ML071310137

Palo Verde, Units 1, 2 and 3 - Annual Radiological Environmental Operating Report 2006

ML071310137
Person / Time
Site:	Palo Verde
Issue date:	05/01/2007
From:	Weber T N Arizona Public Service Co
To:	Document Control Desk, NRC/NRR/ADRO
References
102-05694-TNW/CJJ
Download: ML071310137 (64)

Text

A subsidiary of Pinnacle West Capital Corporation Thomas N. Weber Mail Station 7636 Palo Verde Nuclear Department Leader Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-05694-TNW/CJJ May 01, 2007 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 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 2006 In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2006.No commitments are being made to the NRC in this letter. If you have any questions, please contact Daniel G. Marks at (623) 393-6492.Sincerely, TNW/DGM/CJJ/gat Enclosure cc: B. S. Mallett M. T. Markley G. G. Warnick A. V. Godwin A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway fl Comanche Peak E Diablo Canyon 0 Palo Verde fl South Texas Project 0 Wolf Creek NUCLEAR GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2006 (

Reference:

RCTSAI 1643, Legacy Item No. 036843.01)

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TABLE OF CONTENTS 1. IN TR O D U C TIO N ..........................................................................................................................

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

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

3 2.1. 2006 PVNGS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ...............................

3 2.2. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CHANGES FOR 2006 .....................

3 2.3. REMP DEVIATIONS/ABNORMAL EVENTS

SUMMARY

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

4 2.4. SIGNIFICANT INVESTIGATION REGARDING GROUNDWATER PROTECTION

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

4 3. SA M PLE C O LLEC TIO N PR O G R A M ........................................................................................

11 3.1. W ATER .......................................................................................................................................

11 3.2. V EGETATION

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

11 3.3. M ILK ..........................................................................................................................................

11 3.4. A IR .............................................................................................................................................

11 3.5. SLUDGE AND SEDIM ENT .............................................................................................................

12 4. A N A LY TICA L PR O CED U RE S ...............................................................................................

12 4.1. A IR PARTICULATE

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

12 4.2. A IRBORNE R ADIOIODINE

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

12 4.3. M ILK ..........................................................................................................................................

12 4.4. V EGETATION

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

13 4.5. SLUDGE/SEDIM ENT ....................................................................................................................

13 4.6. W ATER .......................................................................................................................................

13 4.7. SOIL ...................................................................

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

14 5. N U CLEA R IN STR U M EN TA TIO N .......................................................................................

14 5.1. G AM M A SPECTROM ETER ........................................................................................................

14 5.2. LIQUID SCINTILLATION SPECTROM ETER .................................................................................

14 5.3. G AS FLOW PROPORTIONAL C OUNTER ....................................................................................

14 6. ISOTOPIC DETECTION LIMITS AND REPORTING CRITERIA .....................................

15 6.1. LOW ER LIM ITS OF D ETECTION ...................................................................................................

15 6.2. D ATA REPORTIN G CRITERIA ...................................................................................................

15 6.3. LLD AND REPORTING CRITERIA O VERVIEW ...........................................................................

16 7. INTERLABORATORY COMPARISON PROGRAM ...........................................................

21 7.1. Q UALITY C ONTROL PROGRAM ...............................................................................................

21 7.2. INTERCOM PARISON RESULTS ..........................................................

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

21 8. DATA INTERPRETATIONS AND CONCLUSIONS

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

24 8.1. A IR PARTICULATES

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

24 8.2. A IRBORNE R ADIOIODINE

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

25 8.3. V EGETATION

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

25 8.4. M ILK ..........................................................................................................................................

25 8.5. D RINKING W ATER ......................................................................................................................

25 8.6. G ROUNDW ATER ..........................................................................................................................

25 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 ii TABLE OF CONTENTS 8.7. SURFACE W ATER .......................................................................................................................

25 8.8. SLUDGE AND SEDIM ENT .............................................................................................................

26 8.9. D ATA TRENDS ............................................................................................................................

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

46 10. LA N D U SE C EN SU S ..................................................................................................................

52 10. 1. INTRODUCTION

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

52 10.2. C ENSUS R ESULTS ....................................................................................................................

52 11. SU M M A RY A N D CO N C LU SIO N S .......................................................................................

54 12. REFEREN CES .............................................................................................................................

59 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 iii LIST OF TABLES TABLE 2.1 SAMPLE COLLECTION LOCATIONS

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

6 TABLE 2.2 SAMPLE COLLECTION SC.-3ED T JLE ..............................................................................

7 TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS ................................

8 TABLE 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (A PRIORI) ..........................

18 TABLE 6.2 ODCM REQUIRED REPORTING LEVELS ..................................................................

19 TABLE 6.3 TYPICAL MDA VALUES ...............................................................................................

20 TABLE 7.1 INTERLABORATORY COMPARISON RESULTS ......................................................

22 TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1 ST -2ND QUARTER ..................................

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

28 TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES

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

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

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

31 TA B LE 8.6 V EG ETA TIO N ......................................................................................................................

32 T A B L E 8.7 M IL K .....................................................................................................................................

33 TABLE 8.8 DRINKING WATER .........................................................................................................

34 TABLE 8.9 GROUNDWATER

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

36 TA BLE 8.10 SU RFA CE W A TER ........................................................................................................

37 TABLE 8.11 SLUDGE/SEDIMENT

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

40 TABLE 9.1 TLD SITE LOCATIONS

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

47 TABLE 9.2 2006 ENVIRONMENTAL TLD RESULTS ....................................................................

49 TABLE 10.1 2006 LAND USE CENSUS .............................................................................................

53 TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

... 56 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 iv LIST OF FIGURES FIGURE 2.1 REMP SAMPLE SITES -MAP (0-10 miles) .............................................................

9 FIGURE 2.2 REMP SAMPLE SITES -MAP (10-35 miles) ...........................................................

10 FIGURE 8.1 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES)

...........

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

C O M PA RE D TO PR E-O P .....................................................................................................................

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

44 FIGURE 8.4 EVAPORATION POND TRITIUM ACTIVITY ......................................................

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

50 FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON

-PRE-OPERATIONAL VS 2006 ........ 51 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 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 2006, 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 -2006 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 2006. 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 18, 1986, and October 25, 1987, respectively.

PVNGS operational findings (historical) are presented in Reference 2.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 2

2. Description of the Monitoring Program APS and vendor organizations performe~d the pre-operational radiological environmental monitoring program, which began in 1979. APS and vendors continued the program into the operational phase.2.1. 2006 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 forty-nine (49) 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 2006> Site #46 (drinking water) was changed from McArthur (NW9) to Wirth (NNW8) in September as the property was sold and access to the sample was no longer available Refer to Table 2.1 for a description of all current sample locations (except TLDs).PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 3 2.3. REMP Deviations/Abnormaal Events Summary During calendar year 2006, there were three (3) deviations/abnormal events with regard to the monitoring program. Refer to Table 2.3 for more detail and any corrective actions taken.* Monthly goat milk samples were obtained as required in May. During the sample analysis, the equipment shutdown.

The samples could not be re-analyzed due to the short half-life of 1- 131." Air samples were invalidated from Site #21 for gross beta and radioiodine the week of 7/3-7/11.* One interlaboratory crosscheck sample, gross beta in water, failed the acceptance criteria.2.4. Significant Investigation Regarding Groundwater Protection 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 seal and wall below the seal were observed to be wet, with a water puddle on the pipe chase floor. Unit 2 placed the 'B' Spray Pond pump into service for a scheduled pump run on February 16. Personnel observed that water accumulation at the penetration increased while the pump was operating.

In response to the observed in-leakage, station management decided to excavate the Unit 2 SP 'B' supply and return lines immediately west of the Essential Pipe Density Tunnel to inspect for leakage. Maintenance excavated lines 2PSPBLO30 and 2PSPBLO25 to look for leaks, but none were found. Additionally, the penetration seal around SPBL030 was removed to look for leaks, none were found, and the area was restored.A subsequent inspection in the Unit 3 Essential Pipe Density Tunnel identified similar leakage at the penetration for the SP 'A' return line (3PSPAL079) and SP 'B' return line (3PSPBLO25) penetration seals. The seals for the return line penetrations were observed to be dripping while the SPA/B pumps were in operation.

The wall below the SP 'A' supply line (3PSPAL068) and SP 'B' supply line (3PSPBLO30) penetration seals showed dampness, but no visible water drops. Maintenance excavated the return line and the supply line to the 4'-4" top of pipe level. The excavation revealed no visible leaks and Maintenance restored the area.Process piping in Unit 3 associated with the Charging system (CH), Liquid Radwaste system (LR) and Fire Protection system (FP) were partially excavated in the area of the pipe chase penetrations.

The elimination of SP system piping leaks left these pipes suspect. No leaks were identified by excavation.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2006 4 In addition to the major excavation detailed above, a test hole, approximately 13 feet deep, was dug in the radiological controlled area yard to determine the extent of condition.

Water was subsequently discovered in the test hole and a sample was obtained in order to characterize the water and identify its source. Initial results from the unit laboratory (March 1, 2006 sample) indicated the presence of tritium. A confirmatory sample was collected and analyzed by the State certified laboratory at Palo Verde that confirmed the presence of .ritium at a concentration of approximately 7.14E-05 [tCi/ml. The Aquifer Protection Permit, Aquifer Quality Limit for tritium is 2.OOE-05 p.Ci/ml. The Palo Verde Environmental Control department notified the Arizona Department of Environmental Quality (ADEQ) of the possibility of a discharge of non-hazardous material that has the potential to cause groundwater limits to be exceeded.

