ganna Filter Ce-141 pCi/ea 7.49E+01 7.94E401 7.47E+O0 II 1.06 0.60 1.66 Acceptable CXDet3 Co-58 pCi/ea 9.17E+01 1.02E+02 U2E-K)1 9 1.11 0.60 1.66 Acceptable Co-60 pC^ea 1.91E+02 2.02E+02 1.19E+01 17 1.06 0.75 1.33 Acceptable Cr-51 pCi/ea 1.87E-K12 2.05E+02 3.01E-rt)l 7 1.10 0.50 2.00 Acceptable Cs-134 pCi/ea 1.02E+O2 8.26E-+01 4.89E+00 17 0.81 0.75 1.33 Acceptable Cs-137 pCi/ea 1.26E+02 1.39E402 1.74E+01 8 1.10 0.60 1.66 Acceptable Fe-59 pCVea 1.02E+02 1.21E-K12 9.31EHX) 13 1.19 0.60 1.66 Acceptable Mn-54 pCi/ea 9.15E401 1.07E+O2 1.14E-+01 9 1.17 0.60 1.66 Acceptable Zn-65 pCi/ea 1.41E+02 1.63E+02 1.53Et01 11 1.16 0.60 1.66 Acceptable E12515B Gaima Milk Ce-141 pCiA- 1.40E+01 1.54E+01 2.64E-MX) 6 1.10 0.50 2.00 Acceptable CLDet 1 Co-58 pCi/L 1.71EH11 1.60E+O1 2.18E+00 7 0.94 0.50 2.00 Acceptable Co-60 pCiA- 3.58E+01 3.57E+01 2.66E+00 13 1.00 0.60 1.66 Acceptable Cr-51 pCiA- 3.51E+01 3.99EH11 1.13E+01 4 1.14 0.50 2.00 Acceptable Cs-134 pCiA. 1.92E+01 1.90EH11 1.31E+00 15 0.99 0.60 1.66 Acceptable a-137 pCiA. 2.35E+01 2.41EH)1 2.88E400 1.03 0.60 1.66 Acceptable Fe-59 pCiA. 1.90E+O1 2.02E+01 2.92EHX) 1.06 0.50 2.00 Acceptable 1-131 pCiA. 3.22E+01 3.19E+01 5A6E+00 0.99 0.50 2.00 Acceptable Mn-54 pCiA. 1.71E+01 1.72E+01 2.29E+00 1.01 0.60 1.66 Acceptable Zn-65 pCiA. 2.64E401 2.76E+01 3.32E+00 1.05 0.60 1.66 Acceptable E12515B Gamma Milk Ce-141 pCiA- 1.40E+01 1.57E401 4.29EHX) 4 1.12 0.50 2.00 Acceptable CLDet 2 Co-58 pCiA- 1.71E+01 1.74E+01 2.53E+00 7 1.02 0.50 2.00 Acceptable Co-60 pCiA. 3.58E+01 3.85E+01 2.78B+00 14 1.08 0.60 1.66 Acceptable Cr-51 pCiA, 3.51E+01 2.28E401 1.90EtOl 1 0.65 0.50 2.00 Acceptable Cs-134 pCiA- 1.92E+01 1.82E+01 U9E+00 14 0.95 0.60 1.66 Acceptable Cs-137 pCiA. 2.35E+01 2.62E+01 3.05E+00 1.11 0.60 1.66 Acceptable Fe-59 pCiA 1.90E+01 2.26E+01 2.83E+00 1.19 0.60 1.66 Acceptable 1-131 pCiA 3A2E+01 2.68E+01 6.15E+00 0.83 0.50 2.00 Acceptable Mn-54 pCiA 1.71E+01 1.57EH)1 2.30EHX) 0.92 0.50 2.00 Acceptable Zn-65 pCiA 2.64E+01 2.63E+01 3.24E+1X1 1.00 0.60 1.66 Acceptable E12515B Gamma Milk Ce-141 pCiA 1.40B+01 1.57E401 2.87E+00 5 1.12 0.50 2.00 Acceptable CLDet 3 Co-58 pCiA 1.71E+01 1.73E+01 2.21EHX) 8 1.01 0.60 1.66 Acceptable Co-60 pCiA 3.58E+01 3.77E+01 2.62E+00 14 1.05 0.60 1.66 Acceptable Q-51 pCiA 3.51E401 3.48E401 2.42Et01 1 0.99 0.50 2.00 Acceptable Cs-134 pCiA 1.92E+01 1.78E401 1.16EtOO 15 0.93 0.60 1.66 Acceptable Cs-137 pCiA 2.35E+61 2.41E+01 2.48EKX) 10 1.03 0.60 1.66 Acceptable Fe-59 pCiA 1.90E+O1 2.21E401 2.67EHX) 8 1.16 0.60 1.66 Acceptable 1-131 pCiA 372Et01 2.99E^1 6.32E+00 5 0.93 0.50 2.00 Acceptable Mn-54 pCiA 1.71EH)1 1.78E401 2.25EKX) 8 1.04 0.60 1.66 Acceptable Zn-65 pCiA 2.64E+01 2.69E+01 5.82E+00 5 1.02 0.50 2.00 Acceptable E12516 Beta Water G. Beta pCiA 2.88E+02 3.34E+02 4.20E+00 80 1.16 0.80 Acceptable

