ML081150510

Annual Radiological Environmental Operating Report for 2007

ML081150510
Person / Time
Site:	Palo Verde
Issue date:	04/18/2008
From:	Weber T Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05848-TNW/RKR
Download: ML081150510 (68)

Text

m A subsidiary of Pinnacle West Capital Corporation Palo Verde Nuclear Generating Station Thomas N. Weber Department Leader Regulatory Affairs Tel. 623-393-5764 Fax 623-393-5442 Mail Station 7636 PO Box 52034 Phoenix, Arizona, 85072-2034 102-05848-TNW/RKR April 18, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3 Docket Nos. STN 50-528/529/530 Annual Radiological Environmental Operating Report 2007 In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2007.No commitments are being made to the NRC in this letter. If you have any questions, please contact Glenn A. Michael at (623) 393-5750.Sincerely, C).4, I TNW/GAM/RKR/gat Enclosure cc: E. E. Collins Jr.M. T. Markley R. I. Treadway A. V. Godwin NRC Region IV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency (ARRA)A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway L Comanche Peak 0 Diablo Canyon L] Palo Verde 0 South Texas Project L] Wolf Creek

.ENCLOSURE Annual Radiological Environmental Operating Report 2007 i NUCLEAR GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2007 (

Reference:

RCTSAI 1643, Legacy Item No. 036843.01), Digitally signed by Drinovsky, Louis J Drlnovsk", IO: cn=Drinovsky, Louis J(Z33699)L u

• V 3.. 69,- 9 d !Reason: I am the author of this rp"L h uv J 6 Date: 2008.03.27 15:53:15 -07'00'P ri n Reviewed by: Approved by: C Digitally signed by Bungard, James P Bungard, Jameso (Z18012) Ja1es 4/N: cn=Bungard, PZ 1 01 2) 1..Reason:

I have reviewed this document PZ 8012, , .) Date: -2008.04.04 15:01:16 -07'00'Digitally signed by Gaffney, John P Gaffney, John (Z36459)DN. cn=Gaffney, John P(Z36459)P(Z3645 ./ I am approving this P (Z36 5 )" ,J Date: 2008.04.15 07:05:52 -07'00'Director, Radiation Protection TABLE OF CONTENTS 1. IN T R O D U C T IO N ..........................................................................................................................

2 2. DESCRIPTION OF THE MONITORING PROGRAM ...........................................................

3 2.1. 2007 PVNGS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................................

3 2.2. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CHANGES FOR 2007 ....................

3 2.3. REMP DEVIATIONS/ABNORMAL EVENTS

SUMMARY

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

4 2.4. SIGNIFICANT INVESTIGATION REGARDING GROUNDWATER PROTECTION

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

4 3. SAMPLE COLLECTION PROGRAM .....................................................................................

12 3 .1 .W A T E R .......................................................................................................................................

12 3.2. VEGETATION

..........

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

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

12 3 .3 .M IL K ..........................................................................................................................................

12 3 .4 .A IR .............................................................................................................................................

12 3.5. SLUD GE AND SEDIM ENT .........................................................................................................

13 4. ANALYTICAL PROCEDURES

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

13 4.1. A IR PARTICULATE

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

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

13 4.2. A IRBORNE RA DIOIODINE

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

13 4 .3 .M IL K ..........................................................................................................................................

13 4 .4 .V EG ETA T IO N ..............................................................................................................................

14 4.5. SLUD G E/SEDIM ENT ..........................................................................

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

14 4.6. WATER ...........................................................................

14 4 .7 .S O IL ...........................................................................................................................................

1 5 5. NUCLEAR INSTRUMENTATION

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

15 5.1. G AM M A SPECTROM ETER .........................................................................................................

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

17 7. INTERLABORATORY COMPARISON PROGRAM ..........................................................

22 7.1. QUALITY CONTROL PROGRAM ................................................................................................

22 7.2. INTERCOMPARISON RESULTS ..................................................................................................

22 8. DATA INTERPRETATIONS AND CONCLUSIONS

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

25 8.1. A IR P A R TICU LA TES ....................................................................................................................

25 8.2. AIRBORNE RADIOLODINE

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

26 8 .3 .V EG ETA T IO N ..........................................................................

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

2 6 8 .4 .M IL K .............................................................................................

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

2 6 8.5. DRINKING WATER ..................

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

I ........................................

26 8.6 .G RO UN D W A TER .........................................................................................................................

26 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 ii TABLE OF CONTENTS 8.7. SURFACE WATER..............................................................................................

26 8.8. SLUDGE AND SEDIMENT ......................................................................................

27 8.9. DATA TRENDS ..................................................................................................

27 9. THERMOLUMINESCENT DOSIMETER (TLD) RESULTS AND DATA......................

48 10. LAND USE CENSUS..................................................................................

54 10. 1. INTRODUCTION

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

54 10.2. CENSUS RESULTS ................................

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

54 11.

SUMMARY

AND CONCLUSIONS

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

56 12. REFERENCES

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

61 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 LIST OF TABLES TABLE 2.1 SAMPLE COLLECTION LOCATIONS

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

6 TABLE 2.2 SAMPLE COLLECTION SCHEDULE .............................................................................

7 TABLE 2.3 SUMMARIES OF 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 1 ST -2ND QUARTER ...................................

28 TABLE 8.2 PARTICULATE GROSS BETA IN AIR 3RD -4TH QUARTER .................................

29 TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES

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

30 TABLE 8.4 RADIOIODINE IN AIR 1 ST -2ND QUARTER ..........................................................

31 TABLE 8.5 RADIOIODINE IN AIR 3RD -4TH QUARTER .................................................................

32 T A B L E 8.6 V E G E T A T IO N .....................................................................................................................

33 T A B L E 8 .7 M IL K .....................................................................................................................................

34 TA B LE 8.8 D R IN K IN G W A TER .............................................................................................................

35 TA B LE 8.9 G R O U N D W A TER ...............................................................................................................

37 TA B LE 8.10 SU R FA CE W A TER ............................................................................................................

38 TABLE 8.11 SLUDGE/SEDIMENT

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

41 TABLE 9.1 TLD SITE LOCATIONS

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

49 TABLE 9.2 2007 ENVIRONMENTAL TLD RESULTS ........................................................................

51 TABLE 10.1 2007 LAND USE CENSUS ............................................................................................

55 TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

... 57 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 iv LIST OF FIGURES 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 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES)

...........

44 FIGURE 8.2 HISTORICAL GROSS BETA IN AIR (ANNUAL SITE TO SITE COMPARISONS)

C O M PA R E D T O PR E -O P .....................................................................................................................

45 FIGURE 8.3 GROSS BETA IN DRINKING WATER ...................................................................

46 FIGURE 8.4 EVAPORATION POND TRITIUM ACTIVITY ............................

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

47 FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES .................................

52 FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON

-PRE-OPERATIONAL VS 2007 ..... 53 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 V 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 2007, the following categories of samples were collected by APS:* Broad leaf vegetation

• Groundwater" Drinking water* Surface water" Airborne particulate and radioiodine

• Goat milk* Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmental gamma radiation.

The Environmental TLD program is also conducted by APS.The Arizona Radiation Regulatory Agency (ARRA) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by ARRA include onsite samples from the Reservoir, two (2) Evaporation Ponds, and two (2) deep wells. Offsite samples analyzed by ARRA include, two (2) local resident wells. ARRA also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring locations, eighteen (18) of which are duplicates of APS locations.

A comparison of pre-operational and operational data indicates no changes to environmental radiation levels.Low level tritium was discovered in subsurface water onsite (not considered potable) in February 2006 at Unit 3. A significant investigation was initiated to determine the source of the water, the extent of the condition, and corrective actions to protect groundwater.

See Section 2.4 for a detailed description of this event.(NOTE: Reference to APS throughout this report refers to PVNGS personnel)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 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. The REMP is performed in accordance with the federal requirements to provide a complete environmental monitoring program for nuclear reactors, and with concern for maintaining the quality of the local environment.

The program complies with the requirements of 10 CFR 50, Appendix I, PVNGS Technical Specifications, and with the guidance provided by the US Nuclear Regulatory Commission (USNRC) in their Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.This report contains the measurements and findings for 2007. All references are specifically identified in Section 12.The objectives of the REMP are as follows: 1) to determine baseline radiation levels in the environs prior to plant operation and to compare the findings with measurements obtained during reactor operations;

2) to monitor potential critical pathways of radio-effluent to the public; and 3) to determine radiological impacts on the environment caused by the operation of PVNGS.Results from the REMP help to evaluate sources of elevated levels of radioactivity in the environment (e.g., atmospheric nuclear detonations or abnormal plant releases).

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 1.8, 1986, and October 25, 1987, respectively.

PVNGS operational findings (historical) are presented in Reference 2.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 2

2. Description of the Monitoring Program APS and vendor organizations performed the pre-operational radiological environmental monitoring program, which began in 1979. APS and vendors continued the program into the operational phase.2.1. 2007 PVNGS Radiological Environmental Monitoring Program The assessment program consists of routine measurements of background 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. Sample analyses were performed by APS at the PVNGS Central Chemistry Laboratory.

Background gamma radiation measurements were performed by APS using TLDs at fifty (50) locations near PVNGS.In addition to monitoring environmental media, a land use census is performed annually to identify the nearest milk animals, residents, and gardens. This information is used to evaluate the potential dose to members of the public for those exposure pathways that are indicated., 2.2. Radiological Environmental Monitoring Program Changes for 2007 The control goat milk sample location (Site #53) was changed in June. The previous sample location became permanently unavailable.

> The two indicator vegetation sample locations (Site #47, 52) were changed in June.The previous sample locations no longer meet the garden criteria.> A new 45 acre Reservoir was constructed at the Water Reclamation Facility and was added to the REMP (Site #61).> A TLD was placed at a new school (Site #43) in the 4t" quarter.Refer to Table 2.1 for a description of all current sample locations (except TLDs).PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 3 2.3. REMP Deviations/Abnormal Events Summary During calendar year 2007, there were eight (8) deviations/abnormal events with regard to the monitoring program. Refer to Table 2.3 for more detail and any corrective actions taken.* The Water Reclamation Facility influent 1-131 concentration exceeded 100 pCi/liter the week of 1-16-07.* The goat milk sample from 4-13-07 did not meet the required l-131 LLD.* The air sample from Site #21 for particulate gross beta analysis was invalidated the week of 1/9-1/16." The air sample from Site #14A for particulate gross beta and radioiodine analysis was invalid the week of 3/13-3/19.

• The air sample from Site # 15 for particulate gross beta and radioiodine analysis was invalid the week of 8/28-9/4.* The air sample from Site #6A for particulate gross beta and radioiodine analysis was invalid the week of 9/18-9/24.

• The air sample from Site #4 for particulate gross beta analysis was invalidated the week of 9/24-10/2." The air sample from Site #40 for particulate gross beta and radioiodine analysis was invalid the two-week period of 10/29-11/13.

2.4. Significant Investigation Regarding Groundwater Protection (Follow-Up from 2006 AREOR)NOTE: Although not part of the REMP, this information is being provided due to the identification of measurable licensed radioactive material in the onsite environs (within the Radiological Controlled Area) and heightened sensitivity to communicate the potential to affect groundwater.

On February 15, 2006 Palo Verde personnel observed water leakage into the Unit 2 Essential Pipe Density Tunnel through the 'B' Spray Pond (SP) supply line penetration seal (documented on Significant CRDR No. 2869959).The direct root cause of the elevated levels of tritium in subsurface water samples from Unit 3 cannot be identified.

The sources of the tritium come from washout and localized small volume spills. There is no evidence at this time that supports the presence of a system leak.The washout described in the preceding paragraph is historical.

It is due to past operations of the Boric Acid Concentrator (BAC) during rain and wash down of roofs or washout from rain during times when tritium condensation from the ventilation system was present.Atmospheric modeling, conducted as part of the investigation, does not support that rain washout of tritium is the source of the subsurface tritiated water accumulation at identified concentrations, with current operating conditions (not allowing BAC operations during periods of rain).PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 4 Contributing causes of the condition in Unit 3 are the composition of the backfill and above ground grading and paving of the Unit 3 RCA yard.There is no indication that tritiated water has reached any aquifer. No Technical Specification effluent limits have been exceeded nor have any Offsite Dose Calculation Manual (ODCM) effluent limits been exceeded.

