ML071420094

Annual Radiological Environmental Operating Report for 2006

ML071420094
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/14/2007
From:	James D Entergy Operations
To:	Document Control Desk, NRC/NRR/ADRO
References
OCAN050702
Download: ML071420094 (50)

Text

Entergy Operations, Inc.

Entergy 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing 0CAN050702 May 14, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Annual Radiological Environmental Operating Report for 2006 Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

Dear Sir or Madam:

Arkansas Nuclear One (ANO), Units I and 2, Technical Specifications 5.6.2 and 6.6.2, respectively, require the submittal of an annual radiological environmental operating report for the previous year by May 15 of each year. Attached is the annual radiological environmental operating report for ANO for the year 2006. The radionuclides detected by the radiological environmental monitoring program during 2006 were significantly below regulatory limits; therefore, ANO plant operations during 2006 had no harmful effects nor resulted in any irreversible damage to the environment. This report fulfills the reporting requirements referenced above. Should you have any questions regarding this submittal, please contact Richard Scheide at (479) 858-4618.

This submittal contains no commitments.

Sincerely, Dale E. James Manager, Licensing DEJ/rhs Attachment

0CAN050702 Page 2 cc: Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U.S. Nuclear Regulatory Commission Attn: Ms. Farideh Saba Mail Stop 0-8 B1 Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission Attn: Mr. Alan Wang Mail Stop 0-7 D1 Washington, DC 20555-0001

ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2006 I

TABLE OF CONTENTS

SUMMARY

6

1.0 INTRODUCTION

10 1.1 Radiological Environmental Monitoring Program 10 1.2 Pathways Monitored 10 1.3 Land Use Census 10 2.0 INTERPRETATION AND TRENDS OF RESULTS 20 2.1 Air Particulate and Radioiodine Sample Results 20 2.2 Thermoluminescent Dosimetry Sample Results 20 2.3 Water Sample Results 21 2.4 Sediment Sample Results 22 2.5 Milk Sample Results 23 2.6 Fish Sample Results 23 2.7 Food Product Sample Results 23 2.8 Land Use Census Results 23 2.9 Interlaboratory Comparison Results 23 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

25 3.1 2006 Program Results Summary 25 2

LIST OF TABLES TABLE 1.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM 12 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

26 3

LIST OF FIGURES FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD 18 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 19 FIGURE 2-1 TLD RADIATION DOSE 24 4

LIST OF ATTACHMENTS ATTACHMENT 1 2006 RADIOLOGICAL MONITORING REPORT

SUMMARY

OF MONITORING RESULTS 30 ATTACHMENT 2 SEDIMENT DOSE CALCULATIONS 47 5

Summary The Annual Radiological Environmental Operating Report presents data obtained through analyses of environmental samples collected for Arkansas Nuclear One's (ANO's)

Radiological Environmental Monitoring Program (REMP) for the period January 1, 2006 through December 31, 2006. This report fulfills the requirements of ANO Unit 1 Technical Specification 5.6.2 and Unit 2 Technical Specification 6.9.4.

During 2006 as in previous years, ANO detected radionuclides attributable to plant operations at the discharge location (Station 8) where previously monitored liquid radioactive effluent from the plant is periodically discharged in accordance with the regulatory criteria established in the Offsite Dose Calculation Manual (ODCM). ANO personnel routinely monitor results from this area in order to note any trends. The review of results from this area indicates the following:

• Tritium levels in the surface water media continue to be below regulatory reporting limits and are consistent with concentrations that would typically be seen at this location as discussed in Section 2.3 of this AREOR

• Cesium-137 levels in the sediment media are not demonstrating any consistent increase in comparison to previous years. Review indicates that results for 2006 were within the range of previous operational levels as discussed in Section 2.4 of this AREOR.

Gross beta concentrations at the Station 14 (City of Russellville) indicator drinking water location continue to remain consistent with previous operational measurements and similar to the levels detected at the Station 57 (City of Danville) control drinking water location.

Radiological Environmental Monitoring Program ANO established the REMP prior to the station becoming operational (1974) to provide data on background radiation and radioactivity normally present in the area. ANO has continued to monitor the environment by sampling air, water, sediment, fish and food products, as well as measuring radiation directly. ANO also samples milk if milk-producing animals are present commercially within five miles of the plant.

The REMP includes sampling indicator and control locations within an approximately 20-mile radius of the plant. The REMP utilizes indicator locations near the site to show any increases or buildup of radioactivity that might occur due to station operation, and control locations farther away from the site to indicate the presence of only naturally occurring radioactivity. ANO personnel compare indicator results with control and preoperational results to assess any impact ANO operation might have had on the surrounding environment.

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In 2006, ANO personnel collected environmental samples for radiological analysis. They compared results of indicator locations with control locations and previous studies and concluded that overall no significant relationship exists between ANO operation and effect on the plant environs. The review of 2006 data, in many cases, showed undetectable radiation levels in the environment and in all instances, no definable trends related to significant pathways associated with ANO.

Harmful Effects or Irreversible Damage The REMP monitoring did not detect any harmful effects or evidence of irreversible damage in 2006. Therefore, no analysis or planned course of action to alleviate problems was necessary.

Reporting Levels ANO's review indicates that no samples equaled or exceeded reporting levels for radioactivity concentration in environmental samples due to ANO effluents, as outlined in Units 1 and 2 Offsite Dose Calculation Manual (ODCM) Table 2.6-3, when averaged over any calendar quarter. Therefore, 2006 results did not trigger any Radiological Monitoring Program Special Reports.

Radioactivity Not Attributable to ANO The ANO REMP has detected radioactivity attributable to other sources. These include the 25th Chinese nuclear test explosion in 1980 and the radioactivity plume release due to reactor core degradation at the Chernobyl Nuclear Power Plant in 1986. Prior to 1981, the ANO REMP detected radioactivity resulting from nuclear weapons testing, with Cesium-137 continuing to be periodically detected.

Comparison to Federal and State Programs ANO personnel compared REMP data to state monitoring programs as results became available. Historically, the programs used for comparison have included the U.S. Nuclear Regulatory Commission (NRC) TLD Direct Radiation Monitoring Network and the Arkansas Department of Health (ADH).

The NRC TLD Network Program was discontinued in 1998. Historically these results have compared to those from the ANO REMP. ANO TLD results continue to remain similar to the historical average and continue to verify that plant operation is not affecting the ambient radiation levels in the environment.

The ADH and the ANO REMP entail similar radiological environmental monitoring program requirements. These programs include collecting air samples and splitting or sharing sample media such as water, sediment and fish. Both programs have obtained similar results over previous years. A comparison of the 2006 results will be made when available.

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Sample Deviations

+ Milk The REMP did not include milk sampling within five miles (8 kIn) of ANO in 2006 due to unavailability. ANO Units 1 and 2 ODCM require collection of milk samples if available commercially within 8 km (5 miles) of the plant. ANO personnel collected vegetation samples to monitor the ingestion pathway, as specified in the ODCM, because of milk unavailability.

