0CAN041102, Annual Radiological Environmental Operating Report for 2010

Annual Radiological Environmental Operating Report for 2010

ML111101191
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/20/2011
From:	Pyle S Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
0CAN041102
Download: ML111101191 (60)

Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4710 Stephenie L. Pyle Acting Manager, Licensing Arkansas Nuclear One 0CAN041102 April 20, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Annual Radiological Environmental Operating Report for 2010 Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

REFERENCE:

1. Arkansas Nuclear One, Unit 1, Technical Specification 5.6.2

2. Arkansas Nuclear One, Unit 2, Technical Specification 6.6.2

Dear Sir or Madam:

The referenced Arkansas Nuclear One (ANO) Technical Specifications (TSs) require the submittal of an annual radiological environmental operating report for the previous year by May 15 of each year. Attached is the subject ANO report for the calendar year 2010.

This report fulfills the reporting requirements of the TSs referenced above.

The radionuclides detected by the radiological environmental monitoring program during 2010 were significantly below the regulatory limits. The operation of the ANO station during 2010 had no harmful effects nor resulted in any irreversible damage to the local environment.

Based on ANOs review, no environmental samples from the monitoring program equaled or exceeded the reporting levels for radioactivity concentration due to ANO effluents when averaged over any calendar quarter. Therefore, the 2010 results did not require any Radiological Monitoring Program special reports.

This letter contains no new commitments.

0CAN041102 Page 2 of 2 If you have any questions or require additional information, please contact me.

Sincerely, Original signed by Stephenie L. Pyle SLP/rwc

Attachment:

Annual Radiological Environmental Operating Report for 2010 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment to 0CAN041102 Annual Radiological Environmental Operating Report for 2010

ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)

FOR 2010

Attachment to 0CAN041102 Page 2 of 57 TABLE OF CONTENTS

SUMMARY

6

1.0 INTRODUCTION

11 1.1 Radiological Environmental Monitoring Program 11 1.2 Pathways Monitored 11 1.3 Land Use Census 11 2.0 INTERPRETATION AND TRENDS OF RESULTS 22 2.1 Air Particulate and Radioiodine Sample Results 22 2.2 Thermoluminescent Dosimetry (TLD) Sample Results 22 2.3 Water Sample Results 22 2.4 Sediment Sample Results 25 2.5 Milk Sample Results 25 2.6 Fish Sample Results 25 2.7 Food Product Sample Results 25 2.8 Interlaboratory Comparison Results 26 2.9 Land Use Census Results 26 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

28 3.1 2010 Program Results Summary 28

Attachment to 0CAN041102 Page 3 of 57 LIST OF TABLES Table 1.1 Radiological Environmental Sampling Program 13 Table 2.1 2010 Land Use Census 27 Table 3.1 Radiological Environmental Monitoring Program Summary 29

Attachment to 0CAN041102 Page 4 of 57 LIST OF FIGURES Figure 1-1 Sample Collection Sites - NEAR FIELD 19 Figure 1-2 Sample Collection Sites - FAR FIELD 20 Figure 1-3 Sample Collection Sites - SITE MAP 21

Attachment to 0CAN041102 Page 5 of 57 LIST OF ATTACHMENTS 2010 Radiological Monitoring Report Summary of Monitoring Results 33 Interlaboratory Comparison Program 49 Sediment Dose Calculations 55

Attachment to 0CAN041102 Page 6 of 57 Summary The Annual Radiological Environmental Operating Report (AREOR) presents data obtained through analyses of environmental samples collected for Arkansas Nuclear One's (ANOs)

Radiological Environmental Monitoring Program (REMP) for the period January 1, 2010 through December 31, 2010. This report fulfills the requirements of ANO Unit 1 Technical Specification (TS) 5.6.2 and Unit 2 TS 6.6.2.

During 2010, 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 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.

Attachment to 0CAN041102 Page 7 of 57 In 2010, 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 2010 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 2010. 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 ODCM Table 2.6-3, when averaged over any calendar quarter. Therefore, 2010 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) Thermoluminescent Dosimeter (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.

Attachment to 0CAN041102 Page 8 of 57 Sample Deviations Milk The REMP did not include milk sampling within five miles of ANO in 2010 due to unavailability. The ODCM requires collection of milk samples if available commercially within 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 ODCM.

Attachment to 0CAN041102 Page 9 of 57 Air Samples Listed below are air sampler deviations that occurred during 2010 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 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 02 02/02/2010 - 02/16/2010 Identified power failure at 1139 on 2/16/11 Air.

Entergy Arkansas notified. Power restored at 1330.