Federal effluent limits have not been exceeded.

Palo Verde has not identified any increased health or safety risk to the public or onsite personnel due to this condition.

The condition report is classified as significant by management direction due to recent industry events and public trust issues.Corrective actions are ongoing and include the installation of several monitoring wells in the RCA at all three Units. These monitoring wells are routinely sampled for radiological analyses.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 5 Table 2.1 SAMPLE COLLECTION LOCATIONS SAMPLE TYPE LOCATION DESCRIPTION air air air air air air air air air air drinking water vegetation drinking water drinking water milk vegetation milk milk drinking water (supplemental) groundwater groundwater surface water surface water surface water vegetation surface water APS Office Old US 80 Arlington School 371 Ave. and Buckeye-Salome Rd.NE Site Boundary 35 1t Ave.S Site Boundary W Site Boundary Tonopah Transmission Rd Wirth residence Garden of Eatin (replaced McCoy residence as of June)Berryman residence Sandoval residence Painter residence-goats Wright residence (replaced Branch residence as of June)Martin residence-goats (replaced Adams residence as of June)Hernandez residence-goats Gavette residence Well 27ddc Well 34abb Evaporation Pond #1 80 acre Reservoir 45 acre Reservoir (new location)Duncan Family Farms Evaporation Pond #2 NOTES:* Designates a control site (a) Distances and direction are from the center-line of Unit 2 containment and rounded to the nearest mile (b) Denotes a change in location or a new sample location Air sample sites designated with the letter 'A' are sites that have the same site number as a TLD location, but are not in the same location (e.g. site #6 TLD location is different from site #6A air sample location; site #4 TLD location is the same as site #4 air sample location)PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 6 Table 2.2 SAMPLE COLLECTION SCHEDULE SAMPLE AIR AIRBORNE GROUND DRINKING SURFACE SITE # PARTICULATE MILK RADIOIODINE VEGETATION WA TER WA TER WA TER 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 52 M/AA 53 M/AA 54 M/AA 55 W 57 Q 58 Q 59 W 60 W 61 W 62 M/AA 63 W W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 7 TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS Deviation/Abnormal Event 1. The Water Reclamation Facility influent 1-131 concentration exceeded 100 pCi/liter (actual concentration was 108 pCi/liter) the week of 1-16-07.2. The goat milk sample from 4-13-07 did not meet the required 1- 131 LLD.3. The air sample from Site #21 for particulate gross beta analysis was invalidated the week of 1/9-1/16.4. The air sample from Site #14A for particulate gross beta and radioiodine analysis was invalid the week of 3/13-3/19.

Actions taken 1. Phoenix sewage effluent is the supply for this water and is known to contain radiopharmaceutical 1-131. The Arizona Radiation Regulatory Agency is notified when this source of water exceeds an 1- 131 concentration of 100 pCi/liter (the threshold is exceeded on an infrequent basis). This is considered a courtesy notification (not regulatory) and no further action is required.2. The available sample volume was one-half the volume required to meet the 1- 131 LLD of 1.0 pCi/liter (actual volume was 500 ml and the MDA was 2 pCi/liter).

The decision was made to analyze the available sample because the other required LLDs for gamma emitting radionuclides could be met (the alternative would have been to not analyze the sample due to inadequate volume, resulting in no data for this sample period). This is not an adverse condition and no further actions are required.3. There was a verified power outage during the week. The sample result at this location was abnormally high when compared to all other sample locations.

The sample result was invalidated due to the anomalous result. Data from this location both the week prior to and after this sample period were acceptable.

No further actions are required.4. Power to this sample location had been disconnected on 3/9. The local utility office was contacted and power was restored.

Subsequent sample results were acceptable.

No further actions are required.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 8 TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS Deviation/Abnormal Event 5. The air sample from Site #15 for particulate gross beta and radioiodine analysis was invalid the week of 8/28-9/4.6. The air sample from Site #6A for particulate gross beta and radioiodine analysis was invalid the week of 9/18-9/24.

7. The air sample from Site #4 for particulate gross beta analysis was invalidated the week of 9/24-10/2.

8. The air sample from Site #40 for particulate gross beta and radioiodine analysis was invalid the two-week period of 10/29-11/13.

Actions taken 5. The air sample pump failed so the samples were invalidated as it was not possible to determine the sample volume. Subsequent sample results were acceptable.

No further actions are required.6. A power outage resulted in the inability to determine the sample volume so the samples were invalidated.

Subsequent sample results were acceptable.

No further actions are required.7. The sample result was 0.020 pCi/m 3 (nearly 50% less than the other nine sample locations) with a RSD of 15.2 % for the week. The cause of the lower value was indeterminate, so the sample result was invalidated.

Subsequent sample results were acceptable.

No further actions are required.8. A power outage resulted in the inability to determine the sample volume so the samples were invalidated.

Subsequent sample results were acceptable.

No further actions are required PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 9

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3. Sample Collection Program APS personnel using PVNGS procedures collected all samples.3.1. Water Weekly samples were collected from the in-service (45 or 80 acre) Reservoir, Evaporation Pond #1, Evaporation Pond #2, and four (4) residence wells. Samples were collected in one-gallon containers and 500 ml glass bottles. One liter from each weekly one-gallon sample was added to a monthly composite, which is preserved with nitric acid (HNO 3). The composite samples were then analyzed for gamma emitting radionuclides.

Residence wells were also analyzed for gross beta activity.

Weekly grab samples in glass bottles were composited quarterly and analyzed for tritium.Quarterly grab samples were collected from onsite wells 34abb and 27ddc. Samples were collected in one-gallon containers and 500 ml glass bottles. Samples were analyzed for gamma emitting radionuclides and tritium.Treated sewage effluent from the City of Phoenix was sampled as a weekly composite at the onsite Water Reclamation Facility (WRF), and analyzed for gamma emitting radionuclides.

A monthly composite was analyzed for tritium.3.2. Vegetation Vegetation samples were collected monthly, as available, and were analyzed for gamma emitting radionuclides.

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

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 12 3.5. Sludge and Sediment Sludge samples were obtained weekly from the WRU waste centrifuge (whenever the plant was operational) and analyzed for gamma emitting radionuclides.

Samples were collected using 1 liter containers.

Cooling tower sludge was analyzed for gamma emitting radionuclides prior to disposal in the WRF sludge landfill.Bottom sediment/sludge samples were obtained from Evaporation Pond #1 and Evaporation Pond #2 and analyzed for gamma emitting radionuclides.

4. Analytical Procedures The procedures described in this report are those used by APS to routinely analyze samples.4.1. Air Particulate 4.1.1. Gross Beta A glass fiber filter sample is placed in a stainless steel planchet and counted for gross beta activity utilizing a low background gas flow proportional counter.4.1.2. Gamma Spectroscopy The glass fiber filters are counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for specific radionuclides.

4.2. Airborne Radioiodine The charcoal cartridge is counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for 1-131.4.3. 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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 13 4.4. Vegetation 4.4.1. Gamma Spectroscopy The sample is pureed in a food processor, placed in a one liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for specific radionuclides.

4.5. Sludge/Sediment 4.5.1. Gamma Spectroscopy The wet sample is placed in a one-liter plastic marinelli beaker, weighed, and counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for specific radionuclides.

4.6. Water 4.6.1. Gamma Spectroscopy The sample is placed in a one-liter plastic marinelli beaker and counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for specific radionuclides.

4.6.2. Tritium The sample is evaluated to determine the appropriate method of preparation prior to counting.

If the sample contains suspended solids or is turbid, it may be filtered, distilled, and/or de-ionized, as appropriate.

Eight (8) milliliters of sample are mixed mwith fifteen (15) milliliters of liquid scintillation cocktail.The mixture is dark adapted and counted for tritium activity using a liquid scintillation counting system.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 14 4.6.3. Gross Beta A 200-250 milliliter sample is placed in a beaker. Five (5) milliliters of concentrated nitric (HN0 3) acid is added and the sample is evaporated down to about twenty (20) milliliters.

The remaining sample is transferred to a stainless steel planchet.

The sample is heated to dryness and counted for gross beta in a gas flow proportional counter.4.7. Soil 4.7.1. Gamma Spectroscopy The samples are sieved, placed in a one-liter plastic marinelli beaker, and weighed. The samples are then counted on a multichannel analyzer equipped with an HPGe detector.

The resulting spectrum is analyzed by a computer for specific radionuclides.

5. Nuclear Instrumentation 5.1. Gamma Spectrometer The Canberra Gamma Spectrometer consists of a Canberra System equipped with HPGe detectors having resolutions of 1.73 keV and 1.88 keV (as determined by full width half max with an energy of 0.5 keV per channel) and respective efficiencies of 21.5% and 38.4% (as determined by the manufacturer with Co-60). The Canberra System is used for all gamma counting.

The system uses Canberra developed software to search, identify, and quantify the peaks of interest.5.2. Liquid Scintillation Spectrometer A Beckman LS-6500 Liquid Scintillation Counter is used for tritium determinations.

The system background averages approximately 15-17 cpm with a counting efficiency of approximately 40% using a quenched standard.5.3. Gas Flow Proportional Counter The Tennelec S5E is a low background gas flow proportional counter for gross beta analysis.

The system contains an automatic sample changer capable of counting 50 samples in succession..

Average beta background count rate is about 1-2 cpm with a beta efficiency of approximately 30% for Cs-137.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 15

6. Isotopic Detection Limits and Reporting Criteria 6.1. Lower Limits of Detection The lower limits of detection (LLD) and the method for calculation are specified in the PVNGS ODCM, Reference

4. The ODCM required a priori LLDs are presented in Table 6.1. For reference, a priori LLDs are indicated at the top of data tables for samples having required LLD values.6.2. Data Reporting Criteria All results that are greater than the Minimum Detectable Activity (MDA) (a posteriori LLD) are reported as positive activity with its associated 2cy 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: S 0 S S 0 0 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 and includes a description of any sample results that did not meet a priori LLD requirements.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 16 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.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.A 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.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 17 The factors governing the calculation of the LLD and MDA values are discussed below: 1. Sample Size 2. Counting Efficiency The fundamental quantity in the measurement of a radioactive substance is the number of disintegrations per unit time. As with most physical measurements in analytical chemistry, an absolute measurement of the disintegration rate is seldom possible, rather it is necessary to compare the sample with one or more standards.

The standards determine the counter efficiency that may then be used to convert sample counts per minute (cpm) to disintegrations per minute (dpm).3. Background Count Rate Any counter will show a certain counting rate without a sample in position.

This background counting rate comes from several sources: 1) natural environmental radiation from the surrounding materials, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background counting rate will depend on the amounts of these types of radiation and the sensitivity of the counter to the radiation.

4. Background and Sample Counting Time The amount of time devoted to the counting of the background depends on the level of activity being measured.

In general, with low level samples, this time should be about equal to that devoted to counting a sample.5. Time Interval between Sample Collection and Counting Decay measurements are useful in identifying certain short-lived nuclides.

The disintegration constant is one of the basic characteristics of a specific radionuclide and is readily determined, if the half-life is sufficiently short. To ensure the required LLDs are achieved, appropriate decay correction values are used to account for radioactive decay during transit time and sample processing.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 18 Table 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (a priori)AIRBORNE ANALYSIS/

WATER PARTICULATE or MILK VEGETATION NUCLIDE (pCi/liter)

GAS (pCi/m 3) (pCi/liter) (pCi/kg, wet)Gross Beta 4 0.01 H-3 2000*Mn-54 15 Fe-59 30 Co-58, 60 15 Zn-65 30 Zr-95 30 Nb-95 15 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 NOTES:* 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.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 -2007 19 Table 6.2 ODCM REQUIRED REPORTING LEVELS AIRBORNE ANALYSIS/

WATER PARTICULATE MILK VEGETATION NUCLIDE (pCi/liter) or GAS (pCi/m 3) (pCi/liter) (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 NOTES:* For drinking water samples. This is a 40CFRI41 value. If no drinking water pathway exists, a value of 30,000 pCi/liter may be used.** If no drinking water pathway exists, a reporting level of 20 pCi/liter may be used.The values in this table are (calendar) quarterly average values, as stated in the ODCM.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 20 Table 6.3 TYPICAL MDA VALUES ANALYSIS/

AIRBORNE VEGETATION NUCLIDE WATER MILK PARTICULATE or (pCi/kg, wet)(pCi/liter) (pCi/liter)

GAS (pCi/m 3)Gross Beta 2.2 0.003 H-3 277 Mn-54 15 Fe-59 25 Co-58 13 Co-60 13 Zn-65 27 Zr-95 23 Nb-95 14 1-131 11 a 1 0.05 b 39 Cs-134 13 1 0.02 b33 CS-137 13 1 0.029b .59 Ba-140 45 La-140 15 1 NOTES: a -low level 1-131 is not required since there is no drinking water pathway b -Based on 433 m 3 volume PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING.REPORT

-2007 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, Rev. 1. Included in the program are procedures for sample collection, preparation and tracking, sample analysis, equipment calibration and checks, and ongoing participation in an interlaboratory comparison program. Duplicate/replicate samples are analyzed to verify analytical precision and sample methodology.