The station also notified the Nuclear Regulatory Commission pursuant to 1OCFR50.72 (b) (2) (xi); specifically of a situation related to the protection of the environment, for which a notification to another government agency has been or will be made. Public meetings with local residents were held to inform the public and answer concerns.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).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 will be routinely sampled for radiological analyses and results will be reported in the PVNGS Annual Radioactive Effluent Release Report (ARERR). This reporting protocol was agreed upon by industry leaders via the NEI Industry Ground Water Protection Voluntary Communication Protocol Interim Guidance Document (June 2006) for non-REMP well samples (with additional direction via a position paper developed during the industry RETS-REMP workshop).

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 5 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 62 M/AA 63 W W = WEEKLY M/AA = MONTHLY AS AVAILABLE Q = QUARTERLY PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 7 TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS Deviation/Abn'ermal Event 1. Monthly goat milk samples were obtained as required in May. During the sample analysis, the equipment shutdown.

The samples could not be re-analyzed due to the short half-life of 1- 131.2. Air sample results from Site #21 for gross beta and radioiodine were invalidated due to pump inoperability the week of 7-11-06.3. One interlaboratory crosscheck sample, gross beta in water, failed the acceptance criteria.Actions taken 1. This event was documented on corrective action document CRDR 2894572 due to the missed sample analysis frequency requirements of the ODCM. The cause of tlhe eq'irnent shutdown was the elevated temperature of the countroom due to the building A/C unit failure.The A/C unit was repaired to correct the condition and no further actions were required.2. The air sample pump was not running when the technician arrived at the sample location, although the ETM had power. The actual sample volume could not be determined.

Equipment was replaced and subsequent samples were valid. No additional actions are necessary.

3. The crosscheck sample was re-analyzed and again failed the acceptance criteria.

CRDR#2975606 was initiated, as part of the Corrective Action Program, due to the failure. Actions in progress include the purchase of a new calibration source and replacement of an EPROM. Corrective actions are not complete at this time.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 8 I FIGURE 2.1.., ..............

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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 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 -2006 11

3.5. Sludge

and Sediment Sludge samples were obtained weekly from the WRF waste centrifuge (whenever the plant was operational) and analyzed for gamma emitting radionuclides.

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 -2006 12

4.4. Vegetation

4.4.1. Gamma

Spectroscopy The sample is pureed in a food processor, placed in a one liter plastic mar;nelli 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 with 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 -2006 13

4.6.3. Gross

Beta A 200-250 milliliter sample 4. placed in a beaker. Five (5) milliliters of concentrated nitric (HN0 3) ac'd 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 -2006 14

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 2a counting error. All results that are less than the MDA are reported as less than values at the associated MDA. For example, if the MDA is 12 pCi/liter, the value is reported as <12.Typical MDA values are presented in Table 6.3.Occasionally, the PVNGS ODCM a priori LLDs may not be achieved as a result of: 0 0 0 0 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 -2006 15 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 -2006 16 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 -2006 17 Table 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (a priori)ATRBORNE 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 -2006 18 Table 6.2 ODCM REQUIRED REPORTING LEVELS AIRBORNE ANALYSIS/

WATER PARTICULATE MILK VEGETATION NUCLIDE (pCi/liter) or GAS (pCijm 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 -2006 19 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 3 0.003 H-3 273 Mn-54 12 Fe-59 19 Co-58 11 Co-60 12 Zn-65 26 Zr-95 17 Nb-95 11 1-131 8 a 1 0.05 50 Cs-134 10 1 0.02 b 55 Cs-137 13 1 0.02 b 60 Ba-140 38 3 La-140 12 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 -2006 20

7. Interlaboratory Comparison Pr-ggram 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 2006, APS analyzed the following sample types under the interlaboratory comparison program;" Beta/Gamma/

in Air Filter" 1-131 in Air* Beta in Water" Gamma in Water* Tritium in Water" Gamma in milk 7.2. Intercomparison Results APS participates in a crosscheck program using vendor supplied blind radionuclide samples. Results for the interlaboratory comparison program are presented in Table 7.1.One crosscheck result in 2006, gross beta in water, did not pass the established acceptance criteria.

This failure was documented in the PVNGS Corrective Action Program via CRDR #2975606.

See Table 2.3 for additional information.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 21 TABLE 7.1 INTERLABORATORY COMPARISON RESULTS 1 Sample Analysis Nuclide Known PVNGS sigma Resolution Ratio Accept/Reject Type Type Value Value Error *Mixed Water Gamma 1-131 75.7 82 11 7 1.08 Accept E5062-111 Ce-141 57 66 9 7 1.16 Accept Cr-51 68.1 58 33 2 0.85 Accept Cs-134 98.3 86 11 8 0.87 Accept Cs-137 94.8 97 12 8 1.02 Accept Co-58 52.3 53 8 7 1.01 Accept Mn-54 107 110 14 8 1.03 Accept Fe-59 37.6 31 11 3 0.82 Accept Zn-65 132 139 19 7 1.05 Accept Co-60 103 106 12 9 1.03 Accept Tritium H-3 5960 5130 233 22 0.86 Accept E5060-111 Gross Beta gbeta 198 225 5.5 41 1.14 Accept E5061-111 Air Gross Beta gbeta 65.1 78.4 1.5 52 1.20 Accept E5063-111 Iodine Cart 1-131 68.1 67 8 8 0.98 Accept E5064-111 Mixed Gamma Ce-141 59.7 72 8 9 1.21 Accept E5065-111 Cr-51 71.4 81 19 4 1.13 Accept Cs-134 103 84 10 8 0.82 Accept Cs-137 99.4 111 13 9 1.12 Accept Co-58 54.9 63 9 7 1.15 Accept Mn-54 113 129 17 8 1.14 Accept Fe-59 39.5 48 8 6 1.22 Accept Zn-65 139 174 21 8 1.25 Accept Co-60 108 116 13 9 1.07 Accept Mixed Milk Gamma 1-131 54.6 50 3 17 0.92 Accept E5236-111 Ce-141 53.8 54 3 18 1.00 Accept Cr-51 77.2 80 9 9 1.04 Accept Cs-134 31.0 28 2 14 0.90 Accept Cs-137 50.3 51 3 17 1.01 Accept Co-58 16.6 16 2 8 0.96 Accept Mn-54 23.2 26 2 13 1.12 Accept Fe-59 15.2 13 2 7 0.86 Accept Zn-65 34.1 38 3 13 1.11 Accept Co-60 59.4 59 3 20 0.99 Accept PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 22 TABLE 7.1 INTERLABORATORY COMPARISON RESULTS Sample [Analysis Nuclide Known PVNGS sigma ResolutionAccept/Reject Type ~ Type Value Value Error Mixed Water Gamma 1-131 70.2 75 7 11 1.07 Accept E5230-111 Ce-141 286 283 15 19 0.99 Accept Cr-51 421 397 38 10 0.94 Accept Cs-134 143 132 8 17 0.92 Accept Cs-137 230 229 13 18 1.0 Accept Co-58 81.4 84 7 12 1.03 Accept Mn-54 108 111 14 8 1.03 Accept Fe-59 77.4 90 11 8 1.16 Accept Zn-65 159 174 14 12 1.09 Accept Co-60 273 282 15 19 1.03 Accept 1.48E0 1.20E0 Tritium H-3 4 4 154 78 0.81 Accept E5234-111 Gross Beta gbeta 249 340 3.5 97 1.37 REJECT E5229-111 gbeta 249 321 3.5 92 1.29 REJECT Air Gross Beta gbeta 86.6 111 2.4 46 1.28 Accept E5231-111 Iodine Cart 1-131 86.2 89 7 13 1.03 Accept E5232-111 Mixed Gamma Ce-141 226 224 11 20 1.09 Accept E5233-111 Cr-51 332 330 29 11 1.08 Accept Cs-134 113 103 7 15 0.85 Accept Cs-137 182 188 13 15 1.13 Accept Co-58 64.3 70 6 12 1.10 Accept Mn-54 85.1 97 7 14 1.19 Accept Fe-59 61.1 73 8 9 1.28 Accept Zn-65 126 147 12 12 1.18 Accept Co-60 215 224 12 19 1.10 Accept* calculated from PVNGS value/1 sigma error value Acceptance Criteria 1 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" PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 23

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

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

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

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

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

The acceptance of data is dependent upon the results of quality control samples and is part of the data review process for all analytical results.The "plus or minus value" reported with each analytical result represents the counting error associated with the result and gives the 95% confidence (2a) interval around the data.Most samples contain radioactivity associated with natural background/cosmic radioactivity (e.g. K-40, Th-234, 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 2006 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 2006 was the low level tritium discovered in subsurface water onsite in the RCA. 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 0.010 to 0.070 pCi/m 3.The associated counting error ranged from 0.001 to 0.004 pCi/m 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 as 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 -2006 24

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 6.2 pCi/liter (Gavette 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 Reservoir and Evaporation Ponds were analyzed for tritium and gamma emitting radionuclides.

The Reservoir contains processed sewage water from the City of Phoenix and is approximately 80 acres in size. A 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. Results are presented in Table 8.10. 1-131 was observed in Evaporation Pond # 2 in one (1) monthly composite sample (15 pCi/liter) and six (6) of the Reservoir monthly composite samples (7 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 2142 pCi/liter and the highest concentration in Evaporation Pond #2 was also 2142 pCi/liter.

Tritium was not identified in the PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 25 Reservoir.