' calculated fromPVNGS value/1 sigma error value NRC Acceptance Criteria Resolution Ratio 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.80-125

>200 0.85-1.18

' From NRC Inspection Manual, procetkre #84730, "Radioactive Waste ^sterns; Water Chemistry; Confirmatory Measirements/'

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 24

Table 7-1 Interlaboratory Comparison Results (Continued)

Sample Analysis Known PVNGS 1 sigma NRC Nuclide Units Resolution* Ratio Results ID Type Value Value Error Range E13032 Gamma Water 0-141 pO/L 1.27E+02 1.23E-rt)2 6.15E+00 20 0.97 0.75 1.33 Acceptable CLDet I Co-58 pC3/L 1.33E+02 l,35E+02 6.80E+00 20 1.02 0.75 1.33 Acceptable Co-tiO pCi/L 1.60BO2 1.65E+<)2 5.65E+00 29 1.03 0.75 1.33 Acceptable Or-51 pO/L 2.51E402 3.39E+02 5.40E+01 6 1.35 0.50 2.00 Acceptable Cs-134 pO/L 1.37E+02 1.50E402 3.05E+00 30 0.96 0.75 1.33 Acceptable Cs-137 pO/L 1.14E+02 1.18E+02 6.20E+00 19 1.04 0.75 1.33 Acceptable Fe-59 pCi/L 1.12E+02 1.19E+02 6.15E+00 19 1.06 0.75 1.33 Acceptable 1-131 pO/L 8.99EH)1 1.02E402 1.32E+01 8 1.13 0.60 1.66 Acceptable Mn-54 pO/L 1.17EKH 1Z4E+02 6.05E+00 20 1.06 0.75 U3 Acceptable Zn-65 pO/L 2Z2E+C2 2.31EHH 1.08E^1 21 1.04 0.75 U3 Acceptable E13032 Gamma Water Ce-141 pO/L IZTEKH 134E4D2 6.90E+00 19 1.06 0.75 1.33 Acceptable 0,Det2 Co-58 pCVL 1.33E+02 1.27Et02 6.30E+00 20 0.95 0.75 1.33 Acceptable Co-60 pO/L 1.60E-KI2 1.63E402 5.10EtO0 32 1.02 0.75 1.33 Acceptable 0-51 pCS/L 2.51E+C2 2.29E+02 4.33E+01 5 0.91 0.50 2.00 Acceptable Cs-134 pCVL 1.57E+02 1.38E+02 4.49E+00 31 0.88 0.75 1.33 Acceptable Cs-137 pO/L 1.14E+fl2 1.13E402 5.55E+00 20 0.99 0.75 1J3 Acceptable Fe-59 pO/L 1.12E+02 1.20EtO2 5.10Ef00 24 1.07 0.75 1.33 Acceptable 1-131 pCVL 8.99E+01 7.08E+O1 9.80E400 7 0.79 0.50 ZOO Acceptable Mn-54 pCVL 1.17E+02 1.20E+O2 5.80E+00 21 1.03 0.75 1.33 Acceptable Zn-65 pO/L 2Z2E+02 2.33Et02 1.05Et01 22 1.05 0.75 1.33 Acceptable E13032 Gemma Water Ce-141 pO/L lZ7Et4)2 1.22E+02 4.74EtOO 26 0.% 0.75 U3 Acceptable CLDet 3 Co-58 pO/L 1.33E+02 1.28E+02 5.00E460 26 0.96 0.75 1.33 Acceptable Co-60 pCi/L 1.60E+O2 1.61E+02 3.89E-tO0 41 1.01 0.75 133 Acceptable G-51 pCVL 2.51E+<H 2.60E+02 1.95E+01 13 1.04 0.60 1.66 Acceptable Cs-134 pO/L 1.57E+02 1.38E+02 3.50EKK) 39 0.88 0.75 1.33 Acceptable Cs-137 pCS/L 1.14E+02 1.15E+62 4.46EHM 26 1.01 0.75 133 Acceptable Fe-59 pO/L 1.12EK12 1.15E402 4.57E-HX) 25 1.03 0.75 133 Acceptable 1-131 pO/L 8.99EK11 8.93E401 4.22E+00 21 0.99 0.75 133 Acceptable Mn-54 