Comprehensive data reviews are performed including trending of data where appropriate.

During 2007, APS analyzed the following sample types under the interlaboratory comparison program;S 0 0 0 0 0 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 -2007 22 TABLE 7.1 INTERLABORATORY COMPARISON RESULTS Sample Analysis Nuclide Known PVNGS sigma Resolution Ratio Accept/Reject Type Type Value Value Error *Mixed Water Gamma Ce-141 160 161 7 23 1.01 Accept E5393-111 Cr-51 411 417 34 12 1.01 Accept Cs-134 194 166 5 33 0.86 Accept Cs-137 135 141 4 35 1.04 Accept Co-58 159 149 5 30 0.94 Accept Mn-54 133 131 4 33 0.98 Accept Fe-59 134 165 11 15 1.23 Accept Zn-65 268 297 9 33 1.11 Accept Co-60 191 174 5 35 0.91 Accept Tritium H-3 9040 7620 134 57 0.84 Accept E5397-111 Gross Beta gbeta 199 237 3 79 1.19 Accept E5392-111 Air Gross Beta gbeta 76.1 91 1.13 81 1.20 Accept E5394-111 Iodine Cart 1-131 79.1 80 2.4 33 1.01 Accept E5395-111 Mixed Gamma Ce-141 102 106 2 53 1.04 Accept E5396-111 Cr-51 262 282 10 28 1.08 Accept Cs-134 124 118 4' 30 0.95 Accept Cs-137 86.6 99 3 33 1.14 Accept Co-58 102 113 4 28 1.11 Accept Mn-54 85 100 3 33 1.18 Accept Fe-59 85.5 101 4 25 1.18 Accept Zn-65 171 199 6 33 1.16 Accept Co-60 122 133 3 44 1.09 Accept PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 23 TABLE 7.1 INTERLABORATORY COMPARISON RESULTS 1 Sample Analysis Nuclide Known PVNGS sigma Resolution Ratio Accept/Reject Type Type Value Value Error *Mixed Milk Gamma 1-131 34.7 33 2 17 0.95 Accept E5398-111 Ce-141 36.1 26 2 13 0.72 Accept Cr-51 92.5 73 9 8 0.79 Accept Cs-134 43.7 42 3 14 0.96 Accept Cs-137 30.5 30 2 15 0.98 Accept Co-58 35.8 35 2 18 0.98 Accept Mn-54 30 24 2 12 0.80 Accept Fe-59 30.1 26 3 9 0.86 Accept Zn-65 60.3 53 3 18 0.88 Accept Co-60 43 41 2 21 0.95 Accept* calculated from PVNGS value/i sigma error value Acceptance Criteria **Resolution Ratio<4 4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51-200 0.80-1.25>200 0.85-1.18"*From NRC Inspection Manual, Inspection Procedure 84750, "Radioactive Waste Treatment, And Effluent And Environmental Monitoring" PT PVNGS Certified Acceptance Sample Type Analysis Type Nuclide Value Value ' Limit 2 Results Water Mixed gamma Co-60 128 119 109 -129 Accept 8/14/2007 Zn-65 96.7 88.6 73.3 -104 Accept Ba-133 28.5 29.3 20.6 -38 Accept Cs-134 46 54.3 45.6-63 Accept Cs-137 51 50.3 41.6-59 Accept Tritium H-3 6840 8060 6660 -9450 Accept Gross Beta 30.9 25.3 16.6 -34.0 Accept ERA RAD-69 PT Mixed Gamma Study Results Water Gross beta 16.3 9.73 4.26 -18.2 Accept 12/18/2007 ERA RAD-71 Beta PT Study Results The certified values are verified to meet criteria as established by NIST NVLAP in Handbooks 150 and 150-19 and the USEPA in National Standards for Water Proficiency Testing Studies Criteria Document (December 30, 1998).2 "Acceptance Limits" have been calculated per the requirements of the USEPA in National Standards for Water Proficiency Testing Studies Criteria Document (December 30, 1998).PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 24

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

Random errors are beyond the control of the analyst.Efforts are made to minimize both systematic and random errors in the data reported.Systematic errors are minimized by performing reviews throughout the analysis.

For example, instruments are checked routinely with radioactive sources, and recovery and self-absorption factors based on individual sample analyses are incorporated into the calculation equations where necessary.

Random errors are reduced by comparing all data to historical data for the same site and performing comparisons between analytical results when available.

In addition, when data do not appear to match historical results, analyses may be rerun on a separate aliquot of the sample to verify the presence of the activity.

The acceptance of data is dependent upon the results of quality control samples and is part of the data review process for all analytical results.The "plus or minus value" reported with each analytical result represents the counting error associated with the result and gives the 95% confidence (2(y) interval around the data.Most samples contain radioactivity associated with natural background/cosmic radioactivity (e.g, K-40, Th-234, and Be-7). Gross beta results for drinking water and air are due to natural background.

Gamma emitting radionuclides, which can be attributed to natural background sources, are not indicated in this report.Results and interpretation of the data for all of the samples analyzed during 2007 are presented in the following sections.

Assessment of pre-operational and operational data revealed no changes to environmental radiation levels. The only measurable impact on the environment in 2007 was the low level tritium discovered in subsurface water onsite in the RCA in 2006. See Section 2.4for specific information.

8.1. Air Particulates Weekly gross beta results, in quarterly format, are presented in Tables 8.1 and 8.2.Gross beta activity at indicator locations ranged from 0.016 to 0.061 pCi/m 3.The associated counting error ranged from 0.001 to 0.004 pCi/mi 3.Mean quarterly activity is calculated using weekly activity over a thirteen (13) week period. Also presented in the tables are the weekly mean values of all the sites a's well as the percent relative standard deviation (RSD %) for the data. The findings are consistent with pre-operational baseline and previous operational results. The results are summarized in Table 11.1.Table 8.3 displays the results of gamma spectroscopy on the quarterly composites.

No Cs-134 or Cs-137 was observed.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 25 8.2. Airborne Radioiodine Tables 8.4 and 8.5 present the quarterly radioiodine results. No airborne radioiodine was observed in any of the samples.8.3. Vegetation Table 8.6 presents gamma isotopic data for the vegetation samples. No gamma emitting radionuclides were observed in any of the samples.8.4. Milk Table 8.7 presents gamma isotopic data for the goat milk samples. No gamma emitting radionuclides were observed in any of the samples.8.5. Drinking Water Samples were analyzed for gross beta, tritium, and gamma emitting radionuclides.

Results of these analyses are presented in Table 8.8. No tritium or gamma emitting radionuclides were detected in any samples. Gross beta activity ranged from less than detectable to a high of 5.6 pCi/liter (Berryman residence, April composite).

8.6. Groundwater Groundwater samples were analyzed 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 80 acres in size.The 45 acre Reservoir was constructed to allow for re-lining of the 80 acre Reservoir.

The two Evaporation Ponds receive mostly circulating water from main turbine condenser cooling and are about 250 acres each. A third pond is currently under construction.

Results are presented in Table 8.10. 1-131 was observed in the Evaporation Ponds in five (5) of the monthly composite samples (9-23 pCi/liter) and five (5) of the Reservoir monthly composite samples (11 to 23 pCi/liter).

1-131 is a result of radiopharmaceutical 1-131 in the Phoenix sewage effluent.Tritium was routinely observed in Evaporation Ponds 1 and 2. The highest concentration in Evaporation Pond #1 was 1496 pCi/liter and the highest concentration in Evaporation Pond #2 was also 2323 pCi/liter.

Tritium was not identified in the PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 26 Reservoir.

The tritium identified in the Evaporation Ponds has been attributed to plant gaseous effluent releases and secondary plant liquid discharges.

WRF Influent (Phoenix sewage effluent) samples collected by the WRF were analyzed for gamma emitting radionuclides and tritium. The results, presented in Table 8.10, demonstrate that 1-131 was observed routinely.

The highest 1-131 concentration was 108 pCi/liter (week of Jan. 16th). None of the samples analyzed indicated the presence of tritium.Table 8.10 also presents gamma spectroscopy and tritium measurements of samples collected from Sedimentation Basin #2. This basin collects rain water from site runoff and was dry for most of the year. Neither gamma emitting radionuclides nor tritium were detected in any of the three (3) samples taken in 2007.8.8. Sludge and Sediment 8.8.1. WRF Centrifuge waste sludge Sludge samples were obtained from the WRF centrifuge and analyzed by gamma spectroscopy.

1-131 in the WRF waste centrifuge sludge is consistent with historical values and, as previously discussed, is due to radiopharmaceuticals in the WRF influent.

1-131 was present in all fifty-two (52) samples ranging from 459 to 2117 pCi/kg.In- 111 was also identified in the sludge in four (4) samples. The highest concentration was 81 pCi/kg. It was previously established that In-Ill is in use in the Phoenix area as a radiopharmaceutical.

Results for WRF centrifuge waste sludge can be found in Table 8.11.8.8.2. Evaporation Ponds #1 and #2 sediment A set of eight (8) Evaporation Pond sediment samples indicated low levels of Cs-137 ranging from <MDA to 34 pCi/kg. These results are consistent with previous samples. Sample results can be found in Table 8.11.8.8.3. Cooling Tower sludge Sludge/sediment originating from the Unit 1 and Unit 2 Cooling Towers and/or Circulating Water canals was disposed of in the WRF sludge landfill during 2007. Sample results can be found in Table 8.11.8.9. Data Trends Figures 8.1-8.4 present data in graphical format. Historical data are displayed for comparison where practical.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 27 TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1st -2nd QUARTER ODCM required samples denoted by *__ __units are pCi/m 3 T____________

7i-,,' sti _________.t.