• Required Lower Limit of Detection (LLD) Values LLDs during this reporting period were within the acceptable limits required by Table 2.6-2 of the ANO Units 1 and 2 ODCM.

• Air Samples Listed below are air sampler deviations that occurred during 2006 due to electrical power outages and equipment failure. These deviations did not result in the exceedance of the LLD values specified in the ODCM. As described in footnote (a) to ANO Units 1 and 2 ODCM Table 2.6-1, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons.

Station Sampling Period Comment 1 03/07/06 - 03/21/06 Pump found not running. Out of service pump was replaced with a new pump.

1 04/18/06 - 05/02/06 Air sample station power isolated due to maintenance on meteorological tower.

2 04/18/06 - 05/02/06 Loss of electrical power.

1 05/02/06 - 05/16/06 Volume totalizer failed. Volume totalizer was replaced.

2 10/17/06 - 10/31/06 Pump found not running. Out of service pump was replaced with a new pump.

• Missed Samples One first quarter ThD (Station 127) was missed during 2006 due to vandalism. This loss was an isolated instance that did not recur during the year and was replaced with a new TLD by ANO personnel once discovered. The recovery rate for TLDs during 2006 was 99% (95 of 96).

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• Surface Water Electrical power to the outlet that powers the composite surface water sampler at Station 8 was temporarily lost during the third quarter sampling period. Daily grab samples were taken as a compensatory measure until electrical power was restored to the composite sampler. This deviation did not result in a missed sample and as described in footnote (a) to ANO Units 1 and 2 ODCM Table 2.6-1, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons.

• Unavailable Results ANO received analytical results in adequate time for inclusion in this report. In addition, ANO's review identified no missing results.

Program Modifications ANO made no modifications to the REMP during 2006.

Attachments ' contains results of air, TLD, water, sediment, fish, and food product samples collected in 2006. TLDs were analyzed by Waterford-3 Dosimetry. All remaining samples were analyzed by River Bend Station's (RBS) Environmental Laboratory. Attachment 1 also contains RBS' participation in the interlaboratory comparison program during 2006. contains dose calculations performed for sediment using a generalized equation from Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I."

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1.0 Introduction 1.1 Radiological Environmental Monitoring Program ANO established the REMP to ensure that plant operating controls properly function to minimize any associated radiation endangerment to human health or the environment. The REMP is designed for:

" Analyzing important pathways for anticipated types and quantities of radionuclides released into the environment.

" Considering the possibility of a buildup of long-lived radionuclides in the environment and identifying physical and biological accumulations that may contribute to human exposures.

" Considering the potential radiation exposure to plant and animal life in the environment surrounding ANO.

" Correlating levels of radiation and radioactivity in the environment with radioactive releases from station operation.

1.2 Pathways Monitored The airborne, direct radiation, waterborne and ingestion pathways are monitored as required by the ANO ODCM. A description of the ANO REMP utilized to monitor the exposure pathways is described in Table 1.1 and shown in Figures 1-1 and 1-2.

Section 2.0 of this report provides a discussion of 2006 sampling results and Section 3.0 provides a sumnmary of results for the monitored exposure pathways.

1.3 Land Use Census ANO personnel conduct a land use census biannually (once every two years) as required by ANO Units 1 and Unit 2 ODCM Section 2.6.2. The purpose of this census is to identify changes in uses of land within five miles of ANO that would require modifications to the REMP or ODCM. The most important criteria during this census are to determine location in each sector of the nearest:

1) Residence

2) Animal milked for human consumption

3) Garden of greater than 500 square feet producing broadleaf vegetation

• 10

The method used by ANO personnel for conducting the land use census is as follows:

" ANO personnel conduct door-to-door field surveys and/or aerial surveys in each meteorological sector out to five miles in order to locate the nearest resident and milk animal.

" Consultation with local agricultural authorities is used in instances when personal contact cannot be made.

" As a result of these surveys, the following information is obtained in each meteorological sector:

1) Nearest permanent residence

2) Nearest milking animal

" ANO personnel identify locations on the map, measure distances to ANO (or use a GPS system) and record results.

" Locations, if any, are identified which yield a calculated dose or dose commitments greater than those currently calculated in the ODCM.

" ANO personnel compare results to previous census.

• ANO personnel do not perform a garden census since ODCM Section 2.6.2 allows the routine sampling of broadleaf vegetation in the highest D/Q sector near the site boundary in lieu of the garden census.

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Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Airborne Radlolodlne and Particulates 2 samples close to the Site Boundary, in Station 2 (243" - 0.5 miles) - South of the Continuous operation of Radiolodine Canister - Analyze at (or near) different sectors with the highest sewage treatment plant. sampler with sample least once per 14 days for 1-131.

calculated annual average groundlevel Station 56 (264 - 0.4 miles) - West end of the collection as required by DIQ. sewage treatment plant. dust loading but at least Particulate Sampler - Analyze for once per 14 days. gross beta radioactivity following filter change.

Radlolodine and Particulates 1 sample from the vicinity of a community Station 6 (1110 - 6.8 miles) - Entergy local having the highest calculated annual office in Russellville (305 South Knoxville average groundlevel DIQ. Avenue).

Radiolodine andParticulates I sample from a control location 15-30 Station 7 (210* - 19.0 miles) - Entergy Supply km (10 -20 miles) distance. Yard on Highway 10 in Danville.

Radlolodine and Particulates One location sampled voluntarily by Station 1 (88 - 0.5 miles) - Near the ANO. meteorology tower.

Direct TLDs Radiation 16 inner ring stations with two or more Station 1 (880 - 0.5 miles) - On a pole near the Once per 92 days. Gamma Dose - Once per 92 days.

dosimeters in each meteorological sector meteorology tower.

In the general area of the Site Boundary Station 2 (243° - 0.5 miles) - South of the sewage treatment plant.

Station 3 (50 - 0.7 miles) - West of ANO Gate

1. 2 on Highway 333 (approximately 0.35 miles) 12

Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 16 Inner ring stations with two or more Station 4 (1810 - 0.5 miles) - West of May Once per 92 days. Gamma Dose - Once per 92 dosimeters in each meteorological Cemetery entrance on south side of the road. days.

sector In the general area of the Site Station 56 (2640 - 0.4 miles) - West end of the Boundary sewage treatment plant Station 108 (306° - 0.9 miles) - South on Flatwood Road on a utility pole.

Station 109 (2910 - 0.6 miles) - Utility pole across from the junction of Flatwood Road and Round Mountain Road.

Station 110 (138° - 0.8 miles) - Bunker Hill Lane on the first utility pole on the left.

Station 145 (28° - 0.6 miles) - Near west entrance to the RERTC on a utility pole.

Station 146 (450 - 0.6 miles) - South end of east parking lot at RERTC on a utility pole.