The tritium identified in the Evaporation Ponds has been attributed to plant gaseous effluent releases and secondary plant liquid releases.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 96 pCi/liter (week of Dec. 19th). None of the samples analyzed indicated the presence of tritium.Table 8.10 also presents gamma spectroscopy and tritium- meastuements 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 five (5) samples taken in 2006.8.8. 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-one (51) samples ranging from 351 to 2460 pCi/kg.In-Ill was also identified in the sludge in twelve (12) samples. The highest concentration was 181 pCi/kg. It was previously established that In-111 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 ten (10) Evaporation Pond sediment samples indicated all gamma emitting radionuclides to be <MDA. Sample results can be found in Table 8.11.8.8.3. Cooling Tower sludge Sludge originating from the Unit 1 and Unit 3 Cooling Towers and/or Circulating Water canals was disposed of in the WRF sludge landfill during 2006. Sample results can be found in Table 8.11.8.9. Data Trends Figures 8.1-8.5 present data in graphical format. Historical data are displayed for comparison where practical.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 26 TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1st -2nd QUARTER ODCM required samples denoted by *units are pCi/m 3 Llst Quarter (control)START STOP Week # DATE DATE Site Site Site Site Site Site Site 4 6A* 7A 14A* 15* 17A 21 Site 29*Site Site 35 40* Mean RSD (%)1 2 3 4 5 6 7 8 9 10 11 12 13 27-Dec-05 3-Jan-06 10-Jan-06 17-Jan-06 24-Jan-06 3 1-Jan-06 7-Feb-06 14-Feb-06 21-Feb-06 28-Feb-06 7-Mar-06 14-Mar-06 21-Mar-06 3-Jan-06 0.036 10-Jan-06 0.031 17-Jan-06 0.039 24-Jan-06 0.024 31-Jan-06 0.043 7-Feb-06 0.030 14-Feb-06 0.033 21-Feb-06 0.025 28-Feb-06 0.047 7-Mar-06 0.027 14-Mar-06 0.016 21-Mar-06 0.021 28-Mar-06 0.024 0.031 0.029 0.039 0.026 0.045 0.034 0.039 0.024 0.049 0.029 0.012 0.019 0.027 0.030 0.027 0.028 0.030 0.029 0.026 0.026 0.024 0.023 0.023 0.035 0.034 0.033 0.034 0.036 0.022 0.026 0.023 0.024 0.020 0.044 0.042 0.044 0.040 0.042 0.029 0.027 0.030 0.031 0.027 0.034 0.031 0.033 0.032 0.029 0.023 0.022 0.022 0.023 0.020 0.048 0.043 0.045 0.041 0.045 0.025 0.024 0.024 0.026 0.025 0.012 0.012 0.011 0.012 0.010 0.019 0.020 0.019 0.019 0.019 0.027 0.025 0.026 0.025 0.026 0.030 0.028 0.029 0.030 0.026 0.036 0.021 0.043 0.028 0.033 0.023 0.042 0.027 0.011 0.020 0.028 0.024 0.031 0.019 0.039 0.027 0.033 0.020 0.043 0.025 0.014 0.018 0.024 0.025 0.026 0.034 0.035 0.018 0.022 0.043 0.043 0.023 0.029 0.031 0.033 0.021 0.022 0.038 0.044 0.024 0.026 0.011 0.012 0.017 0.019 0.025 0.026 8.3 10.1 7.2 12.5 4.3 10.3 8.0 7.3 7.7 6.4 14.3 5.8 5.2 Mean 0.030 0.031 0.029 0.028 0.028 0.028 0.027 0.028 0.027 0.026 0.028 5.6 2nd Quarter START STOP Site Site Site Site Site Site Site DATE DATE 4 6A* 7A 14A* 15* 17A 21 Site Site Site RSD 29* 35 40* Mean M)Week #14 15 16 17 18 19 20 21 22 23 24 25 26 28-Mar-06 4-Apr-06 0.018 4-Apr-06 10-Apr-06 0.017 10-Apr-06 18-Apr-06 0.022 18-Apr-06 25-Apr-06 0.028 25-Apr-06 2-May-06 0.027 2-May-06 9-May-06 0.033 9-May-06 16-May-06 0.047 16-May-06 23-May-06 0.034 23-May-06 30-May-06 0.028 30-May-06 5-Jun-06 0.041 5-Jun-06 13-Jun-06 0.035 13-Jun-06 21-Jun-06 0.040 21-Jun-06 27-Jun-06 0.039 0.018 0.019 0.022 0.029 0.026 0.030 0.046 0.028 0.024 0.039 0.042 0.038 0.039 0.019 0.019 0.018 0.019 0.018 0.018 0.017 0.018 0.016 0.018 0.021 0.021 0.021 0.021 0.019 0.028 0.025 0.027 0.025 0.025 0.026 0.026 0.026 0.028 0.026 0.033 0.030 0.035 0.035 0.029 0.048 0.043 0.048 0.047 0.043 0.034 0.031 0.034 0.032 0.028 0.025 0.023 0.025 0.028 0.024 0.039 0.037 0.041 0.042 0.037 0.038 0.037 0.036 0.036 0.035 0.038 0.034 0.038 0.036 0.032 0.039 0.036 0.038 0.037 0.036 0.017 0.017 0.020 0.027 0.027 0.034 0.046 0.033 0.023 0.041 0.038 0.039 0.036 0.019 0.020 0.021 0.027 0.031 0.036 0.046 0.034 0.025 0.039 0.037 0.035 0.038 0.017 0.018 0.016 0.018 0.019 0.021 0.026 0.027 0.025 0.027 0.035 0.033 0.045 0.046 0.030 0.032 0.026 0.025 0.035 0.039 0.040 0.037 0.033 0.036 0.032 0.037 4.3 7.2 5.1 5.3 6.3 7.6 3.9 7.7 7.1 5.7 5.9 7.5 5.8 Mean 0.031 0.031 0.031 0.029 0.031 0.031 0.028 0.03 1 0.03 1 0.029 0.030 3.6 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 27 TABLE 8.2 PARTICULATE GROSS BETA IN AIR 3rd -4th QUARTER ODCM required samples denoted by *units are pCi/m 3 3rd Quarter ._ _____START STOP Week # DATE DATE (control)Site Site Site Site Site 4 6A* 7A 14A* 15*Site 17A Site Site Site Site 21 29* 35 40* Mean RSD (%)27 28 29 30 31 32 33 34 35 36 37 38 39 27-Jun-06 3-Jul-06 3-Jul-06 11-Jul-06 11-Jul-06 18-Jul-06 18-Jul-06 25-Jul-06 25-Jul-06 1-Aug-06 1-Aug-06 8-Aug-06 8-Aug-06 15-Aug-06 15-Aug-06 22-Aug-06 22-Aug-06 29-Aug-06 29-Aug-06 5-Sep-06 5-Sep-06 12-Sep-06 12-Sep-06 19-Sep-06 19-Sep-06 26-Sep-06 0.042 0.036 0.037 0.037 0.027 0.035 0.030 0.028 0.033 0.029 0.024 0.034 0.031 0.044 0.040 0.036 0.041 0.030 0.037 0.028 0.029 0.033 0.029 0.027 0.038 0.032 0.040 0.039 0.039 0.036 0.036 0.035 0.036 0.034 0.036 0.039 0.037 0.038 0.027 0.027 0.029 0.034 0.033 0.034 0.027 0.028 0.028 0.028 0.026 0.028 0.036 0.033 0.035 0.029 0.026 0.026 0.025 0.023 0.025 0.035 0.031 0.034 0.035 0.031 0.035 0.043 0.037 0.035 0.039 0.029 0.033 0.028 0.026 0.036 0.028 0.025 0.034 0.034 0.032 Invalida 0.035 0.038 0.026 0.032 0.025 0.026 0.034 0.027 0.025 0.032 0.032 0.040 0.041 0.036 0.040 0.037 0.036 0.038 0.037 0.035 0.034 0.034 0.035 0.040 0.038 0.036 0.038 0.028 0.027 0.026 0.028 0.037 0.033 0.034 0.034 0.029 0.028 0.026 0.028 0.029 0.029 0.026 0.028 0.032 0.033 0.032 0.034 0.028 0.030 0.026 0.028 0.026 0.026 0.026 0.025 0.036 0.035 0.034 0.034 0.035 0.033 0.030 0.033 8.8 4.0 2.9 3.9 4.9 4.9 5.1 4.9 4.4 5.3 4.5 5.7 5.7 ean 0.033 0.034 0.033 0.031 0.032 0.033 0.030 0.033 0.033 0.031 0.032 3.6 4th Quarter I START STOP Week # DATE DATE (control)Site Site Site Site Site 4 6A* 7A 14A* 15*Site 17A Site Site Site Site 21 29* 35 40*RSD (%)Mean 40 41 42 43 44 45 46 47 48 49 50 51 52 29-Sep-06 3-Oct-06 10-Oct-06 17-Oct-06 24-Oct-06 31-Oct-06 7-Nov-06 14-Nov-06 21-Nov-06 28-Nov-06 5-Dec-06 12-Dec-06 19-Dec-06 3-Oct-06 10-Oct-06 17-Oct-06 24-Oct-06 31-Oct-06 7-Nov-06 14-Nov-06 21-Nov-06 28-Nov-06 5-Dec-06 12-Dec-06 19-Dec-06 26-Dec-06 0.040 0.034 0.031 0.035 0.034 0.052 0.043 0.047 0.065 0.036 0.049 0.041 0.049 0.045 0.032 0.034 0.037 0.038 0.060 0.045 0.047 0.074 0.035 0.049 0.038 0.049 0.041 0.038 0.038 0.030 0.028 0.031 0.035 0.034 0.034 0.038 0.033 0.037 0.038 0.034 0.035 0.054 0.049 0.054 0.042 0.040 0.041 0.044 0.039 0.042 0.070 0.059 0.065 0.032 0.032 0.031 0.046 0.044 0.046 0.035 0.031 0.034 0.043 0.035 0.040 0.040 0.031 0.032 0.035 0.040 0.053 0.039 0.041 0.065 0.034 0.045 0.033 0.043 0.035 0.031 0.031 0.034 0.033 0.056 0.037 0.041 0.063 0.028 0.041 0.030 0.039 0.039 0.036 0.036 0.031 0.031 0.027 0.033 0.035 0.032 0.035 0.033 0.034 0.039 0.038 0.036 0.059 0.055 0.052 0.041 0.043 0.036 0.045 0.039 0.041 0.070 0.067 0.064 0.032 0.0323 0.030 0.047 0.042 0.038 0.034 0.030 0.030 0.041 0.041 0.042 0.039 0.031 0.033 0.035 0.037 0.054 0.041 0.043 0.066 0.032 0.045 0.034 0.042 7.6 6.4 4.6 4.9 6.6 6.1 6.9 7.0 6.4 7.3 7.9 11.0 10.1 Mean Annual Average 0.043 0.045 0.042 0.038 0.041 0.034 0.035 0.034 0.032 0.033 0.041 0.038 0.042 0.040 0.038 0.033 0.031 0.034 0.033 0.031 0.041 5.3 0.033 4.2 a Pump was off with power to the ETM. Unable to determine sample volume so sample was invalidated.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 28 TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES ODCM required samples denoted by *units are pCi/m 3 (control)QUARTER Site Site Site Site Site Site Site Site Site Site ENDPOINT NUCLIDE 4 6A* 7A 14A* 15* 17A 21 29* 35 40*28-Mar-06 Cs-134 <0.0024 <0.0024 <0.0018 <0.0023 <0.0023 <0.0037 <0.0021 <0.0034 <0.0026 <0.0029 Cs-137 <0.0018 <0.0025 <0.0021 <0.0042 <0.0027 <0.0038 <0.0024 <0.0029 <0.0031 <0.0028 27-Jun-06 Cs-134 <0.0020 <0.0034 <0.0008 <0.0022 <0.0029 <0.0034 <0.0024 <0.0033 <0.0012 <0.0034 Cs-137 <0.0023 <0.0038 <0.0021 <0.0018 <0.0047 <0.0045 <0.0026 <0.0036 <0.0029 <0.0047 26-Sep-06 Cs-134 <0.0017 <0.0039 <0.0023 <0.0018 <0.0033 <0.0022 <0.0036 <0.0019 <0.0038 <0.0019 Cs-137 <0.0021 <0.0011 <0.0054 <0.0027 <0.0039 <0.0027 <0.0042 <0.0025 <0.0049 <0.0025 26-Dec-06 Cs-134 <0.0021 <0.0029 <0.0044 <0.0022 <0.0041 <0.0024 <0.0028 <0.0018 <0.0035 <0.0024 Cs-137 <0.0026 <0.0038 <0.0043 <0.0023 <0.0033 <0.0026 <0.0028 <0.0034 <0.0052 <0.0027 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 29 TABLE 8.4 RADIOIODINE IN AIR 1st -2nd QUARTER RADIOIODINE IN AIR 1st -2nd QUARTER ODCM required samples denoted by *units are pCi/m 3 ,_ _[I ______ 7l stQuarter