START Week# DATE STOP DATE Site Site Site Site Site Site 4 6A* 7A 14A* 15* 17A Site Site 21 29*Site Site 35 40*RSD Mean 1 2 3 4 5 6 7 8 9 10 11 12 13 26-Dec-06 2-Jan-07 9-Jan-07 16-Jan-07 23-Jan-07 29-Jan-07 5-Feb-07 12-Feb-07 20-Feb-07 26-Feb-07 5-Mar-07 13-Mar-07 19-Mar-07 2-Jan-07 0.040 9-Jan-07 0.041 16-Jan-07 0.037 23-Jan-07 0.051 29-Jan-07 0.043 5-Feb-07 0.051 12-Feb-07 0.045 20-Feb-07 0.021 26-Feb-07 0.019 5-Mar-07 0.023 13-Mar-07 0.041 19-Mar-07 0.046 26-Mar-07 0.023 0.043 0.040 0.033 0.036 0.037 0.035 0.038 0.035 0.038 0.042 0.039 0.052 0.045 0.054 0.049 0.020 0.019 0.021 0.045 0.046 0.024 0.042 0.039 0.040 0.039 0.041 0.037 0.032 0.036 0.033 invalid'0.051 0.048 0.052 0.047 0.049 0.041 0.038 0.042 0.042 0.038 0.048 0.046 0.050 0.046 0.044 0.047 0.043 0.044 0.045 0.044 0.022 0.020 0.019 0.021 0.019 0.020 0.018 0.019 0.018 0.018 0.021 0.019 0.020 0.023 0.019 0.042 0.045 b 0.042 0.040 0.039 0.045 invalid' 0.044 0.043 0.041 0.022 0.021 0.022 0.021 0.022 0.038 0.035 0.050 0.041 0.048 0.043 0.019 0.017 0.020 0.041 0.043 0.024 0.042 0.034 0.052 0.038 0.049 0.042 0.020 0.017 0.021 0.039 0.044 0.023 0.038 0.033 0.051 0.04 0.043 0.044 0.017 0.016 0.021 0.038 0.044 0.024 0.038 0.040 0.035 0.050 0.041 0.048 0.045 0.020 0.018 0.021 0.041 0.044 0.023 7.9 4.0 6.6 3.5 5.8 6.9 4.6 7.1 6.6 6.7 5.8 3.6 5.2 Mean 0.037 0.038 START STOP Site Site Week # DATE DATE 4 6A*0.037 0.032 0.036 0.035 0.034 Site Site Site Site Site 7A 14A* 15* 17A 21 0.035 Site 29*0.035 0.034 Site Site 35 40*0.035 Mean 4.7 RSD (%).14 15 16 17 18 19 20 21 22 23 24 25 26 26-Mar-07 2-Apr-07 0.026 2-Apr-07 9-Apr-07 0.033 9-Apr-07 16-Apr-07 0.026 16-Apr-07 23-Apr-07 0.027 23-Apr-07 1-May-07 0.032 1-May-07 8-May-07 0.030 8-May-07 15-May-07 0.041 15-May-07 22-May-07 0.038 22-May-07 29-May-07 0.028 29-May-07 5-Jun-07 0.034 5-Jun-07 12-Jun-07 0.029 12-Jun-07 18-Jun-07 0.034 18-Jun-07 25-Jun-07 0.029 0.031 0.044 0.024 0.024 0.033 0.030 0.044 0.039 0.029 0.035 0.030 0.038 0.037 0.024 0.022 0.026 0.025 0.025 0.030 0.033 0.036 0.035 0.032 0.024 0.026 0.027 0.028 0.023 0.023 0.023 0.023 0.025 0.024 0.032 0.028 0.032 0.032 0.029 0.026 0.027 0.029 0.026 0.027 0.041 0.038 0.042 0.041 0.038 0.033 0.033 0.039 0.036 0.038 0.029 0.026 0.030 0.028 0.026 0.037 0.035 0.037 0.035 0.032 0.030 0.026 0.029 0.031 0.028 0.038 0.035 0.037 0.038 0.035 0.033 0.031 0.033 0.032 0.033 0.026 0.036 0.024 0.024 0.026 0.027 0.042 0.037 0.029 0.035 0.029 0.035 0.033 0.026 0.035 0.027 0.029 0.032 0.031 0.041 0.037 0.029 0.037 0.028 0.037 0.035 0.025 0.032 0.024 0.023 0.029 0.031 0.036 0.039 0.028 0.033 0.031 0.038 0.035 0.026 0.035 0U025 0.025 0.031 0.028 0.040 0.037 0.028 0.035 0.029 0.037 0.033 8.9 11.1 6.7 8.2 7.6 7.1 5.9 6.2 4.7 4.9 5.2 4.3 6.7 Mean 0.031 0.034 0.031 0.029 0.032 0.032 0.030 0.031 0.033 0.031 0.031 a Power loss during this week caused abnormally high result (0.051 pCi/m3) with %RSD of 14.9. Sample invalidated due to anomalous result.4.0 bSample pump only ran from 3-5 to 3-9 due to power disconnect.

Sample volume was calculated using actual run time. cOOS due to no power.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 28 TABLE 8.2 PARTICULATE GROSS BETA IN AIR 3rd -4th QUARTER ODCM required samples denoted by *START STOP Site units are p C i/m 3 .. ... ..Site Site Site Site Site Site Site Site Site RSD Week# DATE DATE 4 6A* 7A 14A* 15*17A 21 29* 35 40* Mean (%)27 28 29 30 31 32 33 34 35 36 37 38 39 M 25-Jun-07 2-Jul-07 0.044 0.041 0.039 0.037 0.042 2-Jul-07 10-Jul-07 0.041 0.042 0.038 0.038 0.041 10-Jul-07 17-Jul-07 0.044 0.042 0.041 0.038 0.045 17-Jul-07 25-Jul-07 0.031 0.030 0.030 0.029 0.030 25-Jul-07 30-Jul-07 0.026 0.028 0.023 0.022 .0.023 30-Jul-07 7-Aug-07 0.031 0.034 0.031 0.029 0.029 7-Aug-07 14-Aug-07 0.033 0.040 0.039 0.033 0.036 14-Aug-07 21-Aug-07 0.037 0.041 0.034 0.033 0.039 21-Aug-07 28-Aug-07 0.033 0.037 0.036 0.035 0.037 28-Aug-07 4-Sep-07 0.037 0.034 0.032 0.035 invalida 4-Sep-07 11-Sep-07 0.034 0.036 0.032 0.031 0.034 11-Sep-07 18-Sep-07 0.038 0.040 0.039 0.034 0.040 18-Sep-07 24-Sep-07 0.022 invalidb 0.024 0.020 0.024 0.041 0.043 0.042 0.032 0.024 0.031 0.036 0.034 0.038 0.037 0.033 0.036 0.022 0.036 0.040 0.039 0.040 0.040 5.8 0.037 0.041 0.040 0.037 0.040 5.4 0.041 0.042 0.043 0.042 0.042 4.5 0.028 0.028 0.024 0.028 0.029 7.6 0.020 0.023 0.024 0.022 0.024 9.5 0.028 0.033 -0.036 0.031 0.031 7.8 0.036 0.037 0.035 0.035 0.036 6.3 0.036 0.039 0.039 0.035 0.037 7.4 0.034 0.035 0.036 0.034 0.036 4.5 0.036 0.033 0.038 0.032 0.035 6.5 0.035 0.038 0.036. 0.029 0.034 7.9 0.036 0.038 0.039 0.034 0.037 6.1 0.021 0.025 0.024 0.022 0.023 7.3 ean 0.035 0.037 0.034 0.032 0.035 0.035 START STOP Site Site Site Site Site Site DATE DATE 4 6A* 7A 14A* 15* 17A 0.033 0.035 0.035 0.032 0.034 4.5 Week #Site Site Site Site RSD 21 29* 35 40* Mean (%)40 41 42 43 44 45 46 47 48 49 50 51 52 24-Sep-07 2-Oct-07 invalidc 0.037 0.036 0.031 0.034 2-Oct-07 9-Oct-07 0.026 0.031 0.024 0.023 0.029 9-Oct-07 16-Oct-07 0.038 0.041 0.040 0.039 0.042 16-Oct-07 23-Oct-07 0.022 0.027 0.024 0.022 0.024 23-Oct-07 29-Oct-07 0.035 0.035 0.030 0.032 0.033 29-Oct-07 6-Nov-07 0.053 0.069 0.058 0.052 0.059 6-Nov-07 13-Nov-07 0.059 0.061 0.056 0.051 0.060 13-Nov-07 19-Nov-07 0.053 0.062 0.052 0.053 0.061 19-Nov-07 27-Nov-07

.0.051 0.061 0.054 0.049 0.055 27-Nov-07 4-Dec-07 0.036 0.046 0.038 0.036 0.038 4-Dec-07 11-Dec-07 0.033 0.036 0.036 0.031 0.035 11-Dec-07 18-Dec-07 0.039 0.045 0.042 0.040 0.044 18-Dec-07 26-Dec-07 0.036 0.037 0.034 0.033 0.035 0.036 0.028 0.037 0.023 0.031 0.054 0.058 0.054 0.057 0.036 0.033 0.041 0.034 0.035 0.035 0.036 0.031 0.035 6.3 0.026 0.027 0.026 0.025 0.027 8.9 0.038 0.040 0.037 0.036 0.039 5.0 0.024 0.024 0.024 0.024 0.024 5.9 0.029 0.032 0.035 -0.031 0.032 6.7 0.055 0.056 0.057 invalidb 0.057 8.9 0.055 0.057 0.056 invalidb 0.057 5.3 0.052 0.056 0.060 0.048 0.055 8.3 0.050 0.055 0.056 0.049 0.054 7.3 0.040 0.039 0.042 0.036 0.039 8.4 0.032 0.034 0.033 0.034 0.034 4.9 0.041 0.042 0.041 0.040 0.042 4.4 0.033 0.034 0.034 0.032 0.034 4.3 Mean Annual Average 0.040 0.045 0.040 0.038 0.042 0.040 0.039 0.041 0.041 0.035 0.040 6.6 0.036 0.039 0.036 0.033 0.037 0.036 0.034 0.036 0.036 0.033 0.036 4.5 a Sample pump failed, sample invalidated b Power out at sample location.

Unable to determine sample volume, sample invalidated.

c Sample result was 0.020 with a RSD of 15.2 %. Result suspect and unable to determine cause, so sample result was invalidated PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 29 TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES ODCM required samples denoted by *units are pCi/m 3 QUARTER ENDPOINT Site Site Site 4 6A* 7A Site Site Site 14A* 15* 17A Site Site Site Site 21 29* 35 40*NUCLIDE 26-Mar-07 25-Jun-07 24-Sep-07 26-Dec-07 Cs-134 Cs-137 Cs-134 Cs-137 Cs-134 Cs-137 Cs-134 Cs-137<0.0019<0.0024<0.0025<0.0026<0.0034<0.0048<0.0034<0.0017<0.0023<0.0042<0.0013<0.0029<0.0041<0.0050<0.0029<0.0029<0.0035<0.0039<0.0030<0.0047<0.0023<0.0028<0.0033<0.0035<0.0035<0.0027<0.0027<0.0028<0.0044<0.0052<0.0029<0.0057<0.0038<0.0030<0.0034<0.0030<0.0036<0.0064<0.0037<0.0035<0.0024<0.0029<0.0016<0.0028<0.0035<0.0036<0.0038<0.0036<0.0018<0.0025<0.0041<0.0037<0.0029<0.0043<0.0033<0.0010<0.0020<0.0025<0.0023<0.0025<0.0030<0.0047<0.0041<0.0044<0.0021<0.0025<0.0045<0.0039<0.0029<0.0039<0.0041<0.0047<0.0023<0.0023<0.0026<0.0028<0.0018<0.0031<0.0034<0.0068 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 30 TABLE 8.4 RADIOIODINE IN AIR 1st -2nd QUARTER ODCM required samples denoted by *START STOP Week # DATE DATE Site Site 4 6A*units are pCi/mr 3 I l'Quarter i< f .Site Site Site Site 7A 14A* 15* 17A Site Site 21 29*Site Site 35 40*1 2 3 4 5 6 7 8 9 10 11 12 13 26-Dec-06 2-Jan-07 9-Jan-07 16-Jan-07 23-Jan-07 29-Jan-07 5-Feb-07 12-Feb-07 20-Feb-07 26-Feb-07 5-Mar-07 13-Mar-07 19-Mar-07 2-Jan-07 9-Jan-07 16-Jan-07 23-Jan-07 29-Jan-07 5-Feb-07 12-Feb-07 20-Feb-07 26-Feb-07 5-Mar-07 13-Mar-07 19-Mar-07 26-Mar-07<0.066<0.035<0.042<0.034<0.036<0.039<0.068<0.035<0.040<0.034<0.032<0.061<0.037<0.036<0.064<0.048<0.064<0.050<0.013<0.056<0.036<0.032<0.031<0.045<0.067<0.056<0.044 <0.030<0.037 <0.043<0.037 <0.063<0.050 <0.028<0.049 <0.038<0.012 <0.041<0.067 <0.027<0.038 <0.028<0.030 <0.056<0.042 <0.030<0.051 <0.069a<0.061 invalidb<0.032 <0.064<0.050 <0.025 <0.034 <0.030 <0.065 <0.030<0.026 <0.042 <0.036 <0.049 <0.036 <0.059<0.021 <0.033 <0.053 <0.033 <0.041 <0.063<0.049 <0.042 <0.043 <0.032 <0.043 <0.035<0.046 <0.039 <0.040 <0.051 <0.047 <0.048<0.048 <0.036 <0.049 <0.041 <0.012 <0.031<0.061 <0.033 <0.034 <0.041 <0.056 <0.037<0.048 <0.033 <0.055 <0.031 <0.043 <0.034<0.044 <0.064 <0.027 <0.048 <0.033 <0.039<0.049 <0.027 <0.054 <0.039 <0.049 <0.039<0.027 <0.055 <0.030 <0.024 <0:049 <0.032<0.043 <0.053 <0.043 <0.062 <0.045 <0.069<0.030 <0.050 <0.036 <0.056 <0.026 <0.029.... ,:.i. ...... .' .f...... ...... ., ....2nd Q uarter z~- ..... I I: ...-.. ... -.. ... ...-. ... ... .START STOP Site Site Site Site Site Site Site Site Site Site Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29* 35 40*14-15 16 17 18 19 20 21 22 23 24 25 26 26-Mar-07 2-Apr-07 9-Apr-07 16'-Apr-07.