Station 147 (610 - 0.6 miles) - West side of Bunker Hill Road, approximately 100 yards from intersection with State Highway 333.

Station 148 (122° - 0.6 miles) - Intersection of Bunker Hill Road with Scott Lane on county road sign past.

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Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 16 Inner ring stations with two or more Station 149 (15r'- 0.5 miles) - On a utility pole Once per 92 days. Gamma Dose - Once per 92 dosimeters in each meteorological on the south side of May Road. days.

sector in the general area of the Site Station 150 (2050 - 0.6 miles) - North side of Boundary May Road on a utility pole past the McCuriey Place turn.

Station 151 (2250 - 0.4 miles) - West side of sewage treatment plant near the lake on a metal post.

Station 152 (3370 - 0.8 miles) -South side of State Highway 333 on a road sign post.

TL-Ds 8 stations with two or more dosimeters Station 6 (111* - 6.8 miles) - Entergy local In special Interest areas such as office in Russellvile (305 South Knoxville population centers, nearby residences, Avenue).

schools, and in 1 - 2 areas to serve as Station 7 (210' - 19.0 miles) - Entergy Supply control locations. Yard on Highway 10 In Danville.

Station 111 (120° - 2.0 miles) - Marina Road on a utility pole on the left just prior to curve.

Station 116 (3180 - 1.8 miles) - Highway 333 and Highway 64 In London on a utility pole north of the railroad tracks.

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Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 8 stations with two or more dosimeters Station 125 (460 - 8.7 miles) - College Street on Once per 92 days. Gamma Dose - Once per 92 in special interest areas such as a utility pole at the southeast comer of the red days.

population centers, nearby residences, brick school building.

schools, and in 1 - 2 areas to serve as Station 127 (100° - 5.2 miles) - Arkansas Tech control locations. Campus on a utility pole across from Paine Hall.

Station 137 (151° - 8.2 miles) - On a speed limit sign on the right in front of the Morris R.

Moore Arkansas National Guard Armory.

Station 153 (3040 - 9.2 miles) - Knoxville Elementary School near the school entrance gate on a utility pole.

Waterbome Surface Water 1 indicator location (influenced by Station 8 (1660 - 0.2 miles) - Plant discharge Once per 92 days. Gamma isotopic and tritium plant discharge) canal. analyses once per 92 days.

I control location (uninfluenced by Station 10 (92° - 0.6 miles) - Plant intake canal.

plant discharge)

Drinking Water I Indicator location (influenced by Station 14 (700 - 5.1 miles) - Russellville city Once per 92 days. 1-131, gross beta, gamma plant discharge) water system from the Illinois Bayou. Isotopic and tritium analyses I control location (uninfluenced by Station 57 (208° - 19.5 miles) - Danville public once per 92 days.

plant discharge) water supply treatment on Fifth Street.

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Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Waterbome Sediment I indicator location (influenced by Station 8 (2430 - 0.9 miles) - Plant discharge Once per 365 days. Gamma Isotopic analysis once plant discharge) canal. per 365 days.

I control location (uninfluenced by Station 16 (287* - 5.5 miles) - Panther Bay on plant discharge) south side of Arkansas River across from mouth of Piney Creek.

Ingestion Milk I indicator sample location within 8 km Currently, no available milking animals within 8 Once per 92 days. Gamma isotopic and 1-131 distance if commercially available. km of ANO. analyses once per 92 days.

I control sample location at a distance of >8 km, when an indicator exists.

Fish 1 sample of commercially andlor Station 8 (2120 - 0.5 miles) - Plant discharge Once per 365 days. Gamma isotopic on edible recreationally Important species in canal. portions once per 365 days.

vicinity of plant discharge.

I sample of same species in area not Station 16 (287* - 5.5 miles) - Panther Bay on influenced by plant discharge. south side of Arkansas River across from mouth of Piney Creek.

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Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Ingestion Food Products I sample of broadleaf (edible or non- Station 13 (273* - 0.5 miles) - West from ANO Three per 365 days. Gamma Isotopic and 1-131 edible) near the Site Boundary from toward Gate 4 onto Flatwood Road. analyses three times per 365 one of the highest anticipated annual average groundlevel D/Q sectors, if days.

milk sampling is not performed.

1 sample location of broadleaf Station 55 (208° - 16.5 miles) - Intersection of vegetation (edible or non-edible) from Highway 27 and 154.

a control location 15 - 30 km distant, if milk sampling Is not performed.

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FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD 18

FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD I

Arkansas Nuclear One REMP Sample Locations WFar Fielcl) 19

2.0 Interpretation and Trends of Results 2.1 Air Particulate and Radioiodine Sample Results The REMP has detected radioactivity in the airborne pathway attributable to other sources.

These include the 25th Chinese nuclear test explosion in 1980 and the radioactive plume release due to reactor core degradation at Chernobyl Nuclear Power Plant in 1986.

During 2006, Iodine-131 was not detected in the radioiodine cartridges, as has been the case in previous years. In addition, indicator gross beta air particulate results for 2006 were within the range of levels obtained in previous years of the operational REMP and well below preoperational levels as seen below. Results are reported as annual average pCi/m 3 .

Monitoring Period Result 2000 - 2005 (Minimum Value) 0.020 2006 Value 0.027 2000 - 2005 (Maximum Value) 0.030 Preoperational 0.050 In the absence of plant-related gamma radionuclides, gross beta activity is attributed to naturally occurring radionuclides. Table 3.1, which includes gross beta concentrations and provides a comparison of the indicator and control means and ranges, emphasizes the consistent trends seen in this pathway to support the presence of naturally occurring activity.

Therefore, it can be concluded that the airborne pathway continues to be unaffected by ANO operations.

2.2 Thermoluminescent Dosimetry Sample Results ANO reports measured dose as net exposure (field reading less transit reading) normalized to 92 days and relies on comparison of the indicator locations to the control as a measure of plant impact. ANO's comparison of the inner ring and special interest area TLD results to the control, as seen in Table 3.1, identified no noticeable trend that would indicate that the ambient radiation levels are being affected by plant operations. In addition, the inner ring value of 7.2 mrem shown in Table 3.1 is within the historical bounds of 1997 - 2005 annual average results, which have ranged from 6.9 to 9.6 mrem.

Gamma radiation dose in the reporting period was further compared to historical control location readings for previous years as shown in Figure 2-1. ANO's comparison of the results to the control indicates that the ambient radiation levels are unaffected by plant operations.

As shown in Figure 2-1, results from the indicator locations were within the upper (+) three standard deviation range for the control. Therefore, levels continue to remain at or near background.

20

Based on the above comparisons, ANO concluded that the ambient radiation levels are not being affected by plant operations.

2.3 Water Sample Results Analytical results for 2006 surface water and drinking water samples were similar to those reported in previous years.

Surface water samples were collected and analyzed for gamma radionuclides and tritium.