pO/L 1.17E+02 1.15E+02 4.65Et<X) 25 0.98 0.75 1.33 Acceptable Zn-65 pCi/L 2Z2E462 230E+02 8.30E+00 28 1.04 0.75 133 Acceptable E13033 Beta Filter G. Beta pO/ea 1.30E462 lZ7Et02 2.44EtOO 0.98 0.80 Acceptable CLDetl E13034 1-131 Cartridge 1-131 pCS/ea 9.43E+01 9.8IEt<<l 6.75EtO0 1.04 0.60 1.66 Acceptable dDet2 E13034 1-131 Cartridge 1-131 pCi/ea 9.43Et61 8.99E*01 3.86E+00 0.95 0.75 1.33 Acceptable CL Del 3 E13034 1-131 Cartridge 1-131 pQ/ea 9.43E+01 9.56E+01 4.51E+00 1.01 0.75 Acceptable E13035 a Filter Ce-141 pCS/ea 1.52E+02 1.54E+02 6.70E+00 23 1.01 0.75 133 Acceptable CLDetl Co-58 pO/ea 1.59E+02 1.72E+<)2 8.50E+00 20 1.08 0.75 133 Acceptable Co-60 pCi/ea 1.91EH)2 2.07Et02 6.25E-K10 33 1.08 0.75 133 Acceptable Q-51 pCVea 3.01E+O2 3.05E402 2.13E-M)1 14 1.01 0.60 1.66 Acceptable Cs-134 pCi/ea 1.88E+02 1.72E+62 4.51E+00 38 0.91 0.75 133 Acceptable Cs-137 pCi/ea 137Et02 1.50E+<)2 8.25E+00 18 1.09 0.75 133 Acceptable Fe-59 pCi/ea 1.35E+<)2 1.55E+02 6.00E+00 26 1.15 0.75 133 Acceptable Mn-54 pO/ea 1.40E+O2 1.59E+02 7.60E+00 21 1.14 0.75 1.33 Acceptable Zn-65 pCi/ea 2.66E+02 3J1E+02 1.40E+01 22 1.17 0.75 1.33 Acceptable E13035 Gamma Filter CO-141 pCi/ea 1.52E+02 1.51E+02 6.10E+00 25 0.99 0.75 1.33 Acceptable CLDet 2 Co-58 pCi/ea 1.59E+02 1.68E+02 9.80E+60 17 1.06 0.75 133 Acceptable CO-60 pCi/ea 1.91E+02 1.98E+02 5.70E+00 35 1.04 0.75 133 Acceptable Cr-51 pQ/ea 3.01E4C2 3.09EtO2 1.71EtOI 18 1.03 0.75 1.33 Acceptable Cs-134 pCVea 1.88E+02 1.50Et02 4.54Et00 33 0.80 0.75 1.33 Acceptable Cs-137 pCi/ea 1.37E+02 1.49E+02 l.llE+01 13 1.09 0.60 1.66 Acceptable Fe-59 pQ/ea 1.35E+02 1.64E-rt)2 5.75E+00 29 1.21 0.75 1.33 Acceptable Mn-54 pCi/ea 1.40E+02 1.60E+<)2 8.70E+<XI 18 1.14 0.75 1.33 Acceptable Zn-65 pCi/ea 2.66E+02 3.12E+62 1.32E+01 24 1.17 0.75 1.33 Acceptable E13035 Gamma Filter Ce-141 pQ/ea 1.52E+02 1.64E+62 7.40E+00 22 1.08 0.75 1.33 Acceptable aDet3 Co-58 pCi/ea 1.59E+02 1.77E+62 l.OOE+Ol 18 111 0.75 1.33 Acceptable CO-60 pGea 1.91E+02 2.08E+62 6.55E+00 32 1.09 0.75 1.33 Acceptable G-51 pGea 3.01EtO2 2.84E+02 2.15Et01 13 0.94 0.60 1.66 Acceptable G-134 pG/ea 1.88Et02 1.60E-rt)2 4.97E+<<) 32 0.85 0.75 1.33 Acceptable G-137 pO/ea 1.37Et02 1.55E+62 l.OlEtfll 15 1.13 0.60 1.66 Acceptable Fe-59 pO/ea 1.35E+02 1.71Et02 125Sm 24 1.27 0.75 1J3 Acceptable Mn-54 pGea 1.40E+O2 1.64E+62 8.85E+00 19 1.17 0.75 133 Acceptable Zn-65 pCi/ea 2.66E-K)2 3.25E+62 1.57E+01 21 1.22 0.75 133 Acceptable PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 25