.______----(control) 0.07 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*1 2 3 4 5 6 7 8 9 10 11 12 13 27-Dec-05 3-Jan-06 10-Jan-06 17-Jan-06 24-Jan-06 31-Jan-06 7-Feb-06 14-Feb-06 21-Feb-06 28-Feb-06 7-Mar-06 14-Mar-06 21-Mar-06 3-Jan-06 <0.029 <0.060 10-Jan-06

<0.041 <0.070 17-Jan-06

<0.032 <0.049 24-Jan-06

<0.043 <0.043 31-Jan-06

<0.043 <0.034 7-Feb-06 <0.035 <0.028 14-Feb-06

<0.053 <0.035 21-Feb-06

<0.034 <0.033 28-Feb-06

<0.043 <0.038 7-Mar-06 <0.039 <0.038 14-Mar-06

<0.038 <0.052 21-Mar-06

<0.031 <0.033 28-Mar-06

<0.036 <0.044<0.068 <0.012<0.058 <0.031<0.036 <0.045<0.064 <0.034<0.066 <0.036<0.042 <0.035<0.020 <0.060<0.032 <0.034<0.040 <0.028<0.032 <0.033<0.054 <0.036<0.036 <0.036<0.050 <0.037<0.031 <0.049 <0.031 <0.050 <0.037 <0.058<0.046 <0.041 <0.059 <0.035 <0.047 <0.042<0.041 <0.057 <0.028 <0.035 <0.041 <0.052<0.055 <0.049 <0.042 <0.065 <0.045 <0.042<0.060 <0.039 <0.069 <0.020 <0.051 <0.035<0.054 <0.029 <0.012 <0.038 <0.069 <0.039<0.033 <0.050 <0.033 <0.043 <0.032 <0.038<0.033 <0.033 <0.042 <0.065 <0.035 <0.037<0.038 <0.039 <0.070 <0.047 <0.040 <0.068<0.027 <0.042 <0.027 <0.028 <0.040 <0.037<0.066 <0.041 <0.054 <0.047 <0.047 <0.034<0.031 <0.058 <0.046 <0.053 <0.036 <0.036<0.035 <0.069 <0.032 <0.013 <0.039 <0.067[ __ _ _ 2nd Quarter _(control)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 28-Mar-06 4-Apr-06 10-Apr-06 18-Apr-06 25-Apr-06 2-May-06 9-May-06 16-May-06 23-May-06 30-May-06 5-Jun-06 13-Jun-06 21-Jun-06 4-Apr-06 <0.033 <0.043 10-Apr-06

<0.048 <0.061 18-Apr-06

<0.028 <0.026 25-Apr-06

<0.056 <0.031 2-May-06 <0.032 <0.049 9-May-06 <0.042 <0.049 16-May-06

<0.046 <0.048 23-May-06

<0.039 <0.047 30-May-06

<0.038 <0.034 5-Jun-06 <0.043 <0.055 13-Jun-06

<0.032 <0.048 21-Jun-06

<0.064 <0.027 27-Jun-06

<0.042 <0.057<0.049 <0.032<0.055 <0.062<0.033 <0.023<0.034 <0.033<0.033 <0.026<0.041 <0.036<0.053 <0.032<0.034 <0.037<0.021 <0.049<0.069 <0.040<0.052 <0.030<0.037 <0.024<0.058 <0.015<0.059 <0.037 <0.059 <0.036 <0.034 <0.024<0.052 <0.014 <0.055 <0.048 <0.049 <0.068<0.029 <0.039 <0.029 <0.026 <0.036 <0.029<0.043 <0.039 <0.065 <0.033 <0.044 <0.033<0.055 <0.042 <0.042 <0.03 1 <0.043 <0.039<0.060 <0.037 <0.0 12 <0.034 <0.046 <0.032<0.059 <0.026 <0.037 <0.04 1 <0.048 <0.040<0.050 <0.032 <0.054 <0.029 <0.013 <0.035<0.032 <0.060 <0.034 <0.060 <0.051 <0.056<0.044 <0.046 <0.016 <0.042 <0.067 <0.046<0.052 <0.032 <0.043 <0.027 <0.033 <0.032<0.043 <0.023 <0.037 <0.028 <0.042 <0.025<0.057 <0.05 1 <0.050 <0.058 <0.062 <0.058 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 30 TABLE 8.5 RADIOIODINE IN AIR 3rd -4th QUARTER ODCM required samples denoted by *units are pCi/m 3______3rdQuarter

_.__(control) 0.070 START STOP Week # DATE DATE Site 4 Site 6A*Site Site Site 7A 14A* 15*Site 17A Site Site 21 29*Site Site 35 40*27 28 29 30 31 32 33 34 35 36 37 38 39 27-Jun-06 3-Jul-06 <0.068 3-Jul-06 11-Jul-06

<0.022 11-Jul-06 18-Jul-06

<0.038 18-Jul-06 25-Jul-06

<0.059 25-Jul-06 1-Aug-06 <0.040 1-Aug-06 8-Aug-06 <0.032 8-Aug-06 15-Aug-06

<0.025 15-Aug-06 22-Aug-06

<0.038 22-Aug-06 29-Aug-06

<0.032 29-Aug-06 5-Sep-06 <0.027 5-Sep-06 12-Sep-06

<0.053 12-Sep-06 19-Sep-06

<0.029 19-Sep-06 26-Sep-06

<0.041<0.033<0.056<0.033<0.029<0.049<0.033<0.053<0.054<0.058<0.062<0.042<0.067<0.054<0.050 <0.037 <0.069<0.048 <0.035 <0.037<0.043 <0.049 <0.031<0.068 <0.035 <0.059<0.033 <0.060 <0.028<0.049 <0.029 <0.042<0.029 <0.034 <0.062<0.059 <0.033 <0.066<0.064 <0.039 <0.065<0.042 <0.032 <0.064<0.036 <0.069 <0.036<0.053 <0.035 <0.041<0.060 <0.044 <0.050<0.042<0.027<0.057<0.039<0.057<0.030<0.042<0.032<0.031<0.037<0.042<0.031<0.034<0.056 <0.047 <0.063 <0.037 Invalida <0.052 <0.023 <0.048<0.032 <0.050 <0.066 <0.036<0.049 <0.029 <0.056 <0.036<0.030 <0.012 <0.025 <0.060<0.048 <0.031 <0.062 <0.032<0.055 <0.045 <0.067 <0.053<0.051 <0.037 <0.058 <0.031<0.043 <0.028 <0.056 <0.044<0.012 <0.039 <0.059 <0.038<0.029 <0.059 <0.036 <0.030<0.048 <0.033 <0.056 <1.030<0.055 <0.034 <0.057 <0.034 ( ) 4th Quarter 0.0 (control) 0.070 START STOP Week # DATE DATE Site 4 Site 6A*Site Site Site 7A 14A* 15*Site 17A Site Site 21 29*Site Site 35 40*40 41 42 43 44 45 46 47 48 49 50 51 52 26-Sep-06 3-Oct-06 <0.060 3-Oct-06 10-Oct-06