Gamma radionuclides were below detectable limits which is consistent with results seen in previous operational years. Tritium continues to be detected at the indicator location (Station

8) where previously monitored liquid radioactive effluent from the plant is periodically discharged in accordance with the regulatory criteria established in the ODCM. However, the levels detected are consistent with concentrations that would typically be seen at this location as shown below. Results are reported as annual average pCi/l.

Monitoring Period Concentration 2000 - 2005 (Minimum Value) 272.0 2006 Value 702.8 2000 - 2005 (Maximum Value) 876.3 Preoperational Value 200.0 ANO personnel have noted no definable increasing trends associated with the tritium levels at the discharge location. Levels detected during 2006 and previous operational years have been well below regulatory reporting limits. Therefore, the operation of ANO had no definable impact on this waterborne pathway during 2006 and levels of radionuclides remain similar to those obtained in previous operational years.

Drinking water samples were collected from two locations (indicator and control).

Although ANO personnel utilize Station 14 (City of Russellville) as an indicator location due to the potential for the drinking water pathway to exist, the City of Russellville has not withdrawn water from Lake Dardanelle in the past several years.

Drinking water samples were analyzed for gross beta radionuclides, Iodine-131, gamma radionuclides and tritium. Gamma radionuclides, Iodine-131 and tritium concentrations were below detectable limits at the indicator and control locations, which is consistent with preoperational and operational years. Gross beta concentrations at the indicator and control locations are similar as shown in Table 3.1. Listed below is a comparison of 2006 indicator results to preoperational and operational years. Results are reported as annual average pCi/l.

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Radionuclide 2006 2000 - 2005 Preoperational Gross Beta 5.58 3.20 2.0 Iodine-131 <LLD <LLD <LLD Gammas <LLD <LLD <LLD Tritium <LLD <LLD 200.0 ANO personnel have noted no definable trends associated with drinking water results at the indicator location. Therefore, the operation of ANO had no definable impact on this waterborne pathway during 2006 and levels of radionuclides remain similar to those obtained in previous operational years.

2.4 Sediment Sample Results Sediment samples were collected from two locations in 2006 and analyzed for gamma radionuclides. As in previous years, Cesium-137 attributable to ANO was detected in the discharge sediment indicator location (Station 8) where previously monitored liquid radioactive effluent from the plant is periodically discharged in accordance with the regulatory criteria established in the ODCM.. Although it is anticipated that radionuclides would be detected at this location since sediment particles provide a natural binding mechanism, ANO personnel have noted no definable consistent trends associated with this radionuclide at the discharge location. Cesium-137 results for 2006 were within the range of previous operational levels as seen below. Results are reported as annual average pCi/kg.

Monitoring Period Concentration 2000 - 2005 (Minimum Value) 200.3 2006 Value 97.78 2000 - 2005 (Maximum Value) 1170.0 Since reporting levels for radionuclides in sediment have not been established, an evaluation of potential dose to the public from this media was performed as shown in Attachment 2. The annual maximum dose from Cesium-137 to the skin and total body was calculated to be

<0.01 millirem.

Design objectives given in 10CFR50, Appendix I for liquid effluents are annual doses of <3 millirem total body and *10 millirem any organ. The values of <0.01 millirem for the skin and total body are well within the design objective criteria. Therefore, the level of Cesium-137 detected in 2006 had no significant impact on the environment or public by this waterborne pathway.

22

2.5 Milk Sample Results Milk samples were not collected during 2006 due to the unavailability of indicator locations within 8-km of ANO. Since there are no dairies within five miles of the ANO site, it is concluded ANO's operation had no impact on this pathway in 2006.

2.6 Fish Sample Results Fish samples were collected from two locations and analyzed for gamma radionuclides. In 2006, gamma radionuclides were below detectable limits which are consistent with the preoperational monitoring period and operational results since 1997. Therefore, based on these measurements, ANO operations had no significant radiological impact upon the environment or public by this ingestion pathway.

2.7 Food Product Sample Results The REMP has detected radionuclides prior to 1990 that are attributable to other sources.

These include the radioactive plume release due to reactor core degradation at Chemobyl Nuclear Power Plant in 1986 and atmospheric weapons testing.

In 2006, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2006 levels remained undetectable, as has been the case in previous years. Therefore, based on these measurements, ANO operations had no significant radiological impact upon the environment or public by this ingestion pathway.

2.8 Land Use Census Results ANO personnel conduct a land use census biannually (once every two years). The most recent land use census was conducted in 2005. Therefore, a census was not required for this reporting year.

2.9 Interlaboratory Comparison Results RBS' Environmental Laboratory analyzed interlaboratory comparison samples for ANO to fulfill the requirements of ANO Units 1 and 2 ODCM Section 2.6.3. Attachment 1, 2006 Radiological Environmental Monitoring Report, contains these results. ANO's review of RBS' interlaboratory comparison indicated that 98% of the sample results for accuracy and precision were within the acceptable control limits of the three normalized deviations. For the one sample result (Beta in water sample prepared June 8, 2006) outside the acceptable control limits, ANO's and RBS's review indicated no impact on previously reported data. provides additional discussion regarding the sample result outside the acceptable control limit.

23

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3.0 Radiological Environmental Monitoring Program Summary 3.1 2006 Program Results Summary Table 3.1 summarizes the 2006 REMP results. ANO personnel did not use values reported as less than the lower limit of detection (<LLD) when determining ranges and means for indicator and control locations.

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TABLE 3.1 Radioloaical Environmental Monitorine Program Summary Name of Facility: ANO - Units 1 and 2 Docket No: 50-313 and 50-368 Location of Facility: Pope County. Arkansas Reporting Period: January - December 2006 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) C Mean (F) c Nonroutine

[ Range I IRange ] Results e Mean (F) c Location d [ Range I Air Particulates GB 135 0.01 0.027 (81/81) Station 56 0.027 (27 /27) 0.024 (54/ 54) 0

( pCI/m3 ) [ 0.007-0.045] (264, 0.4 mi) [0.018 - 0.044] [0.013 - 0.045]

Airborne Iodine 1-131 135 0.07 <LLD N/A N/A <LLD 0

( pCi/m3 )

Inner Ring TLDs Gamma 64 (f) 7.2(64/64) Station 56 8.0(4/4) N/A 0 (rmR/Qtr) [4.0-9.0] (264', 0.4 mi) [7.1 -9.0]

Station 109 8.0(4/4) N/A 0 (291-, 0.6 mi) [7.1-9.0]

SpeclallnterestTLDs Gamma 27 (f) 6.1(27/27) Station 137 7.3(4/4) N/A 0 (mR/Qtr) [4.0-8.0] (151-, 8.2 mi) [6.9-8.0]

Control TLD Gamma 4 (f) N/A N/A N/A 5.8(4/4)

(mR/Qtr) [5.1-6.1 ]