Table 7-1 Interlaboratory Comparison Results (Continued)

Sample Analysis Known PVNGS 1 sigma NRC Nuclide Units Resdutioo* Ratio Results ID Type Value Value Error Ranee Tech A El 3036 H-3 Water H-3 pCi/L 1.40E+04 1.23E+04 3.59E+02 34 0.88 0.75- 1.33 Acceptable TechB E13036 H-3 Water H-3 pCi/L 1.40E404 1.23E+04 3.58Ed02 34 0.88 0.75 - 1.33 Acceptable TechC E13036 H-3 Water H-3 pCiT 1.40E404 1.22E+04 3.58E+02 34 0.87 0.75 - 1.33 Acceptable TechD E13036 H-3 Water H-3 VO/h 1.40E+04 l,20E-tO4 3.56E-t02 34 0.86 0.75 - 1.33 Acceptable TechE E13036 H-3 Water H-3 pCi/L 1.40E+04 1.24E404 3.58E402 35 0.88 0.75- 1.33 Acceptable TechF E13036 H-3 Water H-3 pCi/L 1.40E-KM 1.25E+04 3.62Et02 34 0.89 0.75 - 1.33 Acceptable TechO E13036 H-3 Water H-3 pCi/L 1.40E404 1.23E+04 3.60EH)2 34 0.88 0.75 - 1.33 Acceptable

calculated fixtmPVNGS value/1 sigma error value NRC Acceptance Qiteria' Resolution Ratio 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.80-125

>200 0.85-1.18

' From NRC Infection Manual, procedire #84750, "Radioactive Waste Systems; Water Chemistry; Confirmatory Measurements" Table 7-1 Interlaboratory Comparison Results (Continued)

Sample Analysis ERAPT Nuclide Units PVNGS Assigned Value' Acceptance Limit Results Type Type Study Value Water Tritium MRA1>030 H-3 pCiT- 22,700 23,700 17900-28800 Acceptable Water Gross Beta RAD-U8 Gross Beta pCi/L 60.1 63.9 44.2-70.5 Acceptable

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

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 26

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 (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 2019 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 0.011 to 0.075 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. Radioiodine was not observed in any samples.

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 27

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 8.75 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 IB. The 1-131 levels ranged from 13 pCi/L - 17 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 1086 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.

Low levels of Cs-137 has been detected in Evaporation Pond 3A. Evaporation Pond 3A is in the process of being drained for liner repairs. The water inventory is very low, such that the sampling tool comes into contact with the bottom and sides of the pond, resulting in a small amount of salt and sediment intrude into the water sample. Evaporation Pond 3A has not received any influent from the plant since 2016, and the low levels of Cs-137 was not detectable until the water inventory in the pond was low, such that sampling tools also came into contact with the salt and/or sediment during sampling. The low levels of Cs-137 is consistent with diluted background levels seen in preoperational sediment analysis, and is attributed sediment intrusion from the surrounding area. No action levels have been exceeded.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 28

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. 1-131 activity in the sludge is consistent with historical values and, as previously discussed, is due to radiopharmaceuticals in the WR Influent. The concentration of 1-131 ranged from no detectable to 1020 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 3 Cooling Towers and Circulating Water canals was disposed of in the WR sludge landfill during 2019. 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- 2019 Page 29

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Table 8-6 Vegetation VEGETATION ODCM required samples denoted by

units are pCi/kg, wet DATE LOCATION TYPE COLLECTED I-13I Cs-134 Cs-137 Note Lettuce 17-Jan-19 <9 <17 <49 LOCAL Lettuce 14-Feb-19 <57 <45 <64 RESIDENCE Hybrid Lettuce 21-Mar-I9 <44 <58 <76 (She #47)* Lettuce 17-Apr-19 <32 <55 <62 Lettuce 17-May-19 <57 <46 <57 Lettuce 21-Jun-19 <54 <51 <56 Lettuce 19-JuM9 <54 <37 <66 Spinach 22-Aug-19 <55 <59 <78 No Sample Available - September No Saintle Available - October No Sample Available - November Lettuce 19-Dec-19 <53 <49 Arugula 17-Jan-19 <36 <8 <41 Spring Mix 17-Jan-19 <35 <45 <50 Kale 17-Jan-19 <41 <12 <57 Spring Mix 28-Feb-19 <32 <35 <60 Red Oak Lettuce 21-Mar-19 <49 <52 <49 Spinach 21-Mar-19 <44 <43 <46 COMMERCIAL Red Butter Lettuce 21-Mar-19 <36 <41 <49 FARM Kale 17-Apr-19 <41 <52 <42 (Site #62)* Spinach 17-Apr-19 <36 <28 <45 Spring Mix 17-Apr-19 <31 <35 <29 No Sample Available - May No Sample Available