(CR-ANO-C-2010-00323) 01 08/03/2010 - 08/17/2010 Air sample pump discovered not operating (seized up). Replaced sample pump.

(CR-ANO-C-2010-02102) 01 10/26/2010 - 11/09/2010 Pump running with fewer than expected run time hours recorded. Indicates a power outage during sampling period.

(CR-ANO-C-2010-02888) 01 11/09/2010 - 11/23/2010 Runtime meter did not advance during sample period. Replaced runtime meter.

(CR-ANO-C-2010-03016) 02 12/07/2010 - 12/21/2010 Pump running with fewer than expected run time hours recorded. Indicates a power outage during sampling period.

(CR-ANO-C-2010-03240)

Attachment to 0CAN041102 Page 10 of 57 Missed Samples During the first quarter 2010 change out of environmental TLD's, TLD # 148 along with the TLD holder were missing. A replacement TLD holder and TLD was installed.

(CR-ANO-C-2010-0077).

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

Program Modifications ANO made no modifications to the REMP during 2010.

Attachments contains results of air, TLD, water, sediment, fish, and food product samples collected in 2010. TLDs were analyzed by a vendor (AREVA). All remaining samples were analyzed by River Bend Stations (RBS) Environmental Laboratory. also contains RBS participation in the interlaboratory comparison program during 2010. 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, Revision 1.

Attachment to 0CAN041102 Page 11 of 57 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 applicable 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 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, 1-2 and 1-3.

Section 2.0 of this report provides a discussion of 2010 sampling results and Section 3.0 provides a summary of results for the monitored exposure pathways.

1.3 Land Use Census ANO personnel conducts land use census biannually (once every two years) as required by ODCM Section 2.6.2. The latest land use census was conducted in 2009. 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 fresh leafy (broadleaf) vegetables*

• 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.

Attachment to 0CAN041102 Page 12 of 57 The method used by ANO personnel for conducting the land use census is as follows:

• ANO personnel conducted door-to-door (drive by) field surveys in order to locate the nearest resident in each meteorological sector.

• Consultation with local agricultural authorities is used for the identification of commercial milk providers within five-miles of the Unit-1 reactor building.

• 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.

Attachment to 0CAN041102 Page 13 of 57 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Of Analyses Frequency Airborne Radioiodine and Particulates 2 samples close to the Site Boundary, in Station 2 (243° - 0.5 miles) - South of the Continuous operation of Radioiodine Canister - Analyze at (or near) different sectors with the highest sewage treatment plant. sampler with sample least once per 14 days for I-131.

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

Radioiodine and Particulates 1 sample from the vicinity of a community Station 1 (88° - 0.5 miles) - Near the having the highest calculated annual meteorology tower.

average groundlevel D/Q.

Radioiodine and Particulates 1 sample from a control location 15-30 km Station 7 (210° - 19.0 miles) - Entergy Supply (10 - 20 miles) distance. Yard on Highway 10 in Danville.

Radioiodine and Particulates One location sampled voluntarily by ANO. Station 6 (111° - 6.8 miles) - Entergy local office in Russellville (305 South Knoxville Avenue).

Direct Thermoluminescent dosimetry (TLDs)

Radiation 16 inner ring stations with two or more Station 1 (88° - 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 (5° - 0.7 miles) - West of ANO Gate

1. 2 on Highway 333 (approximately 0.35 miles)

Attachment to 0CAN041102 Page 14 of 57 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Of Analyses Frequency Direct TLDs Radiation 16 inner ring stations with two or more Station 4 (181° - 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 Boundary Station 56 (264° - 0.4 miles) - West end of the sewage treatment plant.

Station 108 (306° - 0.9 miles) - South on Flatwood Road on a utility pole.

Station 109 (291° - 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 (45° - 0.6 miles) - South end of east parking lot at RERTC on a utility pole.

Station 147 (61° - 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 post.

Attachment to 0CAN041102 Page 15 of 57 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Of Analyses Frequency Direct TLDs Radiation 16 inner ring stations with two or more Station 149 (156° - 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 Boundary Station 150 (205° - 0.6 miles) - North side of May Road on a utility pole past the McCurley Place turn.

Station 151 (225° - 0.4 miles) - West side of sewage treatment plant near the lake on a metal post.

Station 152 (338° - 0.8 miles) - South side of State Highway 333 on a road sign post.

TLDs 8 stations with two or more dosimeters Station 6 (111° - 6.8 miles) - Entergy local office in special interest areas such as in Russellville (305 South Knoxville Avenue).

population centers, nearby residences, 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 (318° - 1.8 miles) - Highway 333 and Highway 64 in London on a utility pole north of the railroad tracks.