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TABLE 3.1 Radiolocieal Environmental Monitorin! Program Summary Name of Facility: ANO - Units 1 and 2 Docket No: 50-313 and 50-368 Location of Facility: Pope County, Arkansas Reporting Period: January - December 2006 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) c Mean (F) c Nonroutine

[Range ] [Range ] Results e Mean ( F) c Location d [ Range I Surface Water H-3 8 3000 702.8(4/4) Station 8 702.8(4/4) <LLD 0 (pCi/I) [289.0- 1,250.0] (166', 0.2 mi) [289.0- 1,250.0]

GS 24 Mn-54 15 <LLD N/A N/A <LLD 0 Fe-59 30 <LLD N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Co-60 15 <LLD N/A N/A <LLD 0 Zn-65 30 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 Nb-95 15 <LLD N/A N/A <LLD 0 1-131 15 <LLD N/A N/A <LLD 0 Cs-134 15 <LLD N/A N/A <LLD 0 Cs-137 18 <LLD N/A N/A <LLD 0 Ba-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD 0 27

TABLE 3.1 Radiologieal Environmental Monitoring Program Summary Name of Facility: ANO - Units 1 and 2 Docket No: 50-313 and 50-368 Location of Facility: Pope County, Arkansas Reporting Period: January - December 2006 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) c Mean (F) C Nonroutine

[Range I Range ] Results e Mean ( F) c Location d [ Range I Drinking Water GB 8 4 5.58(3/4) Station 14 5.58(3/4) 5.61(4/4) 0 (pCi/i) [1.80-8.23] (70-, 5.1 mi) [1.80-8.23] [1.84-12.75]

1-131 8 1.0 <LLD N/A N/A <LLD 0 H-3 8 2000 <LLD N/A N/A <LLD 0 GS 8 Mn-54 15 <LLD N/A N/A <LLD 0 Fe-59 30 <LLD N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Co-60 15 <LLD N/A N/A <LLD 0 Zn-65 30 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 Nb-95 15 <LLD N/A N/A <LLD 0 Cs-134 15 <LLD N/A N/A <LLD 0 Cs-137 18 <LLD N/A N/A <LLD 0 Ba-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD 0 Bottom Sediment GS 2 (pCi/kg) Cs-134 150 <LLD N/A N/A <LLD 0 Cs-137 180 97.78(1 / 1) Station 8 97.78(1 / 1) <LLD 0

[ N/A ] (243',0.9 mi) [ N/A ]

28

TABLE 3.1 Radloloeocal Environmental Monitorine Proaram Summary Name of Facility: ANO - Units 1 and 2 Docket No: 50-313 and 50-368 Location of Facility: Pope County. Arkansas Reporting Period: January - December 2006 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) c Mean (F) c Nonroutine

[ Range ] [ Range ] Results e Mean (F) c Location d [Range ]

Fish GS 2 (pCi/kg) Mn-54 130 <LLD N/A N/A <LLD 0 Fe-59 260 <LLD N/A N/A <LLD 0 Co-58 130 <LLD N/A N/A <LLD 0 Co-60 130 <LLD N/A N/A <LLD 0 Zn-65 260 <LLD N/A N/A <LLD 0 Cs-134 130 <LLD N/A N/A <LLD 0 Cs-137 150 <LLD N/A N/A <LLD 0 Food Products 1-131 6 60 <LLD N/A N/A N/A 0 (pCi/kg)

GS 6 Cs-134 60 <LLD N/A N/A N/A 0 Cs-137 80 <LLD N/A N/A N/A 0 a GB = Gross beta; 1-131 = Todine-131; H-3 = Tritium; GS f Gamma scan.

b LLD - Required lower limit of detection based on ANO Units 1 and 2 ODCM Tables 2.6-2.

c Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis (F).

d Locations are specified (1) by name and (2) degrees relative to reactor site.

e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result Is considered non-routine if it exceeds ten times the preoperational value for the location.

f LLD is not defined in ANO Units 1 and 2 ODCM Tables 2.6-2.

29

Attachment 1 2006 Radiological Monitoring Report Summary of Monitoring Results 30

TABLE OF CONTENTS TABLE 1.1 AIR PARTICULATE 32 TABLE 1.2 RADIOIODINE CARTRIDGE 33 TABLE 2.1 THERMOLUMINESCENT DOSIMETERS (INNER RING) 34 TABLE 2.2 THERMOLUMINESCENT DOSIMETERS (SPECIAL INTEREST AREAS) 35 TABLE 3.1 SURFACE WATER (GAMMA ISOTOPIC) 36 TABLE 3.2 SURFACE WATER (TRITIUM) 38 TABLE 4.1 DRINKING WATER (GROSS BETA, 1-131 AND GAMMA ISOTOPIC) 39 TABLE 4.2 DRINKING WATER (TRITIUM) 40 TABLE 5.1 SEDIMENT 41 TABLE 6.1 FISH 42 TABLE 7.1 FOOD PRODUCTS 43 TABLE 8.1 INTERLABORATORY COMPARISON 44 31

Table 1.1 Sample Type: Air Particulate Analysis: Gross 3

Beta Units: pCi/m Start Date End Date Station 1 Station 2 Station 56

• Station 6 Station 7 (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 4 0.01 0.01 0.01 0.01 0.01 12/22/2005 01/04/2006 0.035 0.035 0.034 0.027 0.032 01/04/2006 01/10/2006 0.033 0.031 0.034 0.025 0.033 01/10/2006 01/24/2006 0.021 0.022 0.021 0.016 0.019 01/24/2006 02/07/2006 0.022 0.021 0.023 0.017 0.021 02/07/2006 02/21/2006 0.026 0.027 0.023 0.020 0.024 02/21/2006 03/07/2006 0.030 0.031 0.029 0.025 0.029 03/07/2006 03/21/2006 0.016 0.023 0.022 0.018 0.022 03/21/2006 04/04/2006 0.019 0.018 0.018 0.015 0.017 04/04/2006 04/18/2006 0.022 0.024 0.023 0.017 0.023 04/18/2006 05/02/2006 0.022 0.025 0.025 0.021 0.026 05/02/2006 05/16/2006 0.015 0.018 0.018 0.013 0.017 05/16/2006 05/30/2006 0.021 0.022 0.023 0.017 0.024 05/30/2006 06/13/2006 0.027 0.026 0.029 0.023 0:027 06/13/2006 06/27/2006 0.022 0.022 0.020 0.018 0.020 06/27/2006 07/11/2006 0.025 0.027 0.030 0.022 0.024 07/11/2006 07/25/2006 .0.031 0.029 0.031 0.024 0.028 07/25/2006 08/08/2006 0.020 0.019 0.020 0.016 0.017 08/08/2006 08/22/2006 0.025 0.025 0.026 0.021 0.025 08/22/2006 09/05/2006 0.027 0.025 0.028 0.022 0.024 09/05/2006 09/19/2006 0.029 0.029 0.031 0.025 0.028 09/19/2006 10/03/2006 0.029 0.028 0.031 0.020 0.025 10/03/2006 10/17/2006 0.034 0.031 0.033 0.025 0.031 10/17/2006 10/31/2006 0.028 0.007 0.029 0.021 0.024 10/31/2006 11/14/2006 0.035 0.033 0.035 0.026 0.031 11/14/2006 11/28/2006 0.028 0.028 0.027 0.023 0.027 11/28/2006 12/12/2006 0.032 0.031 0.033 0.027 0.030 12/12/2006 12/19/2006 0.045 0.045 0.044 0.037 0.045

• Station with highest annual mean.