<0.040 10-Oct-06 17-Oct-06

<0.061 17-Oct-06 24-Oct-06

<0.041 24-Oct-06 31-Oct-06

<0.051 31-Oct-06 7-Nov-06 <0.031 7-Nov-06 14-Nov-06

<0.070 14-Nov-06 21-Nov-06

<0.035 21-Nov-06 28-Nov-06

<0.046 28-Nov-06 5-Dec-06 <0.043 5-Dec-06 12-Dec-06

<0.053 12-Dec-06 19-Dec-06

<0.040 19-Dec-06 26-Dec-06

<0.031<0.032 <0.056 <0.033 <0.050<0.028 <0.034 <0.035 <0.058 <0.033<0.048<0.054<0.033<0.028<0.044<0.045<0.066<0.049<0.062<0.049<0.034<0.042<0.054 <0.030 <0.041<0.033 <0.064 <0.027<0.054 <0.024 <0.033<0.049 <0.045 <0.054<0.067 <0.038 <0.043<0.055 <0.039 <0.054<0.061 <0.029 <0.037<0.069 <0.030 <0.040<0.056 <0.033 <0.034<0.035 <0.031 <0.035<0.043 <0.055 <0.039<0.048 <0.031 <0.059<0.035<0.012<0.038<0.041<0.029<0.026<0.034<0.038<0.032<0.033<0.049<0.031<0.042 <0.026 <0.056 <0.029<0.037 <0.033 <0.030 <0.049<0.055 <0.033 <0.050 <0.031<0.058 <0.037 <0.044 <0.037<0.055 <0.029 <0.036 <0.024<0.055 <0.025 <0.064 <0.036<0.013 <0.041 <0.040 <0.042<0.057 <0.031 <0.041 <0.036<0.049 <0.038 <0.035 <3.035<0.034 <0.036 <0.051 <0.037<0.038 <0.056 <0.028 <0.034<0.066 <0.036 <0.042 <0.037 a Pump was off with power to the ETM. Unable to determine sample volume so sample was invalidated.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 31 TABLE 8.6 VEGETATION ODCM required samples denoted by *units are pCi/kg, wet<60<60<80 LOCATION TYPE DATE 1-131 Cs-134 Cs-137 COLLECTED BRANCH RESIDENCE NO SAMPLES AVAILABLE (Site #52)*Green cabbage 19-Jan-06

<51 <57 <41 Red cabbage 19-Jan-06

<44 <53 <71 Savoy cabbage 19-Jan-06

<58 <27 <33 DUNCAN Green cabbage 16-Feb-06

<36 <44 <43 FAMILY Red cabbage 16-Feb-06

<40 <38 <71 FARMS Savoy cabbage 16-Feb-06

<49 <57 <66 (Site #62)* Green cabbage 16-Mar-06

<45 <45 <66 Red cabbage 16-Mar-06

<41 <48 <44 Savoy cabbage 16-Mar-06

<41 <57 <54 Green cabbage 11-Apr-06

<46 <33 <37 Red cabbage 11-Apr-06

<38 <59 <32 Savoy cabbage 11-Apr-06

<37 <57 <63 Red cabbage 11-May-06

<46 <43 <54 Green cabbage 11-May-06

<40 <51 <48 Savoy cabbage 11-May-06

<49 <13 <47 Green cabbage 13-Oct-06

<47 <49 <44 Red cabbage 16-Nov-06

<40 <56 <76 Green cabbage 16-Nov-06

<45 <58 <48 Savoy cabbage 15-Dec-06

<56 <51 <50 Red cabbage 15-Dec-06

<55 <59 <61 Green cabbage 15-Dec-06

<51 <59 <41 MCCOY RESIDENCE NO SAMPLES AVAILABLE (Site #47)*PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 32 TABLE 8.7 MILK ODCM required samples denoted by *units amre pCi/liter SAMPLE LOCATION DATE COLLECTED<1 <15 <18 <60 <15 1-131 Cs-134 Cs-137 Ba-140 La-140 PAINTER GOATS NO SAMPLES AVAILABLE (Site #51)*20-Jan-06

<1 <1 <1 <3 <1 17-Feb-06

<1 <1 <1 <3 <1 17-Mar-06

<1 <1 <1 <3 <1 ADAMS 14-Apr-06

<1 <1 <1 <3 <1 GOATS 16-Jun-06

<1 <1 <1 <3 <1 (Site #53)* 14-Jul-06

<1 <1 <1 <4 <1 11-Aug-06

<1 <1 <1 <3 <1 13-Oct-06

<1 <1 <1 <3 <1 16-Nov-06

<1 <1 <1 <3 <1 15-Dec-06

<1 <1 <1 <3 <1 HERNANDEZ GOATS (Site #54)20-Jan-06 17-Feb-06 17-Mar-06 16-Jun-06 11-Aug-06<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<3<3<3<3<3<1<1<1<1<1 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 33 TABLE 8.8 DRINKING WATER ODCM required samples denoted by *units are pCi/liter<2000 SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 QTRLY <4.0 LOCATION I 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 BERRYMAN RESIDENCE (SITE #48)*31-Jan-06

<14 <11 <27 <11 <30 <12 <23 <12 <12 28-Feb-06

<13 <12 <23 <14 <30 <13 <20 <12 <12 28-Mar-06

<9 <10 <19 <13 <23 <10 <19 <10 <9 25-Apr-06

<11 <11 <24 <15 <25 <12 <21 <11 <11 30-May-06

<7 <11 <17 <12 <24 <11 <19 <9 <9 27-Jun-06

<11 <12 <22 <10 <24 <13 <22 <11 <12 25-Jul-06

<13 <10 <28 <15 <30 <11 <22 <12 <11 29-Aug-06

<9 <10 <19 <9 <26 <10 <15 <10 <10 26-Sep-06

<13 <13 <29 <14 <23 <13 <21 <10 <13 31-Oct-06

<9 <12 <19 <15 <27 <14 <21 <10 <10 28-Nov-06

<13 <15 <26 <14 <28 <14 <24 <13 <11 26-Dec-06

<11 <11 <23 <14 <30 <12 <21 <11 <11<14<14<10<12<9<14<13<10<15<10<13<13<49<45<33<41<35<43<34<33<41<37<48<38 6<13 <3.0<14 <3.3<15 <282 <2.7<13 <2.7<15 <2.9<14 <277 <3.1<14 3.6+/-1.8<15 3.8 ++/-1.8<12 <282 <2.9<15 <3.2<14 3.7 +/- 1.9<14 <273 <3.1<12 4.3 +/- 1.6<10 <2.6<14 <25 4.1 +/- 1.5<12 6.2 +/- 1.6<15 3.2 +/- 1.5<15 <276 2.8 E 1.6<13 4.8 +/- 1.5<15 3.4 +/- 1.4<15 <282 4.5 +/- 1.6<13 <2.6<6 3.8 +/- 1.5<13 <272 2.9 +/- 1.6 GAVETTE RESIDENCE (SITE #55)31-Jan-06

<13 <12 <25 <14 <27 <12 <21 <10 <10 28-Feb-06

<10 <8 <24 <15 <22 <11 <16 <10 <9 28-Mar-06

<13 <13 <29 <10 <30 <14 <20 <11 <11 25-Apr-06

<12 <11 <26 <11 <21 <11 <20 <10 <10 30-May-06

<13 <12 <25 <14 <23 <11 <20 <12 <11 27-Jun-06

<14 <8 <21 <12 <21 <15 <19 <9 <10 25-Jul-06

<12 <12 <25 <13 <30 <13 <20 <11 <10 29-Aug-06

<13 <12 <21 <15 <27 <13 <19 <13 <12 26-Sep-06

<11 <11 <21 <11 <20 <11 <12 <8 <9 31-Oct-06

<14 <13 <29 <15 <30 <14 <25 <13 <13 28-Nov-06

<12 <12 <17 <12 <30 <12 <19 <10 <12 26-Dec-06

<10 <12 <26 <12 <29 <13 <21 <10 <12<11<11<12<10<13<12<10<12<11<17<12<12<41<33<41<38<37<44<41<46<29<42<38<37 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 34 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 I.McARTHUR a/WIRTH RESIDENCE (SITE #46)*31-Jan-06