June No Sample Available - July No Sample Available - August No Sample Available - September Green Romaine 24-Oct-19 <43 <40 <74 Red Romaine 24-Oct-19 <43 <47 <36 Arugula 24-Oct-19 <45 <53 <77 Spring Mix 26-NOV-19 <46 <48 <53 Spinach 26-NOV-19 <56 <55 <48 Tatsoi 26-NOV-19 <28 <11 <36 Lettuce 19-Dec-19 <45 <27 <40 Spring Mix 19-Dec-19 <35 <38 <61 No Sample Available - January No Sample Available - February No Sample Available - March So Sample Available - April LOCAL Lettuce 17-May-19 <35 <27 <49 Chard 21-Jun-19 <47 <51 <66 RESIDENCE Lettuce 19-JU1-19 <54 <57 <56 (Site #51)

No Sample Available - August No Sample Available - September No Sample Avaiable - October No Sample Avaiable - November No Sanmle Avaiable - December PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 35

Table 8-7 Milk ODCM required samples denoted by

units are pCi/liter SAMPLE DATE LOCATION COLLECTED 1-131 Cs-134 Cs-137 Ba-140 La-140 J-Note 18-Jan-19 <1 <1 <0.8 <3 <9 1 Local Resident February- No Sample Available Goats 22-Mar-19 <1 <1 <1 <3 <1 (Site #51)* ApriL No Sanple Available 17-May-19 <1 <1 <1 <4 <1 27-Jun-19 <1 <1 <1 <3 <1 3 19-JuH9 <1 <1 <1 <3 <1 23-Aug-19 <1 <1 <1 <3 <1 September- No Sample Available October- No Sample Available November- No Sample Available December- No Sample Available January- No Sample Available 22-Feb-19 <1 <1 <1 <3 <1 2 28-Mar-19 <1 <1 <1 <3 <1 Local Resident 25-Apr-19 <1 <1 <1 <3 <1 Goats 30-May-19 <1 <1 <1 <3 <1 (Site #53)* 27-Jun-19 <1 <1 <1 <3 <1 25-JuH9 <1 <1 <1 <3 <1 22-Aug-19 <1 <1 <1 <3 <1 26-Sep-19 <1 <1 <1 <4 <1 24-Oct-19 <1 <1 <1 <3 <1 22-NOV-19 <1 <1 <1 <3 <1 26-DCC-19 <1 <1 <1 <3 <1 lO-Jan-19 <1 <1 <1 <3 <1 Local Resident 07-Feb-19 <1 <1 <1 <3 <1 Goats 14-Mar-19 <1 <1 <1 <3 <1 (Site #54)* ll-Apr-19 <1 <1 <1 <3 <2 09-May-19 <1 <1 <1 <3 <1 13-Jun-19 <1 <1 <1 <3 <1 12-JuH9 <1 <1 <1 <3 <1 15-Aug-19 <1 <1 <1 <3 <1 13-Sep-19 <1 <1 <1 <3 <1 ll-Oct-19 <1 <1 <1 <3 <1 15-NOV-19 <1 <1 <1 <3 <1 20-DCC-19 <1 <1 <1 <3 <1 Note 1; Sample recounted; results reported are average of the two counts.

Note 2: Initial sample did not meet required LLD; media resampled andLLDmet Initial missed LLD documented via CR19-02899. Re-sampled results reported.

Note 3: Initial sample did not meet required LLD; media resampled and LLD met Initial missed LLD documented via CR 19-09506. Re-sampled results reported.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 36