23-Apr-07 1-May-07 8-May-07 15-May-07 22-May-07 29-May-07 5-Jun-07 12-Jun-07 18-Jun-07 2-Apr-07 9-Apr-07 16-Apr-07 23-Apr-07 1-May-07 8-May-07 15-May-07 22-May-07 29-May-07 5-Jun-07 12-Jun-07 18-Jun-07 25-Jun-07<0.034<0.050<0.064<0.049<0.028<0.027<0.032<0.040<0.034<0.043<0.031<0.070<0.060<0.041<0.069<0.043<0.043<0.049<0.049<0.056<0.039<0.035<0.061<0.041<0.052<0.038<0.040 <0.056<0.044 <0.035<0.049 <0.050<0.042 <0.033<0.048 <0.031<0.067 <0.036<0.055 <0.037<0.030 <0.034<0.034 .<0.033<0.051 <0.035<0.034 <0.023<0.051 <0.061<0.034 <0.025<0.040 <0.052 <0.031 <0.050 <0.033 <0.028<0.034 <0.037 <0.055 <0.022 <0.043 <0.037<0.065 <0.055 <0.066 <0.069 <0.050 <0.040<0.035 <0.050 <0.029 <0.034 <0.038 <0.012<0.044 <0.036 <0.030 <0.034 <0.039 <0.033<0.043 <0.022 <0.064 <0.038 <0.052 <0.038<0.049 <0.043 <0.038 <0.035 <0.049 <0.046<0.034 <0.069 <0.029 <0.043 <0.031 <0.051<0.049 <0.032 <0.055 <0.029 <0.056 <0.035<0.056 <0.037 <0.050 <0.029 <0.051 <0.030<0.034 <0.034 <0.065 <0.036 <0.036 <0.031<0.066 <0.061 <0.066 <0.049 <0.038 <0.046<0.050 <0.030 <0.034 <0.033 <0.013 <0.028 Sample pump only ran from 3-5 to 3-9 due to power disconnect.

Sample volume was calculated using actual run time. b OOS due to no power.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 31 TABLE 8.5 RADIOIODINE IN AIR 3rd -4th QUARTER ODCM required samples denoted by *______ units are pCi/M 3 START Week # DATE STOP DATE Site Site Site Site Site Site Site 4 6A* 7A 14A* 15* 17A 21 Site Site Site 29* 35 40*27 28 29 30 31 32 33 34 35 36 37 38 25-Jun-07 2-Jul-07 10-Jul-07 17-Jul-07 25-Jul-07 30-Jul-07 7-Aug-07 14-Aug-07 21-Aug-07 28-Aug-07 4-Sep-07 11-Sep-07 18-Sep-07 2-Jul-07 10-Jul-07 17-Jul-07 25-Jul-07 30-Jul-07 7-Aug-07 14-Aug-07 21-Aug-07 28-Aug-07 4-Sep-07 11-Sep-07 18-Sep-07 24-Sep-07<0.035<0.037<0.033<0.029<0.047<0.024<0.043<0.035<0.039<0.047<0.039<0.047<0.049<0.048<0.040<0.055<0.048<0.051<0.037<0.045<0.028<0.043<0.037<0.046<0.030 invalidb<0.048 <0.028<0.031 <0.031<0.055 <0.042<0.038 <0.027<0.058 <0.050<0.034 <0.031<0.058 <0.036<0.033 <0.043<0.045 <0.045<0.064 <0.042<0.065 <0.040<0.030 <0.042<0.057 <0.067<0.059 <0.035 <0.058 <0.046 <0.038 <0.036<0.062 <0.033 <0.030 <0.032 <0.061 <0.025<0.061 <0.034 <0.035 <0.034 <0.057 <0.038<0.049 <0.038 <0.027 <0.037 <0.046 <0.033<0.048 <0.046 <0.068 <0.045 <0.064 <0.055<0.032 <0.031 <0.041 <0.031 <0.034 <0.034<0.069 <0.038 <0.070 <0.034 <0.046 <0.035<0.059 <0.037 <0.043 <0.039 <0.060 <0.042<0.036 <0.036 <0.065 <0.036 <0.066 <0.045 invalid' <0.060 <0.050 <0.054 <0.049 <0.061<0.068 <0.037 <0.065 <0.025 <0.054 <0.036<0.041 <0.034 <0.039 <0.028 <0.040 <0.044<0.042 <0.067 <0.059 <0.068 <0.058 <0.067 START STOP Site Site Week # DATE DATE 4 6A*Site Site 7A 14A*Site Site Site Site Site Site 15* 17A 21 29* 35 40*40 41 42 43 44 45 46 47 48 49 50 51 52 24-Sep-07 2-Oct-07 9-Oct-07 16-Oct-07 23-Oct-07 29-Oct-07 6-Nov-07.13-Nov-07 19-Nov-07 27-Nov-07 4-Dec-07 11 -Dec-07 18-Dec-07 2-Oct-07 9-Oct-07 16-Oct-07 23-Oct-07 29-Oct-07 6-Nov-07 13-Nov-07 19-Nov-07 27-Nov-07 4-Dec-07 11-Dec-07 18-Dec-07 26-Dec-07<0.044<0.050<0.063<0.058<0.055<0.048<0.069<0.067<0.047<0.068<0.042<0.027<0.042<0.031<0.059<0.036<0.054<0.063<0.055<0.065<0.069<0.031<0.055<0.065<0.062<0.056<0.038 <0.052<0.063 <0.063<0.054 <0.037<0.069 <0.063<0.069 <0.062<0.046 <0.046<0.054 <0.066<0.070 <0.048<0.051 <0.046<0.053 <0.036<0.041 <0.049<0.056 <0.046<0.029 <0.028<0.047 <0.052 <0.040 <0.057 <0.057 <0.040<0.046 <0.037 <0.060 <0.064 <0.064 <0.065<0.047 <0.055 <0.058 <0.040 <0.063 <0.070<0.034 <0.054 <0.043 <0.036 <0.063 <0.047<0.055 <0.062 <0.069 <0.064 <0.056 <0.067<0.039 <0.052 <0.050 <0.051 <0.053 invalidb<0.047 <0.063 <0.060 <0.061 <0.069 invalidb<0.060 <0.061 <0.069 <0.047 <0.068 <0.062<0.064 <0.041 <0.047 <0.057 <0.033 <0.053<0.046 <0.069 <0.037 <0.045 <0.053 <0.046<0.049 <0.041 <0.041 <0.063 <0.054 <0.033<0.039 <0.036 <0.069 <0.039 <0.050 <0.062<0.051 <0.038 <0.039 <0.033 <0.042 <0.031 a Sample pump failed, sample invalidated b Power out at sample location.

Unable to determine sample volume, sample invalidated.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 32 TABLE 8.6 VEGETATION ODCM required samples denoted by *units are pCi/kg, wet<60 <60<80 LOCATION TYPE DATE COLLECTED 1-131 Cs-134 Cs-137 BRANCH RESIDENCE NO SAMPLES AVAILABLE (Site #52)*Wright Residence replaced Branch as of June green cabbage 12-Jan-07

<35 <46 <76 red cabbage 12-Jan-07

<40 <36 <65 DUNCAN savoy cabbage 12-Jan-07

<54 <46 <47 FAMILY green cabbage 16-Feb-07

<46 <10 <62 FARMS red cabbage 16-Feb-07

<36 <36 <34 (Site #62)* green cabbage 16-Mar-07

<43 <32 <47 red cabbage 16-Mar-07

<58 <45 <50 green cabbage 11-May-07

<47 <47 <52 green cabbage 12-Oct-07

<55 <55 <42 green cabbage 16-Nov-07

<42 <51 <75 green cabbage 14-Dec-07

<36 <14 <42 MCCOY RESIDENCE NO SAMPLES AVAILABLE (Site #47)*Garden of Eatin' replaced McCoy as of June* PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 33 TABLE 8.7 MILK MILK ODCM required samples denoted by *units are pCi/liter SAMPLE LOCATION DATE COLLECTED<1 <15 <18 <60 1-131 Cs-134 Cs-137 Ba-140<15 La-140 PAINTER GOATS (Site #51)* NO SAMPLES AVAILABLE ADAMS GOATS (Site #53)* NO SAMPLES AVAILABLE Martin replaced Adams as of June HERNANDEZ GOATS (Site #54)12-Jan-07 13-Apr-07 11-May-07 17-Aug-07 14-Sep-07 12-Oct-07 16-Nov-07 14-Dec-07<1 <1 <1 <3 <1<2a <2 <2 <7 <2<1 <1 <1 <3 <1<1 <1 <1 <3 <1<1 <1 <1 <3 <1<1 <1t <1 <3 <1<1 <1 <1 <3 <1<1 <1 <1 <3 <1 Notes: a Sample volume was too low to obtain the required 1-131 LLD of 1.0 pCi/liter.

Sample was analyzed anyway and met all other LLDs.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 34 TABLE 8.8 DRINKING WATER ODCM required samples denoted by *units are pCifiiter<2000 SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 QTRLY <4.0 LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 H-3 Gross Beta Y BERRYMAN RESIDENCE (SITE #48)*29-Jan-07

<10 <12 <27 <12 <22 <12 <14 <9 <9 26-Feb-07

<11 <11 <29 <13 <28 <15 <22 <11 <12 26-Mar-07

<11 <13 <30 <15 <26 <14 <21 <11 <10 23-Apr-07, <13 <8 <26 <14 <24 <12 <18 <9 <11 29-May-07

<13 <13 <22 <14 <29 <13 <23 <9 <12 25-Jun-07

<12 <11 <27 <15 <23 <14 <22 <12 <13 30-Jul-07

<11 <10 <20 <12 <24 <10 <16 <9 <8 28-Aug-07

<12 <10 <25 <15 <28 <11 <18 <10 <11 24-Sep-07

<10 <9 <20 <12 <30 <12 <19 <10 <9 29-Oct-07

<13 <14 <28 <15 <27 <15 <23 <13 <10 27-Nov-07

<8 <9 <20 <11 <20 <9 <16 <8 <7 26-Dec-07

<13 <11 <23 <12 <29 <13 <21 <12 <10<11 <34 <10 > <3.3<12 <40 <15 <3.2<12 <38 <13 <269 <2.8<12 <41 <15 15.6 +/-2.1<13 <40 <15 L -<3.1<13 <42 <12 <272 <2.9<9 <34 <15 4.0 +/- 1.8<13 <42 <14 L--, 3.9 +/- 1.8<10 <37 <12 <275 <2.7<15 <48 <13 <3.1<10. <32 <12 L.,'ii <2.9<11 <44 <15 <270 4.3 +/- 1.8 GAVETTE RESIDENCE (SITE #55)29-Jan-07

<13 <12 <26 <13 <26 <13 <18 <12 <12 26-Feb-07

<10 <11 <23 <12 <24 <12 <19 <11 <11 26-Mar-07

<13 <13 <22 <15 <30 <13 <18 <12 <10 23-Apr-07

<12 <12 <24 <14 <25 <14 <19 <12 <12 29-May-07

<13 <12 <24 <14 <30 <13 <22 <12 <11 25-Jun-07

<13 <12 <22 <13 <26 <11 <19 <9 <9 30-Jul-07

<13 <12 <24 <12 <29 <14 <19 <13 <11 28-Aug-07

<13 <15 <26 <15 <27 <13 <20 <13 <12 24-Sep-07

<12 <13 -<28 <13 <30 <14 <22 <12 <11 29-Oct-07

<13 <13 <28 <14 <29 <13 <24 <12 <13 27-Nov-07

<10 <9 <21 <10 <23 <12 <18 <10 <9 26-Dec-07

<12 <12 <24 <13 <27 <14 <23 <12 <11<13 <41 <15 -3.2 +/- 1.7<11 <39 <15 L, I 2.6+/- 1.7<14 <41 <14 <270 3.7 +/- 1.5<14 <39 <15[7 7?77 3.0+/- 1.6<13 <34 <8 4.2 +/- 1.7<11 <41 <13 <273 3.4+ 1.6<14 <43 <15 4.8 +/- 1.5<15 <49 <14 L. i 3.8+/- 1.5<14 <43 <13 <275 4.0 +/- 1.5<13 <49 <14 <2.5<11 <36 <14 5.2 +/- 1.6<13 <39 <15 <270 4.5 +/- 1.5 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 35 TABLE 8.8 DRINKING WATER ODCM required samples denoted by *units are pCi/liter SAMPLE LOCATION<2000 MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 QTRLY <4.0 ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 H-3 Gross Beta WIRTH RESIDENCE (SITE #46)*29-Jan-07