32

Table 1.2 Sample Type: Radioiodine Cartridge Analysis: Iodine-131 3

Units: pCi/m Start Date End Date Station 1 Station 2 Station 56 Station 6 Station 7 (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD mu) 0.07 0.07 0.07 0.07 0.07 12/22/2005 01/04/2006 <0.022 <0.020 <0.029 <0.022 <0.022 01/04/2006 01/10/2006 <0.032 <0.036 <0.027 <0.033 <0.031 01/10/2006 01/24/2006 <0.017 <0.020 <0.020 <0.013 <0.016 01/24/2006 02/07/2006 <0.020 <0.023 <0.013 <0.017 <0.016 02/07/2006 02/21/2006 <0.019 <0.020 <0.015 <0.018 <0.018 02/21/2006 03/07/2006 <0.018 <0.014 <0.018 <0.019 <0.019 03/07/2006 03/21/2006 <0.021 <0.015 <0.018 <0.016 <0.020 03/21/2006 04/04/2006 <0.019 <0.017 <0.016 <0.019 <0.014 04/04/2006 04/18/2006 <0.015 <0.016 <0.022 <0.019 <0.017 04/18/2006 05/02/2006 <0.003 <0.016 <0.014 <0.012 <0.016 05/02/2006 05/16/2006 <0.015 <0.019 <0.018 <0.020 <0.018 05/16/2006 05/30/2006 <0.017 <0.016 <0.017 <0.017 <0.020 05/30/2006 06/13/2006 <0.014 <0.022 <0.018 <0.021 <0.022 06/13/2006 06/27/2006 <0.019 <0.016 <0.018 <0.017 <0.018 06/27/2006 07/11/2006 <0.022 <0.018 <0.017 <0.017 <0.021 07/11/2006 07/25/2006 <0.015 <0.014 <0.015 <0.013 <0.015 07/25/2006 08/08/2006 <0.017 <0.016 <0.015 <0.020 <0.021 08/08/2006 08/22/2006 <0.019 <0.017 <0.020 <0.016 <0.020 08/22/2006 09/05/2006 <0.016 <0.013 <0.017 <0.017 <0.017 09/05/2006 09/19/2006 <0.020 <0.020 <0.018 <0.015 <0.017 09/19/2006 10/03/2006 <0.024 <0.021 <0.018 <0.020 <0.020 10/03/2006 10/17/2006 <0.018 <0.017 <0.017 <0.014 <0.018 10/17/2006 10/31/2006 <0.020 <0.020 <0.020 <0.020 <0.020 10/31/2006 11/14/2006 <0.025 <0.027 <0.020 <0.025 <0.026 11/14/2006 11/28/2006 <0.020 <0.015 <0.013 <0.017 <0.018 11/28/2006 12/12/2006 <0.013 <0.014 <0.014 <0.018 <0.019 12/12/2006 12/19/2006 <0.034 <0.035 <0.026 <0.029 <0.025 33

Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mremlQtr Inner Ring (Indicators) 1st Qtr '06 '06 Annual Mean '06 Station 1st Qtr '06 2nd Qtr '06 3rd Qtr '06 4th Qtr 4th Qtr '06 Annual Mean '06 (mrem) (mrem) (mrem) (mrem) (mrem) 3 5.1 6.0 4.0 4.9 5.0 145 7.1 8.0 6.1 5.9 6.8 146 8.1 8.0 6.1 6.9 7.3 147 6.1 7.0 6.1 5.9 6.3 1 8.1 9.0 7.1 6.9 7.8 148 8.1 7.0 7.1 6.9 7.3 110 7.1 8.0 6.1 6.9 7.0 149 8.1 8.0 7.1 6.9 7.5 4 8.1 8.0 7.1 7.9 7.8 150 8.1 8.0 7.1 7.9 7.8 151 8.1 9.0 7.1 6.9 7.8 2 8.1 8.0 7.1 6.9 7.5 56* 8.1 9.0 7.1 7.9 8.0 109

• 8.1 9.0 7.1 7.9 8.0 108 7.1 8.0 7.1 6.9 7.3 152 7.1 8.0 6.1 5.9 6.8

• Stations with highest annual mean.

34

Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Annual Mean '06 Station 1st Qtr '06 2nd Qtr '06 3rd Qtr '06 4th Qtr '06 Annual Mean '06 (mrem) (mrem) (mrem) (mrem) (mrem) 6 6.1 7.0 5.1 5.9 6.0 111 4.0 6.0 4.0 4.9 4.7 116 7.1 8.0 6.1 6.9 7.0 125 5.1 5.0 4.0 4.0 4.5 127 Missing 8.0 7.1 5.9 7.0 137

• 7.1 8.0 7.1 6.9 7.3 153 7.1 7.0 6.1 5.9 6.5

• Station with highest annual mean.

Special Interest Areas - (Control)

Station 1st Qtr '06 2nd Qtr '06 3rd Qtr '06 4th Qtr '06 Annual Mean '06 1st Qtr '06 (mrem) (mrem) (mrem) (mrem) (mrem) 7 6.1 6.0 5.1 5.9 5.8 35

Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/1 Location Start Date End Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Date Reguired LLD 4 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 12/31/2005 01/31/2006 <3.44 <8.12 <4.49 <2.74 <9.60 <5.32 <3.88 <6.03 <3.26 <3.59 <15.66 <8.20 Station 10 (Control) 12/31/2005 01/31/2006 <4.14 <5.32 <4.25 <3.09 <7.09 <6.07 <2.90 <5.77 <3.33 <3.25 <12.88 <6.45 Station 8 (Indicator) 01/31/2006 02/28/2006 <4.29 <6.10 <3.35 <3.02 <6.95 <6.78 <4.11 <8.46 <3.82 <4.08 <22.22 <5.65 Station 10 (Control) 01/31/2006 02/28/2006 <3.52 <7.65 <3.63 <3.42 <6.68 <5.39 <3.73 <6.52 <2.74 <3.24 <18.05 <4.07 Station 8 (Indicator) 02/28/2006 03/31/2006 <3.19 <7.71 <3.62 <3.20 <6.60 <6.31 <3.45 <9.27 <3.39 <3.82 <19.52 <6.23 Station 10 (Control) 02/28/2006 03/31/2006 <2.95 <6.47 <3.44 <3.22 <4.52 <5.63 <3.91 <6.64 <2.90 <3.52 <17.12 <5.73 Station 8 (Indicator) 03/31/2006 04/30/2006 <3.89 <7.86 <3.97 <3.08 <6.95 <6.87 <3.98 <6.16 <3.57 <3.51 <14.21 <4.36 Station 10 (Control) 03/31/2006 04/30/2006 <3.58 <6.08 <2.59 <3.24 <6.32 <5.75 <2.67 <4.89 <3.35 <3.13 <14.81 <3.79 Station 8 (Indicator) 04/30/2006 05/31/2006 <3.57 <6.40 <3.50 <3.44 <5.22 <5.44 <3.26' <5.19 <2.95 <2.98 <1 1.63 <4.56 Station 10 (Control) 04/30/2006 05/31/2006 <3.02 <6.25 <2.84 <2.05 <6.97 <4.35 <3.29 <5.51 <3.31 <3.88 <13.24 <3.97 Station 8 (Indicator) 05/31/2006 06/30/2006 <4.08 <10.94 <3.48 <4.22 <9.04 <8.15 <3.68 <11.28 <3.99 <3.87 <22.58 <8.12 Station 10 (Control) 05/31/2006 06/30/2006 <3.86 <8.84 <3.93 <3.38 <7.63 <7.09 <4.77 <12.05 <4.44 <3.71 <24.54 <9.88 36

Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Date Reguired LLD 4 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 06/30/2006 07/31/2006 <3.62 <7.63 <2.90 <2.78 <7.30 <6.84 <4.52 <7.67 <4.04 <3.41 <19.03 <7.15 Station 10 (Control) 06/30/2006 07/31/2006 <3.31 <8.58 <3.34 <3.47 <6.01 <5.84 <4.02 <5.21 <4.34 <3.36 <14.62 <6.06 Station 8 (Indicator) 07/31/2006 08/31/2006 <5.92 <9.67 <4.07 <3.06 <11.08 <10.86 <5.41 <13.64 <5.97 <4.02 <34.12 <9.94 Station 10 (Control) 07/31/2006 08/31/2006 <4.32 <8.95 <4.23 <4.19 <8.61 <8.56 <6.39 <11.28 <3.91 <5.00 <23.33 <9.58 Station 8 (Indicator) 08/31/2006 09/30/2006 <3.15 <6.70 <3.55 <3.61 <7.80 <7.02 <3.97 <7.61 <3.85 <3.90 <18.68 <4.93 Station 10 (Control) 08/31/2006 09/30/2006 <2.48 <6.19 <3.24 <3.03 <6.29 <6.67 <4.14 <6.07 <3.46 <3.73 <17.83 <6.69 Station 8 (Indicator) 09/30/2006 10/31/2006 <2.84 <6.72 <3.37 <2.69 <6.78 <5.50 <3.85 <5.18 <2.33 <2.95 <15.35 <5.89 Station 10 (Control) 09/30/2006 10/31/2006 <3.87 <9.14 <3.37 <2.76 <7.11 <4.83 <3.72 <7.44 <4.72 <4.11 <17.05 <6.71 Station 8 (Indicator) 10/31/2006 11/30/2006 <3.73 <8.14 <2.75 <3.98 <7.94 <8.60 <6.46 <12.57 <4.26 <3.88 <25.29 <10.21 Station 10 (Control) 10/31/2006 11/30/2006 <3.37 <4.99 <3.65 <2.99 <7.44 <6.34 <5.12 <14.25 <3.23 <3.77 <30.97 <6.77 Station 8 (Indicator) 11/30/2006 12/31/2006 <3.84 <7.06 <3.18 <3.18 <7.10 <6.37 <4.02 <7.03 <3.72 <4.33 <22.05 <5.98 Station 10 (Control) 11/30/2006 12/31/2006 <3.62 <7.74 <3.69 <3.36 <6.46 <6.89 <5.03 <7.77 <3.67 <3.66 <15.67 <8.56 37

Table 3.2 Sample Type: Surface Water Analysis: Tritium Units: pCi/l Location Begin Date End Date H-3 Required LLD 4 3000 Station 8 (Indicator) 12/31/2005 03/31/2006 531 Station 10 (Control) 12/31/2005 03/31/2006 <587 Station 8 (Indicator) 03/31/2006 06/30/2006 289 Station 10 (Control) 03/31/2006 06/30/2006 <578 Station 8 (Indicator) 06/30/2006 09/30/2006 1,250 Station 10 (Control) 06/30/2006 09/30/2006 <571 Station 8 (Indicator) 09/30/2006 12/31/2006 741 Station 10 (Control) 09/30/2006 12/31/2006 <571 38

Table 4.1 Sample Type: Drinking Water Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Units: pCi/l Location Collection Gross 1-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Date Beta Reauired LLD 4 4. 1.0 15 30 15 15 30 30 15 15 18 60 15 Station 14 (Indicator) 03/24/2006 6.71 <0.89 <6.31 <12.79 <4.16 <5.46 <7.13 <8.57 <5.04 <3.23 <5.89 <21.30 <8.66 Station 57 (Control) 03/21/2006 3.12 <0.89 <5.14 <5.69 <6.28 <4.95 <8.97 <8.64 <4.16 <4.72 <4.36 <32.37 <7.89 Station 14 (Indicator) 07/06/2006 8.23 <0.81 <3.17 <6.78 <3.57 <3.35 <5.97 <6.10 <3.69 <3.06 <3.03 <14.77 <6.03 Station 57 (Control) 07/06/2006 12.75 <0.87 <3.00 <7.79 <3.35 <4.38 <6.86 <7.69 <4.13 <3.15 <3.94 <19.81 <5.63 Station 14 (Indicator) 09/20/2006 1.80 <0.85 <5.80 <10.81 <6.54 <5.17 <10.01 <9.64 <4.82 <6.47 <6.88 <22.20 <8.95 Station 57 (Control) 09/20/2006 4.71 <0.90 <3.98 <6.67 <4.37 <5.14 <9.87 <8.67 <5.25 <4.72 <2.71 <21.35 <9.87 Station 14 (Indicator) 12/19/2006 <1.95 <0.90 <4.73 <8.62 <4.72 <3.44 <12.80 <8.75 <5.74 <4.89 <6.79 <27.99 <8.14 Station 57 (Control) 12/19/2006 1.84 <0.90 <2.98 <9.16 <3.39 <3.55 <10.05 <6.63 <5.68 <3.68 <5.11 <23.92 <9.39 39

Table 4.2 Sample Type: Drinkin2 Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 4 2000 Station 14 (Indicator) 03/24/2006 <574 Station 57 (Control) 03/21/2006 <579 Station 14 (Indicator) 07/06/2006 <570 Station 57 (Control) 07/06/2006 <576 Station 14 (Indicator) 09/20/2006 <568 Station 57 (Control) 09/20/2006 <574 Station 14 (Indicator) 12/19/2006 <580 Station 57 (Control) 12/19/2006 <573 40