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

units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED 1-131 Cs-134 Cs-137 In-111 Notes 8-Jan-19 <75 <177 15-Jan-19 283+/-176 <145 <142 22-Jan-19 <70 <125 29-Jan-19 492+/-156 <89 <142 5-Feb-19 868+/-221 <122 <169 12-Feb-19 547+/-151 <33 <140 19-Feb-19 408+/-167 <136 <138 26-Feb-19 356+/-123 <128 <126 5-Mar-19 4331142 <114 <128 12-Mar-19 <80 <126 19-Mar-19 1801119 <35 <104 26-Mar-19 3351136 <98 <178 WRF 2-Apr-19 2911148 <86 <105 CENTRIFUGE 9-Apr-19 5951206 <130 <143 WASTE SLUDGE 16-Apr-19 **NO SAMPLE WRF OUTAGE**
23-Apr-19 **NO SAMPLE WRF OUTAGE**
30-Apr-19 <88 <125 7-May-19 2881140 <135 <114 14-May-19 <92 <79 21-May-19 2911193 <144 <178 28-May-19 3511116 <104 <148 4-Jun-19 4491155 <85 <159 ll-Jun-19 3721220 <111 <173 18-Jun-19 557190 <45 <51 25-Jun-19 5511188 <104 <164 l-Jul-19 10201256 <84 <168 No required LLD for I-131 in Sludge/Sediment. Only values for detectable 1-131 are reported in this table.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 45
Table 8-11 Sludge/Sediment (Continued)
ODCM required samples denoted by
units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED 1-131 Cs-134 Cs-137 In-111 Notes 9-JuH9 298+/-136 <92 <154 16-JuH9 388+/-148 <92 <151 23-JuH9 248+/-133 <96 <102 30-JuH9 4211141 <101 <107 6-Aug-19 1641114 <100 <110 13-Aug-19 <39 <114 20-Aug-19 4271128 <23 <96 27-Aug-19 3151144 <77 <144 3-Sep-19 4921159 <124 <122 lO-Sep-19 2841124 <82 <117 17-Sep-19 126198 <109 <110 WRF 24-Sep-19 3761141 <61 <95 CENTRIFUGE 1-Oct-19 4971149 <67 <104 WASTE SLUDGE 8-Oct-19 **NO SAMPLE WRF OUTAGE**
15-Oct-19 **NO SAMPLE WRF OUTAGE**
22-Oct-19 **NO SAMPLE WRF OUTAGE**
29-Oct-19 **NO SAMPLE WRF OUTAGE**
5-NOV-19 **NO SAMPLE WRF OUTAGE**
12-NOV-19 1671166 <128 <126 19-NOV-19 <62 <124 26-NOV-19 3241131 <107 <132 3-Dec-19 1351109 <140 <148 10-Dec-19 <66 <119 17-Dec-19 1001120 <119 <111 23-Dec-19 2621115 <71 <89 30-Dec-19 2541138 <68 <107 No required LLD for I-131 in SIudge/SedimenL Only values for detectable I-131 are reported in this table.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 46
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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 2019 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 The baseline is calculated as the average of the previous 5 year measurements. The minimum differential dose (MDD) is calculated as 3 times the 90'* 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 2019 are presented in graphical form on Figure 9-1 (excluding transit control TLD #45). Figure 9-2 depicts the environmental TLD results from 2019 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- 2019 Page 56
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 from Unit 2 from Unit 2 from Unit 2 1 E30 29.13 18 ESE2 1.48 35 7.86 mms 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 0.74 47 E35 32.35 14 NNE2 155 31 NWl 1.03 48 E24 22.76 15 NE2 1.63 32 NT'mU 0.90 49 ENEll 11.32 16 ENE2 1.59 33 N^'4 4.05 50 WWVS 4.24 17 E2 1.39 34 NN\V5 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- 2019 Page 57
Table 9-2 Environmental TLD Results 5 mrem Palo Verde 2019 MOD.: 10 mrem 1 24.8 23.9 25.4 26.2 24.2 ND ND ND ND 99.3 99.7 ND 2 22.1 21.7 22.5 22.4 22.3 ND ND ND ND 88.5 88.9 ND 3 23.9 23.5 24.3 27.8 23.5 ND ND ND ND 95.5 99.1 ND 4 24.6 24.3 25.9 25.3 23.7 ND ND ND ND 98.5 99.2 ND 5 21.0 21.3 20.9 20.7 20.4 ND ND ND ND 83.9 83.3 ND 6 26.7 25.3 27.2 27.2 29.3 ND ND ND ND 106.6 108.9 ND 7 25.7 26.6 26.7 26.2 24.7 ND ND ND ND 102.8 104.3 ND 8 24.1 24.5 24.5 25.7 24.3 ND ND ND ND 96.5 99.0 ND 9 28.3 27.9 29.4 28.3 29.4 ND ND ND ND 113.0 114.9 ND 10 24.1 24.0 26.8 24.4 22.7 ND ND ND ND 96.2 98.0 ND 11 25.0 26.7 25.5 26.0 24.9 ND ND ND ND 99.9 103.1 ND 12 23.6 23.5 26.0 24.6 23.0 ND ND ND ND 94.6 97.0 ND 13 25.6 26.3 27.2 27.5 25.2 ND ND ND ND 102.6 106.3 ND 14 25.2 24.6 26.4 26.5 25.4 ND ND ND ND 100.6 102.9 ND 15 23.6 24.1 26.0 24.3 24.3 ND ND ND ND 94.5 98.7 ND 16 