<12 <14 <26 <12 <27 <12 <23 <12 <10 <13 <39 <15 1 3.2+/- 1.7 26-Feb-07

<13 <12 <22 <15 <29 <13 <24 <12 <10 <12 <40 <12 <2.6 26-Mar-07

<10 <10 <24 <14 <23 <13 <22 <10 <9 <10 <40 <15 <268 3.8+/- 1.5 23-Apr-07

<13 <11 <25 <15 <22 <11 <18 <10 <10 <12 <40 <13 <2.6 29-May-07

<13 <11 <21 <14 <26 <11 <16 <11 <11 <12 <43 <15 L <2.5 25-Jun-07

<8 <10 <21 <14 <30 <12 <20 <10 <8 <12 <41 <9 <270 3.0+/- 1.6 30-Jul-07

<11 <13 <24 <14 <22 <13 <18 <11 <11 <13 <40 <12 5.0+/- 1.6 28-Aug-07

<9 <9 <17 <13 <23 <10 <19 <8 <10 <11 <32 <12 C. 2.8+/- 1.5 24-Sep-07

<13 <12 <22 <12 <30 <12 <21 <13 <12 <12 <37 <14 <275 4.0+/- 1.5 29-Oct-07

<14 <11 <28 <13 <28 <13 <24 <11 <12 <13 <41 <12 <2.5 27-Nov-07

<13 <13 <26 <13 <27 <12 <22 <12 <10 <14 <42 <15 <2.3 26-Dec-07

<11 <12 <24 <15 <25 <14 <22 <12 <10 <15 <38 <15 <269 4.3+/- 1.5 SANDOVAL RESIDENCE (SITE #49) *29-Jan-07

<11 <11 <21 <10 <29 <12 <20 <11 <9 <12 <42 <14 1 <2.4 26-Feb-07

<12 <13 <28 <12 <30 <10 <20 <12 <12 <14 <47 <14 -- <2.4 26-Mar-07

<13 <10 <27 <13 <29 <13 <20 <12 <11 <12 <44 <15 <266 <2.0 23-Apr-07

<12 <11 <22 <13 <29 <13 <23 <13 <12 <11 <42 <15 <2.4 29-May-07

<12 <11 <21 <13 <29 <11 <22 <12 <10 <12 <41 <11 , <2.4 25-Jun-07

<11 <10 <22 <13 <30 <11 <21 <11 <11 <12 <41 <12 <272 <2.3 30-Jul-07

<15 <12 <24 <12 <25 <13 <27 <13 <14 <13 <40 <14 <2.0 28-Aug-07

<11 <12 <20 <12 <30 <11 <17 <9 <10 <11 <43 <15 <2.1 24-Sep-07

<11 <10 <21 <13 <30 <10 <20 <7 <11 <12 <41 <11 <274 <2.1 29-Oct-07

<12 <13 <24 <13 <27 <14 <24 <13 <12 <13 <48 <10 <2.3 27-Nov-07

<11 <10 <21 <10 <23 <10 <19 <9 <10 <13 <35 <14 <2.2 26-Dec-07

<13 <11 <26 <12 <30 <13 <22 <12 <12 <14 <48 <13 <267 <2.0 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 36 TABLE 8.9 GROUNDWATER ODCM required samples denoted by *units are pCi/liter SAMPLE I DATE <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137<60 <15 <2000 Ba-140 La-140 H-3 WELL 29-Jan-07

<9 <8 <17 <10 <20 <10 <14 <8 <8 <9 <29 <11 <283 27dde 23-Apr-07

<9 <11 <22 <12 <22 <13 <18 <11 <9 <10 <34 <15 <262 (Site #57)* 30-Jul-07

<12 13 <29 <14 <30 <15 <21 <12 <11. <14 <43 <12 <276 29-Oct-07

<11 <9 <25 <13 <30 <12 <18 <11 <9 <12 <35 <14 <264 WELL 34abb (Site #58)*29-Jan-07

<11 <10 <23 <13 <28 <13 <19 <11 <9 <11 23-Apr-07

<14 <12 <27 <13 <27 <14 <28 <15 <13 <14 30-Jul-07

<9 <9 <18 <10 <23 <12 <16 <9 <9 <9 29-Oct-07

<11 <11 <24 <12 <28 <13 <19 <13 <11 <12<39 <14 <279<53 <15 <262<31 <15 <276<44 <15 <261 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 37 TABLE 8.10 SURFACE WATER ODCM required samples denoted by *units are pCi/liter SAMPLE I MONTH <15 <15 <30. <15 <30 <15 <30 <15 <15 <18 <60 <15 LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140<3000 H-3 80 ACRE RESERVOIR (Site #60) *45 ACRE RESERVOIR (Site #61) *29-Jan-07

<14 <13 <24 <13 <27 <13 <25 26-Feb-07

<11 <12 <24 <12 <28 <11 <19 26-Mar-07

<14 <12 <26 <14 <21 <13 <19 23-Apr-07

<9 <11 <22 <13 <26 <11 <18 29-May-07

<11 <12 <22 <11 <27 <12 <20 25-Jun-07

<12 <12 <25 <13 <25 <11 <20 30-Jul-07

<9 <10 <22 <12 <22 <11 <21 28-Aug-07

<12 <11 <21 <13 <30 <14 <20 24-Sep-07

<6 <7 <11 <7 <14 <8 <12 29-Oct-07

<14 <11 <24 <13 <30 <11 <18 27-Nov-07

<12 <11 <24 <11 <26 <13 <19 26-Dec-07

<11 <12 <24 <13 <28 <11 <19 20 +/- 13 23 +/- 11<15 16 +/- 9<15<15<11<14 11 +/- 9<13<15 14 +/- 12<13<11<11<10<11<11<8<11<6<12<10<11<15<11<13<12<13<11<12<13<8<12<13<12<48<39<40<40<41<41<34<41<23<42<45<46<15 o , .. , <15<13 <270<12 7 7 7<12 Li iJ<14 <281<15 ,i: :, 7 >: <7 <272<14<13<15 <270 EVAP POND 1 (Site #59) *29-Jan-07

<12 <12 <22 <13 <29 <10 <20 26-Feb-07

<11 <13 <28 <14 <29 <11 <21 26-Mar-07

<12 <11 <22 <15 <28 <10 <19 23-Apr-07

<12 <12 <24 <13 <30 <10 <18 29-May-07

<12 <10 <25 <12 <30 <11 <20 25-Jun-07

<11 <12 <24 <12 <30 <12 <20 30-Jul-07

<11 <10 <28 <13 <30 <11 <22 28-Aug-07

<11 <10 <25 <13 <30 <11 <19 24-Sep-07

<13 <13 <30 <15 <28 <14 <23 29-Oct-07

<12 <10 <28 <14 " <27 <10 <24 27-Nov-07

<12 <13 <27 <13 <27 <13 <20 26-Dec-07

<13 <13 <30 <10 <30 <13 <22 23 +/- 10<14<12<10<12<10<10<10<12<13 10 +/- 8<15<10<11<9<10<11<11<11<11<12<8<11<12<13<15<10<13<13<13<14<13<14<13<13<13<37<44<40<36<40<37<31<40<45<40<38<41<14 ~~<12 1496+/- 160<13<12 L,< J<10 945 181<15 F~7<12 L~<15 1001 179<15 ... 7771<15 7494- 177<11 749+/-177 4 EVAP POND 2 (Site #63) *29-Jan-07

<11 <12 <26 <15 <29 <11 <19 26-Feb-07

<11 <11 <28 <11 <30 <12 <20 26-Mar-07

<11 <11 <24 <15 <27 <12 <21 23-Apr-07

<10 <10 <23 <14 <30 <10 <17 29-May-07

<10 <10 <24 <11 <28 <10 <19 25-Jun-07

<13 <11 <26 <14 <30 <12 <22 30-Jul-07

<13 <13 <24 <11 <30 <13 <20 28-Aug-07

<12 <12 <27 <13 <29 <12 <22 24-Sep-07

'<11 <11 <25 <15 <30 <11 <22 29-Oct-07

<12 <13 <26 <12 <30 <12 <21 27-Nov-07

<11 <11 <24 <14 <29 <10 <21 26-Dec-07

<13 <14 <28 <14 <29 <13 <21<rl<11 18 +/- 17<12 9+/-10<14<11<15 19+/--8<12<10<13<10<10<11<10<10<12<11<11<11<11<9<10<14<14<14<13<13<13<14<14<12<14<13<14<40<38<41<39<35<44<39<44<41<43<38<50<10<11<12 2323+/- 166<12 7777<11 Lfl:<12 1095 +/-- 182<7<14<15 1047+/-- 182<11<11<12 1047 +/-- 181 Note: The 80-acre Reservoir was out of service for most of the year for re-lining.