Table 5.1 Sample Type: Sediment Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Cs-134 Cs-137 Required LLD -3 150 180 Station 8 (Indicator) 10/04/2006 <134.54 97.78 Station 16 (Control) 10/17/2006 <71.70 <66.18 41

Table 6.1 Sample Type: Fish Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Required LLD 4 130 260 130 130 260 130 150 Station 8 (Indicator) 09/28/2006 <15.83 <180.87 <49.18 <25.22 <68.34 <15.56 <13.46 Station 16 (Control) 09/07/2006 <17.80 <242.69 <50.95 <19.00 <47.22 <14.00 <14.20 42

Table 7.1 Sample Type: Food Products Analysis: Iodine-131 and Gamma Isotopic Units: pCi/kg Location Collection Date 1-131 Cs-134 Cs-137 Required LLD 4 60 60 80 Station 13 (Indicator) 06/15/2006 <47.32 <27.55 <21.93 Station 55 (Control) 06/13/2006 <57.87 <38.05 <55.45 Station 13 (Indicator) 07/26/2006 <57.57 <50.01 <37.87 Station 55 (Control) 07/25/2006 <45.20 <48.04 <39.32 Station 13 (Indicator) 08/22/2006 <55.03 <38.96 <33.32 Station 55 (Control) 08/22/2006 <59.65 <32.82 <32.28 43

Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value Value N-Dev b N-Range Charcoal Cartridge E5008-125 06/08/2006 1-131 66.4 73 1.15 0.297 (pCi/cartridge) I I I Water E5007-125 06/08/2006 Beta 169 125 -3.01 d 0.093 (pCi/liter)

E5006-125 06/08/2006 Cr-51 210 222 0.64 0.544 Mn-54 119 129.0 0.97 0.199 Co-58 81.2 82.0 0.11 0.436 Fe-59 75.8 77.3 0.23 0.779 Co-60 104 105 0.15 0.227 Zn-65 150 157 0.56 0.394 1-131 74.7 79.7 0.77 0.211 Cs-134 103 101 -0.22 0.153 Cs-137 95.1 104 1.12 0.248 Ce-141 149.00 157 0.62 0.159 E5083-125 09/13/2006 H-3 11000 10926 -0.08 0.142 Milk E5009-125 06/08/2006 Cr-51 259 243 -0.70 0.395 (pCi/liter)

Mn-54 146 150.0 0.32 0.135 Co-58 100 101.0 0.12 0.118 Fe-59 93.6 104.0 1.28 0.463 Co-60 104 128 2.63 0.189 Zn-65 185 183.0 -0.12 0.170 1-131 63.2 60.7 -0.46 0.187 Cs-134 127 122.7 -0.39 0.062 Cs-137 117 115 -0.20 0.067 44

Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Tritium and Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value Value N-Dev b N-Rangee Air Filter E5081-125 09/13/2006 Beta 88.4 99.2 1.41 0.058 (pCi/Filter)

E5237-125 02/12/2007 Cr-51 145 141 -0.33 0.277 Mn-54 171 185.3 0.97 0.104 Co-58 77.9 79.6 0.26 0.369 Fe-59 50.2 54.6 1.01 0.745 Co-60 491.0 493.9 0.07 0.030 Zn-65 243 277.6 1.64 0.107 Cs-134 248.0 243.1 -0.23 0.094 Cs-137 423 443 0.54 0.028 Ce-141 145.0 125 -1.56 0.065 Sediment E5082-125 09/13/2006 Cr-51 0.423 0.421 -0.05 0.465 (pCi/gram)

Mn-54 0.169 0.169 0.02 0.163 Co-58 0.164 0.155 -0.61 0.600 Fe-59 0.066 0.062 -0.64 0.776 Co-60 0.201 0.182 -1.11 0.196 Zn-65 0.218 0.210 -0.42 0.578 Cs-134 0.128 0.126 -0.15 0.185 Cs-137 0.362 0.378 0.51 0.174 Ce-141 0.129 0.119 -0.90 0.275 NOTES:

(a) The "known" value as determined by Analytics.

(b) The normalized deviation from the "known" value is computed from the deviation and the standard error of the mean; +/-2.0 is the warning limit and +/-3.00 is the control limit.

This is a measure of accuracy of the analytical methods.

(c) The normalized range is computed from the mean range, the control limit and the standard error of the range; +2.00 is the warning limit and +3.00 is the control limit.

This is a measure of precision of the analytical methods.

(d) The results reported were outside the acceptable control limits.

45

Interlaboratory Comparison Program Exceptions There was one result outside the control limits for accuracy in the 2006 Interlaboratory Comparison Program studies. The gross beta in water was 0.006% outside the lower control limit.

In October 2006, a new gross beta in water sample was prepared using the same source material. The results were within the acceptance criteria for the test. This same sample was counted on a new alpha/beta counter and was also within the control limits.

Review of trending information of gross beta in water results shows a fluctuation of high and low values. In 2000 there was another occurrence of gross beta in water below the control limit of 3.0. Analytics was contacted to see if there was a low bias of reporting gross beta in water by other participants. All other participant results looked normal with no low bias responses with the sample.

The most probable cause of the low value was sample preparation error. The low result could also have been due to machine age or an intermittent issue, but other samples counted on the same machine were within the control level. The new sample that was counted lends the most logical conclusion that a preparation error could have occurred during mixing, transfer or evaporation of the sample media.

There is no impact accessed on previously reported data due to these results.

Environmental samples are analyzed and reported with a ninety-five percent confidence level. A known standard is counted with each group of samples and must read within 10 percent of the decay corrected activity. Ninety-eight percent of RBS environmental crosscheck results were within control limits for accuracy and 100% for precision during 2006.

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AYIACHMENT 2 Sediment Dose Calculations 47

Sediment Dose Calculations Dose calculation for the discharge sediment was performed using generalized equation found in Regulatory Guide 1.109, Appendix A as follows:

R= (40) x (C) x (U) x (D) x (W)

R= Annual dose to skin or total body in mrem/year; 40= Area-mass conversion factor given in Appendix A of Regulatory Guide 1.109 in Kg/m 2 ;

C= 2006 maximum radionuclide concentration in pCi/kg; U= Maximum exposure time given in Table E-5 of Regulatory Guide 1.109 (67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> for teenager);

D= External dose conversion factor for standing on contaminated ground given in Table E-6 of Regulatory Guide 1.109 in mrem/hr per pCi/m 2 , and W= Shore-width factor (0.1) given in Table A-2 of Regulatory Guide 1.109.

(Dose from Sediment in Millirem/Year)

Radionuclide 2006 Maximum Conversion Factor Total Conversion Factor Total Concentration For Skin Skin Dose For Total Body Body Dose Cs-137 97.98 4.90 E-09 1.29 E-04 4.20 E-09 1.10 E-04 TOTAL 1.29 E-04 1.10 E-04 I

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