22.9 24.1 24.6 25.3 24.7 ND ND ND ND 91.7 98.6 ND 17 24.7 25.1 27.4 25.5 24.6 ND ND ND ND 98.8 102.6 ND 18 23.5 24.6 26.1 24.0 23.1 ND ND ND ND 94.0 97.7 ND 19 25.3 25.5 27.1 25.0 25.7 ND ND ND ND 101.0 103.3 ND 20 24.4 25.8 26.8 24.2 24.3 ND ND ND ND 97.7 101.1 ND 21 25.8 26.1 28.5 26.7 25.9 ND ND ND ND 103.3 107.2 ND 22 26.0 26.8 28.2 28.3 26.6 ND ND ND ND 103.8 109.9 ND 23 23.1 24.1 25.5 24.9 23.3 ND ND ND ND 92.5 97.8 ND 24 22.8 23.3 24.5 22.9 21.7 ND ND ND ND 91.2 92.3 ND 25 23.5 24.0 26.1 24.2 24.4 ND ND ND ND 94.2 98.7 ND 26 27.8 28.0 31.0 28.2 27.9 ND ND ND ND 111.1 115.0 ND 27 27.0 27.9 28.9 28.4 27.8 ND ND ND ND 107.8 113.0 ND 28 25.7 26.2 28.6 26.4 25.4 ND ND ND ND 103.0 106.5 ND 29 24.3 24.4 26.2 24.9 23.1 ND ND ND ND 97.2 98.6 ND 30 26.0 24.9 26.6 27.1 26.4 ND ND ND ND 104.1 105.0 ND 31 23.4 24.2 23.9 25.2 23.1 ND ND ND ND 93.7 96.4 ND 32 25.5 25.1 26.2 25.4 24.5 ND ND ND ND 102.1 101.1 ND 33 26.4 25.2 27.2 24.6 25.4 ND ND ND ND 105.5 102.4 ND 34 28.4 29.4 29.1 29.7 28.0 ND ND ND ND 113.5 116.2 ND 35 31.5 29.8 31.7 32.8 31.4 ND ND ND ND 126.0 125.7 ND 36 25.8 26.5 26.3 26.2 25.2 ND ND ND ND 103.4 104.3 ND 37 24.2 23.2 25.5 24.4 24.2 ND ND ND ND 96.8 97.3 ND 38 27.8 27.5 27.5 27.6 28.5 ND ND ND ND 111.1 111.1 ND 39 24.2 24.7 25.4 24.5 24.2 ND ND ND ND 96.9 98.8 ND 40 25.3 25.2 26.1 26.1 26.1 ND ND ND ND 101.3 103.5 ND 41 26.7 28.2 27.6 26.3 28.0 ND ND ND ND 106.7 110.1 ND 42 27.2 26.6 28.0 26.6 26.2 ND ND ND ND 109.0 107.5 ND 43 27.8 26.7 28.5 27.3 27.9 ND ND ND ND 111.3 110.4 ND 44 23.8 23.8 24.6 24.4 23.5 ND ND ND ND 95.2 96.3 ND 45 5.5 6.3 5.9 4.4 5.1 ND ND ND ND 22.2 21.6 ND 46 23.8 23.8 25.1 25.2 24.1 ND ND ND ND 95.2 98.2 ND 47 23.7
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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 2019.~~
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 2019 Land Use Census results identified new potential Radiological Effluent Release Report dose receptor locations. Each location was evaluated. The changes identified, and the evaluation results, are described below.
Nearest Resident There was one (1) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.697 mrem.
Milk Animal There were four (4) changes in milk animal status from the previous year. There were six (6) of the locations that were identified in the census which had the potential for having a dose greater than 20% that of our current sampling location with the lowest dose potential. The locations were visited by the REMP manager to evaluate program participation potential. As of October, 2019, five (5) of the locations no longer had goats, and one (1) location had only male goats. Dose calculations indicated the highest dose to be 0.737 mrem.
Vegetable Gardens There was no change in the nearest gardens identified in the previous year. Dose calculations indicated the highest dose to be 0.239 mrem.
See Table 10-1 for a summary of the specific results and Table 2-1 for current sample locations. Figure 10-1 through 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- 2019 Page 61~~
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) 2018 (Cow/Goat)
Resident 4.68E-2 Milk N 1.55 3.10 3.25 Garden 1.17E-1 Milk 1.26E-1 Resident 9.04E-2 NNE 1.52 NONE 2.82 Milk 2.66E-1 Resident 1.25E-1 Milk NE 2.16 NONE 4.62 Milk 1.21E-1 Resident 6.97E-1 Milk ENE 2.05 4.84 2.05 Garden 2.39E-1 Milk 6.97E-1 Resident 9.31E-2 E 2.81 NONE 4.28 Milk 2.39E-1 Resident 1.34E-1 ESE 3.06 NONE 3.37 Milk 6.10E-1 Resident 1.34E-1 SE 3.39 NONE 4.41 Milk 7.37E-1 SSE NONE NONE NONE NA S NONE NONE NONE NA Resident SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.45E-1 WSW 0.83 NONE NONE Resident 8.69E-2 W 0.76 NONE NONE Resident 5.45E-2 WNW NONE NONE NONE NA NW 0.93 NONE NONE Resident 4.96E-2 Resident 3.31E-2 Milk NNW 1.31 4.34 5.03 Garden 4.51E-2 Milk 3.37E-2 Comments:
Dose calculations were performed using CASPAR code and 2018 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- 2019 Page 62