Both Reservoirs have the same supply from the WRF.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 38 TABLE 8.10 SURFACE WATER ODCM required samples denoted by *units are pCilliter DATE COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium SAMPLE LOCATION WRF INFLUENT 2-Jan-07 9-Jan-07 16-Jan-07 23-Jan-07 29-Jan-07 5-Feb-07 12-Feb-07 19-Feb-07 26-Feb-07 6-Mar-07 13-Mar-07 19-Mar-07 26-Mar-07 2-Apr-07 9-Apr-07 16-Apr-07 23-Apr-07 1-May-07 7-May-07 15-May-07 21 -May-07 28-May-07 4-Jun-07 11-Jun-07 18-Jun-07 25-Jun-07 2-Jul-07 9-Jul-07 16-Jul-07<13 <12 <25 <12 <28 <12 <20 27 +/- 12 <13<11 <12 <24 <15 <29 <11 <23 31 +/- 13 <12<11 <12 <24 <14 <30 <13 <21 108,+/- 21 <11<12 <13 <28 <14 <28 <13 <20 47 +/- 17 <12<12 <10 <27 <7 <30 <10 <21 50+/- 15 <12<12 <12 <24 <15 <25 <11 <22 42 +/- 12 <11<13 <14 <27 <12 <29 <15 <21 40 +/- 14 <12<13 <10 <23 <12 <29 <11 <22 54 +/- 19 <10<12 <11 <26 <13 <28 <11 <20 97 +/- 17 <11<13 <13 <27 <13 <24 <13 <21 59 +/- 14 <11<13 1 <12 <24 <10 <30 <10 <19 53+/- 13 <12<12 <11 <22 <15 <21 <11 <22 53 +/- 14 <11<13 <11 <20 <15 <26 <12 <19 46 +/- 15 <11<11 <11 <20 <12 <24 <13 <19 47:+/- 12 <10<12 <11 <26 <11 <28 <12 <20 <15 <11<12 <10 <27 <11 <22 <12 <20 91 +/- 17 <11<11 <9 <23 <12 <24 <11 <20 60 +/- 15 <9<12 <11 <24 <13 <24 <13 <19 32 +/- 12 <11<10 <12 <22 <13 <30 <11 <17 41 +/- 12 <8<12 <12 <27 <13 <28 <13 <22 26 +/- 12 <11<10 <10 <22 <12 <20 <10 <19 33 +/- 11 <8<13 <12 <30 <12 <27 <13 <23 69 +/- 16 <11<12 <10 <23 <12 <25 <12 <22 36 +/- 13 <10<11 <11 <24 <15 <29 <12 <22 19 +/- 13 <11<11 <10 <20 <15 <22 <12 <18 31 +/- 11 <11<10 <13 <23 <15 <26 <13 <21 32 +/- 16 <11<11 <12 <29 <14 <25 <-12 <22 18 +/- 13 <11<12 <11 <21 <13 <19 <12 <21 22 +/- 12 <10<13 <13 <23 <14 <28 <12 <19 <15 <11<12<14<11<14.<14<11<14<12<13<14<11<12<12<11<11<11<11<12<10<14<11<14<13<13<11<14<14<11<12<40<39<45<35<42<34<41<43<42<39<35<40<38<42<36<37<34<37<36<33<33<37<46<43<33<41<43<39<46<14<15<12 <287<13<13 <296<14<14 <275<14<14 2 287<15<15<11<12 7<13<14<15<15 <275< 14 < 12 <15 .. <15 ,<15 <291<12<15<12<13 <28'4<12<15 ý<11 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 39 TABLE 8.10 SURFACE WATER ODCM required samples denoted by *units are pCi/liter SAMPLE LOCATION DATE COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium WRF INFLUENT 23-Jul-07 30-Jul-07 7-Aug-07 14-Aug-07 20-Aug-07 27-Aug-07 3-Sep-07 10-Sep-07 17-Sep-07 24-Sep-07 2-Oct-07 9-Oct-07 15-Oct-07 22-Oct-07 29-Oct-07 06-Nov-07 13-Nov-07 19-Nov-07 27-Nov-07 4-Dec-07 11-Dec-07 17-Dec-07 25-Dec-07<13 <12<13 <12<11 <10<14 <11<11 <12<10, <9<11 <12<10 <11<10 <10<15 <13<13 13<12 <11<13 <12<13 <13<12 <12<12 <9*<11 <11<10 <9<12 <12<10 <10<12 <10<10 <9<15 <12<20<25<20<23<21<19<25<18<21<26<20<26<27<30<22<20<22<21<25<24<21<20<27<14 <24 <10 <10 41 +/- 11 <11 <10 <32 <15 ____<12 <30 <14 <22 <14 <12 <13 <41 <11 <285<12 <27 <11 <21 14 11 <10 <10 <40 <13<13 <26 <11 <22 38 14 <11 <13 <42 <10 <12 <26 <12 <19 <15 <9 <11 <38 <12 .<9 <24 <9 <20 <15 <9 <11 <38 <10 <282<14 <30 <10 <20 54 +/- 14 <11 <12 <42 <13<13 <21 <10 <16 25 +/- 10 <8 <11 <29 <9<13 -<22 <12 <21 32 +/- 15 <13 <12 <42 <12<15 <28 <13 <26 34 +/- 14 <13 <14 <45 <13 <282<13 <30 <10 <21 27 +/- 11 <12 <12 <43 <15<15 <28 <12 <16 24 +/- 10 <10 <11 <33 <10<13 <29 <13 <23 70+/- 18 <11 <11 <41 <15<11 <23 <14 <23 73 +/- 16 <12 <15 <47 <15<14 <30 <11 <22 31 +/- 12 <10 <12 <39 <14 <267<11 <30 <12 <20 <12 <10 <11 <36 <14<14 <30 <14 <21 25 13 <11 <12 <37 <11,<11 <25 <12 <18 41 10 <10 <12 <37 <13 "<11 <29 <12 <19 27 +/- 11 <11 <12 <40 <14 <279<11 <27 <11 <19 14 +/- 10 <10 <11 <35 <15 '§;j:<13 <25 <12 <17 25 +/- 10 <10 <11 <36 <15 ,<9 <25 <11 <18 95 +/- 17 <9 <10 <38 <15 ' ?<14 <25 <14 <21 44 +/- 15 <12 <12 <50 <12 <276 4-Dec-07 <10 <13 <24 <15 <30 <11 <22 <9 <12 <15 <40 <14 <310 SEDIMENT.

l1-Dec-07

<12 <14 <23 <10 <27 <13 <20 <12 <10 <12 <42 <15 <287 BASIN #2 26-Dec-07

<12 <11 <29 <15 <20 <15 <23 <11 <10 <15 <39 <13 <289 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 40 TABLE 8.11 SLUDGE/SEDIMENT ODCM required samples.denoted by *units are pCi/kg, wet SAMPLE LOCATION DATE COLLECTED 1-131 Cs-134 Cs-137 In-ill 4 WRF CENTRIFUGE WASTE SLUDGE 2-Jan-07 9-Jan-07 16-Jan-07 23-Jan-07 29-Jan-07 5-Feb-07 12-Feb-07 19-Feb-07 26-Feb-07 6-Mar-07 13-Mar-07 19-Mar-07 26-Mar-07 2-Apr-07 9-Apr-07 16-Apr-07 23-Apr-07 1-May-07 7-May-07 15-May-07 21-May-07 28-May-07 4-Jun-07 11-Jun-07 18-Jun-07 25-Jun-07 2-Jul-07 9-Jul-07 16-Jul-07 23-Jul-07 30-Jul-07 7-Aug-07 14-Aug-07 1531 +/- 174 1003 +/- 121 1477 +/- 169 2117 +/- 232 1130 +/- 152 1418 +/-.178 974+ 132 1636 184 1158 147 1765 + 214 1223 +/- 161 995 +/-26 1434 +/- 177 1202 +/- 150 1307 +/- 152 860 +/- 122 1139+ 135 1006+/- 132 861 + 118 826 +/- 111 826 +/- 104 1377 + 175 850 110 728 + 96 1182 146 820++/- 101 605 + 82 476 +/- 71 459 +/- 69 643 +/- 93 606 +/- 83 466 +/- 77 671 +/- 95<19<18<19<19<17<38<33<22<28<34<38<25<35<28<20<26<28<28<20<20<24<32<20<21<22<18<23<17<26<26<20<25<18<26<28<28<16<23<33<29<26<32<42<38<22<37<35<23<7<27<20<43<32<21<22<25<27<33<25<26<25<31.<34<30<19<17 81 47 34 + 25 38 + 22-38 35 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 41 TABLE 8.11 SLUDGE/SEDIMENT ODCM required samples denoted by *units are pCi/kg, wet SAMPLE LOCATION DATE COLLECTED 1-131 Cs-134 Cs-137 In-Ill WRF CENTRIFUGE WASTE SLUDGE 20-Aug-07 27-Atig-07 3-Sep-07 10-Sep-07 17-Sep-07 24-Sep-07 2-Oct-07 9-Oct-07 15-Oct-07 22-Oct-07 29-Oct-07 6-Nov-07 13-Nov-07 19-Nov-07 27-Nov-07 4-Dec-07 11-Dec-07 17-Dec-07 24-Dec-07 770 100 789- 100 1079§ 131 1274 -149 957 +/- 121 927- 116 1087 -142 660 -95 844- 138 1060 +/- 160 1460 +/- 180 772 -109 532 -85 843 -134 804- 112 1019 -150 634 -104 622 +/-- 123<20<21<25<20<18<27<20<18<32<26<26<26<26<32<24<39<21<35<23<22<20<29<18<18<32<30<40<36<31<35<32<35<26<8<37<35 1566 +/- 229 <37 <28 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 42 TABLE 8.11 SLUDGE/SEDIMENT ODCM required samples denoted by *Units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED Cs-134 Cs-137 (N) 5-Dec-07 <9 13 +/- 9 (E) 5-Dec-07 <11 <14 EVAP POND 1 (S) 5-Dec-07 <8 13 +/- 9 (W) 5-Dec-07 <9 <16 (C) N/A N/A N/A (N)(E)EVAP POND 2 (S)(W)(C)5-Dec-07 5-Dec-07 5-Dec-07 5-Dec-07 N/A<10<11<10<10 N/A<16<15 22 +/- 14 34+/- 11 N/A COOLING TOWER SLUDGE UNIT APPROXIMATE ISOTOPE ACTIVITY RANGE SAMPLE TYPE FRACTION OF SAMPLES CYCLE VOLUME (yd 3) (uCi/ml) ABOVE MDA U2R13 449 Co-60 <MDA to 5.65E-07 31 of 32 I Cs-137 <MDA to 1. 14E-07 tower/canal sludge 17 of 32 U1R13 105 Cs-137 <MDA to 7.93E-08 6 of 32 tower/canal sludge PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 43 FIGURE 8.1 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES)Gross Beta in Air 1998-2007 1.000 0.100 u0.010 0.001 o ---.0: PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 44 FIGURE 8.2 HISTORICAL GROSS BETA IN AIR (ANNUAL SITE TO SITE COMPARISONS)

COMPARED TO PRE-OP control location-Gross Beta in Air Particulates-pre-operational (1981-1985)

-1998--o--1999 2000 2001-2002 2003* 2004* 2005-*- 2006* 2007 0.100 0.090 -0.080 -0.070 4 0.060 +U 0.050 +0.040 0.030 0.020 0.010 0.000 o<o oq<)(1 (10 0)0)CD Sample Location Site 7A is not included since the location changed since the pre-operational period A known high bias has occurred in gross beta data since the onsite laboratory began analysis in 1994 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 45 FIGURE 8.3 GROSS BETA IN DRINKING WATER 10 7r-Wirth (site #46)Gavette (site #55)--- Berryman (site #48)-Sandoval (site #49)L--I F e I I I I I I I I-Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec NOTES: MDA values plotted as activity (e.g. <2.3 is plotted as 2.3)PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 46 FIGURE 8.4 EVAPORATION POND TRITIUM ACTIVITY 5000 4000 3000 2000 1000 0 00 00 00 00- 00 00 00 0w 00 00N 00 00 C:, mN mN ON ' ON O N O N O N ON O -00~~ 00 00 w wm PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 47

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 forty-nine locations from one to thirty-five miles from the PVNGS.TLD locations are shown in Figures 2.1 and 2.2 and are described in Table 9.1. TLD results for 2007 are presented in Table 9.2. Historical environmental gamma radiation results for 1985 through 2007 are presented in graphical form on Figure 9.1 (excluding transit control TLD #45).Figure 9.2 depicts the environmental TLD results from 2007 as compared to the pre-operational TLD results (excluding sites #41, #43, and #46-50 as they were either deleted or had no pre-op TLD at these locations for comparison).