<12 <13 <25 <13 <24 <12 <22 <11 <9 <13 <42 <13 + 3.2+/- 1.5 28-Feb-06

<12 <12 <27 <15 <28 <13 <24 <14 <12 <15 <46 <13 <2.5 28-Mar-06

<15 <11 <24 <15 <26 <11 <20 <12 <10 <13 <48 <14 <283 2.7+/- 1.4 25-Apr-06

<11 <11 <23 <15 <25 <11 <19 <11 <10 <11 <45 <12 4.1:7i +/- 1.4 23-May-06

<9 <10 <19 <9 <19 <10 <16 <15 <9 <9 <43 <11 3.5 1.5 27-Jun-06

<12 <11 <26 <15 <30 <13 <21 <12 <12 <11 <45 <14 <279 <2.6 25-Jul-06

<11 <13 <29 <10 <28 <14 <23 <12 <13 <15 <46 <13 2.6+/- 1.4 29-Aug-06

<11 <14 <25 <11 <20 <11 <17 <11 <11 <13 <37 <15 4.1+/- 1.5 26-Sep-06

<13 <13 <24 <11 <30 <14 <22 <12 <11 <12 <47 <12 <272 2.8+/- 1.6 31-Oct-06

<15 <12 <28 <12 <24 <13 <25 <12 <12 <13 <41 <15 <2.6 28-Nov-06

<13 <14 <20 <13 <30 <13 <21 <12 <10 <12 <44 <13 E -2.8+/- 1.5 26-Dec-06

<9 <9 <19 <9 <19 <10 <15 <8 <8 <9 <28 <12 <272 3.1 +/- 1.7 CHOWANECb/

SANDOVAL RESIDENCE (SITE #49) *31-Jan-06

<11 <12 <26 <9 <28 <12 <19 <11 <11 <14 <39 <14 2.3+/- 1.5 28-Feb-06

<13 <12 <25 <15 <28 <13 <22 <12 <11 <14 <43 <14 <2.4 28-Mar-06

<11 <12 <24 <14 <26 <11 <18 <11 <11 <13 <44 <14 <284 <2.1 25-Apr-06

<10 <8 <21 <14 <25 <11 <20 <8 <10 <10 <32 <9 5+/- 1.4 30-May-06

<12 <11 <23 <12 <27 <14 <21 <13 <11 <13 <47 <15 <2.2 27-Jun-06

<13 <13 <29 <14 <29 <15 <23 <14 <13 <13 <53 <12 <277 <2.4 25-Jul-06

<10 <12 <26 <11 <27 <12 <20 <11 <11 <12 <40 <15 <2.0 29-Aug-06

<13 <12 <21 <13 <30 <13 <20 <10 <11 <13 <37 <12 <2.0 26-Sep-06

<12 <11 <21 <14 <25 <13 <20 <11 <11 <12 <40 <15 <279 <2.3 31-Oct-06

<12 <10 <21 <12 <21 <13 <16 <11 <11 <11 <41 <15 <2.5 28-Nov-06

<11 <12 <24 <13 <30 <13 <19 <11 <12 <13 <37 <13 <2.2 26-Dec-06

<14 <15 <29 <14 <29 <15 <24 <12 <13 <14 <45 <13 <274 <2.4 a Sample location changed in September due to sale of property.

New sample location is the Wirth residence.

b Property ownership changed to Sandoval in July.PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 35 TABLE 8.9 GROUNDWATER ODCM required samples denoted by *units are pCi/liter SAMPLE 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 31-Jan-06

<12 <12 <25 <15 <28 <14 <19 <12 <11 <12 <40 <13 <273 27ddc 24-Apr-06

<11 <10 <20 <14 <23 <13 <20 <10 <10 <10 <38 <15 <272 (Site #57)* 25-Jul-06

<10 <10 <24 <14 <30 <12 <20 <11 <11 <12 <38 <13 <264 31-Oct-06

<10 <11 <21 <15 <30 <13 <21 <11 <11 <13 <39 <11 <277 WELL 34abb (Site #58)*31-Jan-06

<14 <12 <27 <13 <25 <15 <21 <11 <11 <12 24-Apr-06

<11 <11 <22 <14 <29 <15 <21 <10 <11 <11 25-Jul-06

<11 <10 <22 <14 <30 <14 <19 <11 <10 <12 31-Oct-06

<12 <12 <21 <11 <26 <15 <19 <12 <10 <12<45 <13 <269<38 <13 <282<44 <15 <262<40 <14 <272 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 36 TABLE 8.10 SURFACE WATER ODCM required samples denoted by *units are pCilliter SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 LOCATION IENDPOINT 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 RESERVOIR (Site #60) *31-Jan-06

<9 <9 <19 <9 <18 <9 <17 28-Feb-06

<12 <11 <26 <15 <27 <11 <20 28-Mar-06

<14 <13 <26 <12 <29 <12 <21 25-Apr-06

<12 <11 <21 <13 <22 <10 <20 30-May-06

<13 <10 <24 <11 <30 <11 <17 27-Jun-06

<10 <11 <18 <12 <30 <12 <20 25-Jul-06

<14 <11 <30 <14 <29 <13 <20 29-Aug-06

<13 <11 <18 <9 <25 <11 <22 26-Sep-06

<11 <12 <24 <13 <26 <13 <20 31-Oct-06

<11 <14 <26 <12 <29 <14 <23 28-Nov-06

<15 <10 <27 <10 <27 <11 <23 26-Dec-06

<11 <9 <22 <15 <26 <13 <16 11 +/- 8 20 +/-10<15<11<14 18 +/-11 7 +/-9 8 +/-10<11<15<12 23 +/- 11<9 <10<10 <12<10 <14<11 <10<11 <13<10 <10<12 <14<9 <11<10 <12<11 <13<12 <13<10 <12<29<36<44<35<47<31<48<38<39<44<41<40<12 " :<13 <8<12<15<14 <27 8<14<15<14 <277<15<15<14 <274 4.EVAP POND 1 (Site #59) *31-Jan-06

<13 <12 <25 <13 <30 <10 <23 28-Feb-06

<13 <13 <26 <13 <30 <15 <22 28-Mar-06

<11 <11 <29 <10 <30 <12 <18 25-Apr-06

<10 <11 <22 <13 <30 <10 <19 30-May-06

<11 <13 <25 <15 <30 <10 <17 27-Jun-06

<12 <11 <23 <11 <30 <12 <21 25-Jul-06

<12 <13 <29 <15 <30 <11 <22 29-Aug-06

<12 <14 <28 <15 <30 <14 <21 26-Sep-06

<9 <9 <23 <11 <24 <10 <19 31-Oct-06

<11 <11 <30 <13 <25 <12 <19 28-Nov-06

<15 <12 <26 <13 <30 <11 <24 26-Dec-06

<13 <12 <26 <13 <30 <14 <19<11<13<12<10<10<10<13<13<10<12<13<15<10 <13<10 <14<10 <13<9 <13<10 <13<11 <14<11 <16<12 <14<8 <10<10 <13<12 <15<11 <13<40<51<38<35<37<41<45<44<30<41<41<41<13 <13 " :<11 1912 +/-103<15<11<11 17,87 +/-161<11<13<12 2142 +/- 167<12<14<12 1 168- +/- 18-,7 EVAP POND 2 (Site #63) *31-Jan-06