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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 2019 calendar year. Where possible, the data were compared to pre-operational sample data.
All sample results for 2019 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 BTP on Environmental Monitoring.
1-131 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 1-131 detected in these locations are consistent with levels identified in previous years.
Cs-137 was detected in one Evaporation Pond 3 A sample. The sample result was 41 pCi/L +/- 9 pCi/L.
The required lower limit of detection for Cs-137 in water is 18 pCi/L; the action level for Cs-137 in water is 50 pCi/L. Evaporation Pond 3A has not received any influent during 2019 and is being drained to another evaporation pond to make repairs to the top liner. The water inventory in Evaporation Pond 3A is low, such that sediment that has collected in the pond was unavoidably collected in the sample. Cs-137 is known to bind to sediment, and the levels detected in the water sample is consistent with what was found in the preoperational soils in the surrounding area as a result of atmospheric bomb testing.
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 2019 resulting from the operation of PVNGS.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 66
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 2019 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) Name Mean If)* Mean (f)*
Range Distance and Range Range Direction Direct TLD -199 NA 25.5 Site #35 31.4(4/4) 25.6 (8/8) 0 Radiation (187/188)
(mrem/std. 19.0-32.8 8 miles 29.8-32.8 23.5-29.3 qtr.) 330° Air Gross Beta - 0.01 0.028 Site # 29 0.027 0.028 (51/52) 0 Particulates 520 (513/520) (50/52)
(pCi/m^) 0.011 - 1 mile 0.014- 0.010-0.066 0.075 270° 0.075 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 0
<LLD NA <LLD <LLD Broadleaf Gamma Spec. -
Vegetation 30 (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 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 67
Groundwater H-3 -12 2000 <LLD NA <LLD NA (pCi/liter)
Gamma Spec. -12 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 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 0 Gross Beta - 47 4 3.51 (47/48) Site #55 4.84(11/12) NA 0 2.33 - 8.75 3 miles 2.75 -8.75 214 H 16 2000 <LLD NA <LLD NA 0 Gamma Spec. - 47 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 0 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 68
Gamma Spec. - 29 Milk 1-131 1 <LLD NA <LLD <LLD 0 (pCi/liter) <LLD NA <LLD <LLD Cs-134 15 <LLD NA <LLD <LLD 0
<LLD NA <LLD <LLD Cs-137 18 <LLD NA <LLD <LLD 0
<LLD NA <LLD <LLD Ba-140 60 <LLD NA <LLD <LLD 0 La-140 15 <LLD NA <LLD <LLD 0 Gamma Spec. -18 Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 Surface Water (pCi/liter) 1-131 15 15(3/18) Site #59 17(1/6) NA 0 13-17 Onsite 180 17-17 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 41(1/18) Site #64 41 (1/2) NA 1 41-41 Onsite 190 41-41 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 H 25 3000 781 (11/18) Site #59 820 (6/6) NA 0 439-1086 Onsite 180 549-1086 (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- 2019 Page 69
~~12. References~~
~~1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985~~
~~2. 1985-2018 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. Offsite Dose Calculation Manual, Revision 28, 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, 2 Oct. 2017.~~
~~Web. 31 Jan. 2020.~~
~~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.~~
~~12. NEI 07-07, Nuclear Energy Institute, Industry Groundwater Protection Initiative - Final Guidance Document, Rev. 1, March 2019~~
~~13. Offsite Dose Calculation Manual, Revision 29, PVNGS Units 1, 2, and 3~~
~~Editorial changes made in March, 2020 to correct corrupted equations in Revision 28. No Technical changes were made.~~
~~PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2019 Page 70~~

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