The site to site comparisons indicate a direct correlation with respect to pre-operational results. It is evident that the offsite dose, as measured by TLDs, has not changed since Palo Verde became operational.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 48 TABLE 9.1 TLD SITE LOCATIONS (distances and directions are relative to Unit 2 in miles)TLD SITE 1 2 3 4 5 6*7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 LOCATION E30 ENE24 E21 E16 ESEll SSE31 SE7 SSE4 S5 SE5 ESE5 E5 NI NNE2 NE2 ENE2 E2 ESE2 SE2 SSE2 S3 SSW3 W5 SW4 WSW5 SSW4 SW1 WSW1 W1 WNW1 NW1 NNW1 NW4 NNW5 NNW8 N5 NNE5 NE5 ENE5 N2 ESE3 N8 LOCATION DESCRIPTION Goodyear Scott-Libby School Liberty School Buckeye Palo Verde School APS Gila Bend substation OldUS 80 and Arlington School Rd Southern Pacific Pipeline Rd.Southern Pacific Pipeline Rd.355th Ave. and Elliot Rd.339th Ave. and Dobbins Rd.3 3 9 th Ave. and Buckeye-Salome Rd.N site boundary NNE site boundary.NE site boundary, WRF access road ENE site boundary E site boundary ESE site boundary SE site boundary SSE site boundary S site boundary SSW site boundary N of Elliot Rd N of Elliot Rd N of Elliot Rd S of Elliot Rd SW site boundary WSW site boundary W site boundary WNW site boundary NW site boundary NNW site boundary S of Buckeye Rd 3 9 5 th Ave. and Van Buren St.Tonopah Wintersburg Rd. and Van Buren St.3 6 3 rd Ave. and Van Buren St.3 5 5 th Ave. and Buckeye Rd.343 Ave. N of Broadway Rd.Wintersburg Arlington School Ruth Fisher School PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 49 TABLE 9.1 TLD SITE LOCATIONS (distances and directions are relative to Unit 2 in miles)TLD SITE-43 44*45**46 47 48 49 50 LOCATION NE5 ENE35 Onsite ENE30 E35 E24 ENE 11 WNW5 LOCATION DESCRIPTION Winters Well School El Mirage Central Laboratory (lead pig)Litchfield Park School Littleton School Jackrabbit Trail Palo Verde Rd.S of Buckeye-Salome Rd.* 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 -2007 50 TABLE 9.2 2007 ENVIRONMENTAL TLD RESULTS Units are mrem/std qtr-TLD site # -lst Quarter ý2nd!Quakrtý 93rd Quarter. 4th Quarter> "v,,,erage 1 22.8 25.6 19.0 22.0 22.4 2 23.0 21.8 18.9 20.4 21.0 3 22.9 21.2 18.7 20.7 20.9 4 23.4 22.7 20.1 22.2 22.1 5 21.7 21. 4 18.4 20.5 20.5 6(control) 27.7 25.9 22.5 25.4 25.4 7 26.1 24.3 23.4 24.5 24.6 8 24.0 24.0 20.0, 22.4 22.6 9 26.9 25.9 23.5 27.4 25.9 10 25.0 23.9 20.3 23.3 23.1 11 26.3 24.4 21.1 23.8 23.9, 12 24.5 23.6 19.9 21.4 22.4 13 26.2 25.4 21.8 24.3 24.4 14 24.2 23.4 19.6 24.3 22.9 15 25.4 23.8 20.0 22.5 22.9 16 .23.3 22.6 18.5 20.5 21.2 17 26.3 24.8 21.2 23.8 24.0 18 25.1 23 .3 19.7 23.1 22.8 19 26.7 24.7 21.7 23.7 24.2 20 25.1 23.7 20.7 24.1 23.4 21 26.6 25.0 20.7 24.5 24.2 22 28.1 25.9 22.1 25.4 25.4 23 23.8 22.9 19.6 21.9 22.1 24 23.1 22.5 18.9 21.4 21.5 25 23.0 21.5 19.6 22.3 21.6 26 28.9 26.2 23.7 26.1 26.2 27 28.0 26.6 24.1 26.8 26.4 28 26.4 24.9 22.7 26.1 25.0 29 25.0 22.6 21.4 23.6 23.2 30 27.0 24.7 22.3 24.4 24.6 3i 24.7 21.7 19.9 23.0 22.3 32 26.7 23.7 21.6 24.6 24.2 33 26.9 26.5 22.4 24.5 25.1 34 29.2 28.7 24.5 27.0 27.4 35 32.3 32.2 27.2 30.4 30.5 36 26.8 25.3 22.9 23.8 24.7 37 23.4 23.6 20.8 22.8 22.7 38 28.4 27.4 24.7 26.7 26.8 39 24.8 23.9 21.5 23.5 23.4 40 26.0 24.7 20.6 24.4 23.9 41 24.4 23.2 20.6 22.5 22.7 42 31.2 30.2 *27.2 27.6 29.1 43 NA NA NA 26.3 26.3 44 (control) 20.7 19.7 17.7 19.2 19.3 45 (transit control) 5.6 5.5 4.8 5.3 5.3 46 28.1 27.0 23.6 25.0 25.9 47 24.2 23.1 20.8 22.1 22.6 48 25.1 23.2 21.5 22.4 23.1 49 23.4 21.6 19.8 22.1 21.7 50 20.0 18.2 17.0 18.8 18.5 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 51 FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES I -- ... IA -~.30.0 stIVL 1 4 Lr-BASELINE----10YEARMEAN 28.0 26.0 79 24.0 E 22.0 1 -' 7 20.0 000 00000000 N N O O N ON N O O. O ONcuN m O m m m w N 0 m00 00000 0000000 w ) 0)c 6 n r 0) 0) CA En 0) 0)c n: n c ý 5; n 'ýc n ýE 5L 5 (PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 52 FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON

-PRE-OPERATIONAL VS 2007 35 -T Control TLD 30 S25 20=15~1 Pre-op (1984-1985) 10 --- 2007 Average 5 1 3 5 7 9 11 13 15 17 ý 19 21 23 TLD Number 25 27 29 31 33 35 37 39 42 45 TLD #41 monitoring location was deleted in June, 2000 due to school closing (this TLD was placed at new school in 2004)TLD #43 monitoring location was deleted in 1994 due to school closing (this TLD was placed at a new school in 2007)TLDs #46-50 are not included since they were not included in the pre-op monitoring program PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 53

10. Land Use Census 10.1. Introduction In accordance with the PVNGS ODCM, Section 6.2, the annual Land Use Census was performed within five miles of Unit 2 containment in May-June 2007.Observations were made in each of the 16 meteorological sectors to determine the nearest milking animals, residences, and gardens of greater than 500 square feet. This census was completed by driving the roads and speaking with residents.

The results of the Land Use Census are presented in Table 10.1 and discussed below.The directions and distances listed are in sectors and miles from the Unit 2 containment.

10.2. Census Results Nearest Resident There were two (2) changes in nearest resident status. Dose calculations indicated the highest dose to be 0.188 mrem.Milk Animal There was one (1) change in milk animal (goat, control location, NE30) status. Dose calculations indicated the highest dose to be 0.273 mrem.Ve2etable Gardens There were three (3) changes in nearest garden status. Dose calculations, indicated the highest dose to be 0.209 mrem.See Table 10.1 for a summary of the specific results and Table 2.1 for current sample locations.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 54 I ý '.' , .TABLE 10.1 2007 LAND'USE CENSUS (Distances and directions are relative to Unit 2 in miles)NEAREST NEAREST NEAREST CALCULATED DOSE SECTOR RESIDENT GARDEN MILK ANIMAL (mrem) CHANGE (COW/GOAT)

FROM 2006 N 1.55 3.10 NONE Resident 3.94E-02 IGarden 9.07E-02 NNE 1.52 3.30 2.05 Resident 6.98E-02 Garden Garden 1.50E-01 Milk 2.73E-01 NE 2.16 NONE 3.91 Resident 9.53E-02 Milk 2.50E-01 ENE 2.16 2.63 4.84 Resident 5.84E-02 Resident Garden 2.09E-01 Garden Milk 8.53E-02 E 2.81 NONE NONE Resident 5.51E-02 ESE 1.89 NONE NONE Resident 1.15E-01 Garden SE 3.36 NONE NONE Resident 7.91E-02 Resident SSE NONE NONE NONE NA S NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.88E-01 WSW 0.75 NONE NONE Resident 1.00E-01 W 0.70 NONE NONE Resident 5.94E-02 WNW 2.67 NONE NONE Resident 1.06E-02 NW 0.93 NONE NONE Resident 3.83E-02 NNW 1.30 NONE NONE Resident 3.25E-02 COMMENTS: Dose calculations were performed using the GASPAR code and 2006 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual dose identified (organ, bone, total body, or skin).PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 55

11. Summary and Conclusions The conclusions are based on a review of the radio assay results and background gamma radiation measurements for the 2007 calendar year. Where possible, the data were compared to pre-operational sample data.All sample results for 2007 are presented in Tables 8.1-8.11 and do not include observations of naturally occurring radionuclides, with the exception of gross beta in air and gross beta in drinking water. Table 11.1 summarizes the ODCM required samples and is in the format required by the NRC BTP on Environmental Monitoring.

1-131 concentrations identified on occasion in the Evaporation Ponds, WRF Influent, WRF Centrifuge sludge, and Reservoirs is the result of offsite sources and appears in the effluent sewage from Phoenix. The levels of 1-131 detected in these locations are consistent with levels identified in previous years.Tritium concentrations identified in surface water onsite have been attributed to PVNGS permitted gaseous effluent releases and secondary plant releases.

These concentrations are consistent with historical values.Natural background radiation levels are consistent with measurements reported in previous Pre-operational and Operational Radiological Environmental annual reports, References 1 and 2.The only measurable impact on the environment in 2007 was the low level tritium discovered in subsurface water onsite in the RCA in 2006. See Section 2.4for specific information.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 56 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 2007 Medium or Lower Limit of All Indicator Location with Highest Annual Mean Control Pathway Type and Total Detection Locations Locations Number of Sampled Number of (LLD) Name Mean (f)a Nonroutine (Unit of Analyses (from Table Mean (f)a Distance and Range Mean (f)a Reported Measurement)

Performed 6.1) Range Direction Range Measurements Direct Radiation TLD -193 NA 23.7 (182/182)

Site #35 30.5 (4/4) 22.4 (8/8) 0 (mrem/std.

qtr.) 17.0-32.3 8 miles 330' 27.2-32.3 17.7 -27.7 Air Particulates Gross Beta- 513 0.010 0.035 (462/462)

Site #15 0.037 (51/51) 0.039 (52/52) 0 (pCi/m 3) 0.016 -0.061 2 miles 550 0.019 -0.061 0.019 -0.069 Gamma Spec.Composite

-40 Cs-134 0.05 <LLD NA <LLD <LLD 0 Cs-137 0.06 <LLD NA <LLD <LLD 0 Air Radioiodine Gamma Spec. -515 (pCi/m 3) 1-131 0.07 <LLD NA <LLD <LLD 0 Broadleaf Gamma Spec. -11 Vegetation 1-131 60 <LLD NA <LLD <LLD 0 (pCi/Kg-wet)

Cs-134 60 <LLD NA <LLD <LLD 0 Cs-137 80 <LLD NA <LLD <LLD 0 Groundwater H-3 -8 2000 <LLD NA <LLD NA 0 (pCi/liter)

Gamma Spec. -8 Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 57 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 2007 Medium or Lower Limit of All Indicator Location with Highest Annual Mean Control Pathway Type and Total Detection Locations Locations Number of Sampled Number of (LLD) Name Mean (f)a Nonroutine (Unit of Analyses (from Table Mean (f)a Distance and Range Mean (f)a Reported Measurement)

Performed 6.1) Range Direction Range Measurements Nb-95 15 <LLD NA <LLD NA 0 Groundwater 1-131 15 <LLD NA <LLD NA 0 (pCi/liter)

Cs-134 15 <LLD NA <LLD NA 0-continued-Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 Gross Beta- 48 4.0 3.8 (22/48) Site #48 4.5(4/12)

NA 0 2.6-5.6 1 mile 2360 3.9-5.6 H-3 -16 2000 <LLD *NA <LLD NA 0 Gamma Spec. -48 Drinking Water Mn-54 15 <LLD NA <LLD NA 0 (pCi/liter)

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 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 58 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 2007 Medium or Lower Limit of All Indicator Location with Highest Annual Mean Control Pathway Type and Total Detection Locations Locations Number of Sampled Number of (LLD) Name Mean (f)a Nonroutine (Unit of Analyses. (from Table Mean (f)a Distance and Range Mean (f)a Reported Measurement)

Performed 6.1) Range Direction Range Measurements Gamma Spec. -8 1-131 1.0 <LLD NA <LLD <LLD 0 Milk Cs-134 15 <LLD NA <LLD <LLD 0 (pCi/liter)

Cs-137 18 <LLD NA <LLD <LLD 0 Ba- 140 60 <LLD NA <LLD <LLD 0 La-140 15 <LLD NA <LLD <LLD 0 Gamma Spec. -36 Mn-54 15 <LLD NA <LLD NA 0 Fe-59 30 <LLD NA <LLD NA 0 Co-58 15 <LLD NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD NA <LLD NA 0 Zr-95 30 <LLD NA <LLD NA 0 Nb-95 15 <LLD NA <LLD NA 0 Surface Water 1-131 15 16(10/36)

Site #60 17(5/12) NA 0 (pCi/liter) 9-23 Onsite 67' 11 -23 Cs-134 15 <LLD NA <LLD NA 0 Cs-137 18 <LLD NA <LLD NA 0 Ba-140 60 <LLD NA <LLD NA 0 La-140 15 <LLD NA <LLD NA 0 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 59 TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Palo Verde Nuclear Generating Station Maricopa County, Arizona Docket Nos. STN 50-528/529/530 Calendar Year 2007 Medium or Lower Limit of Alt Indicator Location with Highest Annual Mean Control Pathway Type and Total Detection Locations Locations Number of Sampled Number of (LLD) Name Mean (f)a Nonroutine (Unit of Analyses (from Table Mean (f)a Distance and Range Mean (f)a Reported Measurement)

Performed 6.1) Range Direction Range Measurements Surface Water H-3 -12 3000 1223 (8/12) Site #63 1398 (4/4) NA 0 (pCi/liter) 749-2323 Onsite 1750 1047-2323--continued-(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 -2007 60

12. References

1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985 2. 1985-2006 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, PVNGS Units 1, 2, and 3 5. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants 6. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants 7. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG-1301)

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2007 61