<12 <11 <20 <15 <29 <12 <19 28-Feb-06

<13 <12 <26 <15 <25 <14 <21 28-Mar-06

<10 <13 <21 <15 <30 <12 <19 25-Apr-06

<12 <11 <24 <12 <30 <13 <22 30-May-06

<13 <13 <28 <12 <29 <13 <24 27-Jun-06

<12 <12 <29 <14 <29 <12 <20 25-Jul-06

<11 <11 <23 <13 <30 <11 <18 29-Aug-06

<11 <10 <26 <10 <30 <10 <18 26-Sep-06

<12 <13 <25 <15 <24 <13 <22 31-Oct-06

<13 <13 <25 <14 <30 <11 <19 28-Nov-06

<11 <8 <23 <11 <29 <10 <16 26-Dec-06

<11 <11 <24 <11 <30 <13 <20<10<11 15 +/- 10<13<14<15<11<14<13<10<9<12<11 <13<10 <15<9 <12<11 <14<12 <14<11 <14<9 <14<12 <15<11 <14<11 <14<8 <12<12 <15<36<36<36<44<42<43<33<40<43<39<31<41<12<13<8 1964 +/- 1069<10<9<14 2142 +/- 173<11<9<11 20)44 +/- 167<11<12 883 +/- 182 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 37 TABLE 8.10 SURFACE WATER ODCM required samples denoted by *units are pCi/liter 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 H-3 SAMPLE LOCATION WRF INFLUENT 3-Jan-06 10-Jan-06 17-Jan-06 24-Jan-06 31 -Jan-06 7-Feb-06 14-Feb-06 21-Feb-06 28-Feb-06 7-Mar-06 14-Mar-06 21-Mar-06 28-Mar-06 4-Apr-06 11-Apr-06 2-May-06 9-May-06 16-May-06 23-May-06 30-May-06 6-Jun-06 13-Jun-06 20-Jun-06 27-Jun-06 4-Jul-06 11-Jul-06 18-Jul-06 25-Jul-06 1-Aug-06 8-Aug-06<13 <13 <23 <15 <24 <13 <22 22 +/-13 <12 <13 <46 <13<9 <11 <24 <13 <23 <11 <18 40 +/-12 <10 <11 <41 <15<11 <10 <17 <11 <17 <11 <17 37 +/-10 <11 <10 <28 <15<11 <12 <17 <11 <22 <11 <17 64 +/-14 <10 <14 <32 <15 <278<10 <10 <17 <15 <19 <11 <17 33 +/-10 <10 <11 <31 <11<13 <14 <28 <13 <30 <15 <25 59 +/-19 <15 <13 <48 <15<14 <15 <22 <13 <29 <14 <20 81 +/-19 <13 <13 <43 <15<12 <12 <24 <14 <26 <14 <18 55 +/-15 <10 <12 <34 <15<12 <11 <17 <11 <22 <13 <17 41+/- 11 <11 <10 <41 <15 <272<12 <13 <30 <12 <29 <10 <18 25 +/- 9 <13 <13 <40 <13<12 <10 <27 <10 <19 <11 <18 18 +/- 9 <11 <10 <39 <15<11 <11 <19 <15 <23 <12 <21 73 +/- 15 <11 <12 <40 <13<13 <12 <27 <12 <30 <13 <25 28 +/- 16 <12 <12 <41 <12 <296<10 <10 <22 <11 <29 <13 <20 19 +/- 9 <10 <14 <38 <15<12 <11 <24 <15 <25 <12 <21 13 +/- 7 <13 <12 <37 <13 <285<14 <14 <25 <13 <24 <11 <16 16:+/- 16 <11 <14 <32 <13<15 <13 <22 <12 <29 <15 <24 25 +/- 10 <13 <15 <42 <14<11 <12 <29 <13 <29 <15 <24 38 +/- 12 <14 <12 <44 <11<13 <11 <26 <14 <26 <13 <24 76 +/- 17 <11 <14 <52 <15<12 <11 <23 <15 <20 <8 <18 30 +/- 10 <12 <10 <35 <15 <277<10 <9 <20 <14 <22 <10 <15 44+/- 14 <9 <10 <38 <15<8 <7 <18 <9 <22 <9 <15 28 +/- 11 <8 <7 <27 <15<15 <13 <26 <8 <26 <14 <23 84 +/- 22 <11 <15 <51 <13<14 <11 <26 <11 <29 <14 <23 35 +/- 13 <11 <14 <41 <11 <282<14 <12 <23 <13 <29 <14 <21 27 +/- 13 <12 <15 <45 <12<10 <12 <28 <15 <30 <14 <21 <13 <11 <13 <43 <13<9 <9 <21 <11 <23 <10 <18 11 +/-6 <9 <9 <33 <15<11 <10 <19 <13 <20 <12 <16 19 +/-10 <8 <12 <39 <13 <272<10 <9 <23 <14 <23 <9 <16 19 +/-9 <10 <11 <33 <13<7 <10 <20 <11 <17 <11 <17 24 +/-8 <10 <11 <31 <15 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 38 TABLE 8.10 SURFACE WATER ODCM required samples denoted by *units are pCi/liter SAMPLE DATE LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 H-3 WRF INFLUENT (continued) 15-Aug-06 22-Aug-06 29-Aug-06 5-Sep-06 12-Sep-06 19-Sep-06 26-Sep-06 3-Oct-06 10-Oct-06 17-Oct-06 24-Oct-06 31-Oct-06 7-Nov-06 14-Nov-06 21-Nov-06 a 28-Nov-06 5-Dec-06 12-Dec-06 19-Dec-06 27-Dec-06<11 <13 <23 <11 <30 <12 <21 37 +/- 15<9 <11 <22 <12 <23 <10 <18 28 +/- 10<13 <11 <21 <11 <30 <11 <22 23+/- 9<11 <10 <22 <12 <23 <12 <21 26 +/-12<14 <14 <26 <13 <27 <14 <24 23 +/-14<11 <11 <19 <11 <29 <9 <17 14+/- 9<15 <15 <29 <15 <29 <14 <23 31 +/-13<14 <12 <23 <14 <29 <13 <20 29+/- 10<14 <12 <29 <12 <29 <13 <24 29+/- 13<10 <11 <20 <14 <30 <11 <19 <11<12 <11 <25 <13 <29 <15 <20 <14<13 <13 <25 <13 <27 <15 <22 38 +/-13<11 <10 <26 <13 <23 <13 <18 12+/- 9<13 <13 <29 <15 <30 <14 <22 32+/- 15<12 <13 <18 <12 <25 <11 <15 55 +/-13<12 <11 <26 <15 <28 <13 <23 20+/- 12<11 <10 <27 <13 <30 <12 <21 22 +/-12<10 <9 <20 <11 <25 <12 <17 15+/- 7<12 <10 <23 <13 <29 <10 <24 96+/- 19<9 <11 <23 <12 <24 <9 <19 35 +/-10<12 <13 <45 <10 I<9 <12 <31 <15<11 <10 <38 <11 <270<11 <14 <41 <13<12 <13 <44 <15<11 <10 <38 <15<13 <12 <50 <14 <293<10 <10 <39 <15<12 <13 <39 <13<12 <12 <35 <10<11 <13 <42 <14<13 <14 <43 <13 <279<11 <14 <40 <15<12 <13 <39 <13<12 <13 <42 <15<11 <14 <46 <13 <280<11 <11 <42 <12<9 <9 <31 <15<11 <10 <34 <6<9 <12 <36 <15 <279 4 SEDIMENT.BASIN #2 1-Aug-06 15-Aug-06 5-Sep-06 12-Sep-06 19-Sep-06<12 <11 <27 <9 <30 <12 <24<13 <14 <30 <12 <27 <12 <17<10 <9 <21 <13 <21 <10 <17<12 <12 <25 <14 <30 <12 <22<13 <12 <24 <12 <30 <12 <23<11<12<9<12<9<11 <11 <41 <15<13 <15 <51 <12<10 <12 <37 <14<12 <14 <40 <13<11 <13 <38 <14<280<289<277<280<269 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 39 TABLE 8.11 SLUDGE/SEDIM.ENT ODCM required samples denoted by *units are pCi/kg, wet SAMPLE LOCATION DATE COLLECTED 1-131 Cs-134 Cs-137 In-lll 4.WRF CENTRIFUGE WASTE SLUDGE 3-Jan-06 10-Jan-06 17-Jan-06 24-Jan-06 31-Jan-06 12-Feb-06 21-Feb-06 28-Feb-06 7-Mar-06 14-Mar-06 21-Mar-06 28-Mar-06 4-Apr-06 11-Apr-06 18-Apr-06 25-Apr-06 2-May-06 9-May-06 16-May-06 23-May-06 30-May-06 6-Jun-06 13-Jun-06 20-Jun-06 27-Jun-06 4-Jul-06 11-Jul-06 18-Jul-06 25-Jul-06 1-Aug-06 8-Aug-06 15-Aug-06 22-Aug-06 29-Aug-06 5-Sep-06 12-Sep-06 19-Sep-06 26-Sep-06 3-Oct-06 10-Oct-06 17-Oct-06 24-Oct-06 31-Oct-06 7-Nov-06 14-Nov-06 21-Nov-06 28-Nov-06 5-Dec-06 12-Dec-06 19-Dec-06 27-Dec-06 794 +/- 115 591 +/- 92 620 +/- 92 679 -97 756+/- 106 978 -122 1704 202 1195 +/- 149 1082 +/- 131 753 -107 546: -89 904 +/- 114 891 +/- 119 762 +/- 107 584+/-h 85 360+/- 70 838 +/- 108 780 +/- 114 879 119 1219 -150 1240+/- 143 977 120 690 -99 818-111 1503 -180 1203 -154 787 +/- 99 481 +/- 76 468 +/- 74 759 +/- 104 882 +/- 118 1035 +/-L 126 1380 +/- 169 1947 +/- 232 1162- 145 921 -120 595 -79 721 +/- 100 1204 -129 1086 +/- 129 351 +/- 62 406 +/- 58 371 +/- 63 467 +/- 73 591 +/- 79 605 +/- 79 1113 +/- 132 847 +/- 114 881 +/- 123 1134 +/- 145 2460 +/- 269<25<28<24<29<27<22<23<28<17<28<30<22<34<30<33<20<25<23<11<18<23<21<20<20<31<22<25<22<27<21<19<21<31<19<21<28<17<26<22<23<24<21<27<21<21<26<19<20<24<29<23<8<40<30<33<30<33<19<28<21<31<32<24<41<34<28<39<17<40<19<67<11<24<25<17<19<13<24<32<19<23<25<28<28<25<30<28<24<24<25<27<27<15<28<26<17<29<30<20<27<25<19 35 +/- 27 59 +/- 31 81 +/--27 27 +/- 21 27 +/- 35 35 +/- 31 22 +/- 18 78 +/- 38 62 +/- 22 181 +/-42 64 +/- 24 94 +/- 40 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 40 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 40 TABLE 8.11 SLUDGE/SEDIMENT ODCM required samples denoted by *Units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED Cs-134 Cs-137 (N) 7-Dec-06 <13 <18 (E) 7-Dec-06 <15 <17 EVAP POND 1 (S) 7-Dec-06 <14 <18 (W) 7-Dec-06 <13 <18 (C) 7-Dec-06 <13 <18 EVAP POND (N)(E)2 (S)(W)(C)7-Dec-06 7-Dec-06 7-Dec-06 7-Dec-06 7-Dec-06<15<13<12<15<13<17<15<18<17<17 COOLING TOWER SLUDGE UNIT APPROXIMATE ISOTOPE ACTIVITY RANGE SAMPLE TYPE FRACTION OF SAMPLES CYCLE VOLUME (yd 3) (uCi/ml) ABOVE MDA U1R12 453 Co-60 Cs-137<MDA to 8.25E-08<MDA to 6.16E-08 tower/canal sludge 4 of 32 8 of 32 U3R12 276 Co-60 2.95E-09 to 6.8 1E-07 tower/canal sludge 32 of 32 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 41 FIGURE 8.1 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES)Gross Beta in Air 1997-2006 1.000 0.100 u 0.010 0.001 00 CUCd C)0d-1 9 r.cd 0 C.)C)0n 0 C.)C)0 C.)C)'C 0 C)6.)PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 42 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) 1997 1998 1999 2000-- 2001 2002--2003--- 2004 2005---- 2006 0.100 T 0.090 +0.080 +0.070 .0.060 +U: 0.050 +0.040 0.030 0.020 0.010 0.000 I I I I I I a)<o¢/]SapeLcto El e'a a)1 an a)0 a)cj~Sample Location PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 43 FIGURE 8.3 GROSS BETA IN DRINKING WATER 10--McArthur/Wirth (site #46)-Gavette (site #55)Berryman (site #48)Chowanec/Sandoval (site #49)C., 0.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 -2006 44 FIGURE 8.4 EVAPORATION POND TRITIUM ACTIVITY 5000 4000-EVAP POND 1----EVAP POND 2 3000Evap P ondlI empty Evap Pond 2 empty 1000 ve 0 ,, ý C r- r- t- 00 00 00 C7, @. CN 0Z 0Z 0C) -r en 'I V) 1 r, 00 ON 0D en 'IT 3jn \o0 00 00 00 00 00000000000 ,Q 0O\O O0,O O 00000000 I I I I II II I , I I 1 1 1 , 1 I 6 aN I- C7, PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 45

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.! and 2.2 and are described in Table 9.1. TLD results for 2006 are presented in Table 9.2. Historical environmental gamma radiation results for 1985 through 2006 are presented in graphical form on Figure 9.1 (excluding transit control TLD #45).Figure 9.2 depicts the environmental TLD results from 2006 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 -2006 46 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 ESE11 SSE31 SE7 SSE4 S5 SE5 ESE5 E5 N1 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 Old US 80 and Arlington School Rd Southern Pacific Pipeline Rd.Southern Pacific Pipeline Rd.355th Ave. and Elliot Rd.3 3 9 th 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.363rd Ave. and Van Buren St.3 5 5 th Ave. and Buckeye Rd.3 4 3 rd Ave. N of Broadway Rd.Wintersburg Arlington School Ruth Fisher School PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 47 TABLE 9.1 TLD SITE LOCATIONS (distances and directions are relative to Unit 2 in milesI TLD SITE 44*45**46 47 48 49 50 LOCATION ENE35 Onsite ENE30 E35 E24 ENE 11 WNW5 LOCATION DESCRIPTION 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 -2006 48 TABLE 9.2 2006 ENVIRONMENTAL TLD RESULTS Units are rnrem/std g .r TLD Site # 1st Quarter 2nd Quarter 3-rd Quarter 4th Quarter Average 1 25.5 24.2 21.4 23.8 23.7 2 22.6 21.3 18.0 20.8 20.7 3 24.2 22.5 17.4 20.5 21.2 4 23.4 21.6 18.8 20.2 21.0 5 22.3 22.6 18.8 19.7 20.9 6 (control) 27.2 26.9 21.7 24.9 25.2 7 26.3 24.3 20.6 23.3 23.6 8 24.2 23.7 18.7 22.4 22.3 9 29.8 24.6 21.2 24.3 25.0 10 25.0 22.6 19.3 22.6 22.4 11 26.5 23.5. 19.7 23.7 23.4 12 24.2 22.5 18.3 21.5 21.6 13 25.8 25.1 21.3 23.7 24.0 14 25.8 22.8 19.1 21.9 22.4 15 24.5 22.6 19.8 21.7 22.2 16 23.3 21.9 18.6 20.4 21.1 17 26.0 24.1 19.4 23.6 23.3 18 25.2 22.7 19.0 21.9 22.2 19 26.5 24.8 20.6 23.7 23.9 20 25.7 23.5 19.4 23.2 23.0 21 27.4 25.2 21.4 24.3 24.6 22 27.9 27.8 21.5 25.3 25.6 23 23.7 21.7 18.5 22.4 21.6 24 24.3 20.3 18.4 20.3 20.8 25 25.3 22.4 18.5 21.5 21.9 26 29.0 26.8 23.3 25.6 26.2 27 30.1 27.5 22.1 25.4 26.3 28 27.9 26.6 21.3 24.0 25.0 29 27.1 23.9 19.2 23.5 23.4 30 27.7 25.2 21.8 24.8 24.9 31 25.1 22.9 19.1 21.0 22.0 32 26.7 25.0 20.3 23.3 23.8 33 27.9 26.6 21.6 23.2 24.8 34 30.2 26.5 23.5 25.1 26.3 35 missing 29.1 26.1 28.5 27.9 36 28.0 25.6 20.9 23.0 24.4 37 26.0 22.3 19.1 21.1 22.1 38 29.8 27.0 22.9 26.1 26.5 39 26.0 24.3 20.3 22.4 23.3 40 27.2 24.9 20.1 22.5 23.7 41 25.4 23.1 20.0 20.9 22.4 42 32.8 30.7 25.3 27.6 29.1 44 (control) 21.5 19.2 16.8 19.4 19.2 45 (transit control) 6.2 5.6 4.3 4.7 5.2 46 28.6 26.3 21.9 23.3 25.0 47 24.8 23.3 19.2 21.1 22.1 48 26.7 24.7 20.0 24.0 23.9 49 24.0 22.4 18.8 20.5 21.4 50 21.0 18.8 16.5 23.4 19.9 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 49 FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES 30.0 28.0 26.024.0 22.0 20.0 18.0___ mR/std qtr BASELINE---- 10 YEAR MEAN tn No r 00 cl 0= " m Vf) %o r 00 01, 0) en V)00 00 00 00 00 O \ O. O ~ O ~ O \ O co I* c* Id 1 1 1 1 1 Id m m w m m m l 0

• 0 0 a s c PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 50 FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON

-PRE-OPERATIONAL VS 2006 I T 1-%35 .,vnllLr O I ..30~25 20 S15--W Pre-op (1984-1985) 10 6 2006 Average 5 1 3 5 7 9 11 13 15 17 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 TLDs #46-50 are not included since they were not included in the pre-op monitoring program PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 51

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 2006.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 0.158 mrem.Milk Animal There were no changes in nearest milk animal (goat) status. Dose calculations indicated the highest dose to be 0.327 mrem.Vegetable Gardens There were three (3) changes in nearest garden status (two former gardens are no longer there, one new garden was identified).

Dose calculations indicated the highest dose to be 0.251 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 -2006 52 TABLE 10.1 2006 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 2005 N 1.55 3.10 NONE Resident 4.50E-02 Garden Garden 1.23E-01 NNE 1.52 NONE 2.05 Resident 8.OOE-02 Garden Milk 3.27E-01 NE 2.16 NONE 3.91 Resident !.12E-01 Milk 2.99E-01 ENE 2.44 NONE 4.84 Resident 6.58E-02 Resident Milk 1.17E-01 Garden E 2.81 NONE NONE Resident 6.75E-02 ESE 1.89 3.85 NONE Resident 1.35E-01 Resident Garden 2.51E-01 SE 4.10 NONE NONE Resident 8.59E-02 SSE NONE NONE NONE NA S NONE NONE NONE NA SSW NONE NONE NONE NA SW 1.39 NONE NONE Resident 1.58E-01 WSW 0.75 NONE NONE Resident 1.28E-01 W 0.70 NONE NONE Resident 9.54E-02 WNW 2.67 NONE NONE Resident 2.31 E-02 NW 0.93 NONE NONE Resident 7.OOE-02 NNW 1.30 NONE NONE Resident 4.81E-02 COMMENTS: Dose calculations were performed using the GASPAR code and 2005 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 -2006 53

11. Summary and Conclusions The conclusions are based on a review of the radio assay results and background gamma radiation measurements for the 2006 calendar year. Where possible, the data were compared to pre-operational sample data.All sample results for 2006 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 Reservoir 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 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 2006 was the low level tritium discovered in subsurface water onsite in the RCA. See Section 2.4for specific information.

PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 54 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 2006 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 -195 NA 23.4 (183/183)

Site #42 29.1 (4/4) 20.0 (8/8) 0 (mrem/std.

qtr.) 16.5-32.8 8 miles 00 25.3 -32.8 16.8 -27.2 Air Particulates Gross Beta- 519 0.010 0.033 (467/467)

Site #4 0.034 (52/52) 0.035 (52/52) 0 (pCi/m 3) 0.010 -0.070 16 miles 900 0.016 -0.065 0.012 -0.074 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. -519 (pCi/m 3) 1-131 0.07 <LLD NA <LLD <LLD C Broadleaf Gamma Spec. -21 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 -2006 55 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 2006 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)' Reported Measurement)

Performed 6.1) Range Direction Range Measuxements 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 3.3 (24/48) Site #55 4.0 (10/12) NA 0 2.3 -6.2 3 miles 2200 2.8 -6.2 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 -2006 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 2006 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)' Distance and Range Mean (f)a Reported Measurement)

Performed 6.1) Range Direction Range Measurements Gamma Spec. -15 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 15 (7/36) Site #60 15 (6/12) NA 0 (pCi/liter) 7-23 Onsite 67' 7-23 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 -2006 57 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 2006 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)' 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 (pCi/liter)-continued-H-3 -12 3000 1748 (8/12)883-2142 Site #59 Onsite 1800 1752 (4/4)1168-2142 NA 0 (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 -2006 58

12. References

1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985 2. 1985-2005 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 4.8, Environmental Technical Specifications for Nuclear Power Plants 6. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2006 59