Attachment to 0CAN041102 Page 16 of 57 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Of Analyses Frequency Direct TLDs Radiation 8 stations with two or more dosimeters Station 125 (46° - 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 corner of the red days.

population centers, nearby residences, brick school building.

schools, and in 1 - 2 areas to serve as control locations. Station 127 (100° - 5.2 miles) - Arkansas Tech 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 (304° - 9.2 miles) - Knoxville Elementary School near the school entrance gate on a utility pole.

Waterborne Surface Water 1 indicator location (influenced by plant Station 8 (166° - 0.2 miles) - Plant discharge Once per 92 days. Gamma isotopic and tritium discharge) canal. analyses once per 92 days.

1 control location (uninfluenced by Station 10 (95° - 0.5 miles) - Plant intake canal.

plant discharge)

Drinking Water 1 indicator location (influenced by Station 14 (70° - 5.1 miles) - Russellville city Once per 92 days. I-131, gross beta, gamma plant discharge) water system from the Illinois Bayou. isotopic and tritium analyses once per 92 days.

1 control location (uninfluenced by Station 57 (208° - 19.5 miles) - Danville public plant discharge) water supply treatment on Fifth Street.

Attachment to 0CAN041102 Page 17 of 57 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Of Analyses Frequency Waterborne Sediment 1 indicator location (influenced by plant Station 8 (243° - 0.9 miles) - Plant discharge Once per 365 days. Gamma isotopic analysis once discharge) canal. per 365 days.

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

1 control sample location at a distance of >five-miles when an indicator exists.

Fish 1 sample of commercially and/or Station 8 (212° - 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.

1 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.

Attachment to 0CAN041102 Page 18 of 57 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Of Analyses Frequency Ingestion Food Products 1 sample of broadleaf (edible or non- Station 13 (273° - 0.5 miles) - West from ANO Three per 365 days. Gamma isotopic and I-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 (10 - 20 miles) distant, if milk sampling is not performed.

Groundwater 1 sample location of Groundwater from Station 58 (GWM-1, 22° - 0.3 miles) - North of Once per 92 days Control, Tritium and Gamma a control location up gradient from the Protected Area on Owner Control Area (OCA). Isotopic, once per 92 days.

protected area South of Outside Fab-Shop, west side of access road 3 sample locations of Groundwater Station 59 (GWM-2, 185° - 0.1 miles) - South of Once per 92 days Indicator, Tritium and Gamma from indicator locations down gradient Protected Area on OCA. Near Security barriers Isotopic, once per 92 days.

from the protected area and discharge canal.

Station 60 (GWM-3, 206° - 0.1 miles) - South of Once per 92 days Indicator, Tritium and Gamma Protected area on OCA. West of Station number Isotopic, once per 92 days.

59 near wood line.

Station 61 (GWM-4, 245° - 0.1 miles) - West of Once per 92 days Indicator, Tritium and Gamma Protected Area on OCA. Edge of parking lot, Isotopic, once per 92 days.

east of equipment laydown area

Attachment to 0CAN041102 Page 19 of 57 FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD SR 333 152 108 Training 145 Center 146 147 109 13 1 West Access Rd. 10 56 2 8C 36 Scott Ln.

151 148 8S May Rd. Bunker Cemetery Bunker Hill Ln.

Hill Rd.

149 150 4 110 Arkansas Nuclear One REMP Sample Locations (Near Field)

Lake Dardanelle Revised 24May05

Attachment to 0CAN041102 Page 20 of 57 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 1

2 0° 16 340° 20° US HWY 7 TO HARRISON 15 320° 40° INTERSTATE 40 3

TO FORT SMITH SR 5 PINEY BAY USE AREA Dover 125 SR 333 300° 60° 164 EAST TO 153 U.S.

MORELAND HWY 14 64 4

14 SR 24 TO MORELAND 280° ARKANSAS RIVER 116 INTERSTATE 40 80° 16 LONDON US 13 J I H G F E D C B HWY 64 5

DELAWARE STATE PARK 127 260° DARDANELLE STATE PARK 111 ARKANSAS TECH UNIVERSITY 100° U.S. HWY 22 HWY 524 LAKE DARDANELLE DARDANELLE STATE PARK RUSSELLVILLE 6

12 DARDANELLE LOCK AND DAM HWY 22 DAM SITE EAST PARK HWY 7T 6 240° 120° HWY 155 HWY 7 SR 247 TO POTTSVILLE MT. NEBO HWY 27 137 STATE PARK DARDANELLE 11 220° HWY 28 140° 7

HWY 7 200° 160° 10 180° 8

HWY 7 TO HOT SPRINGS HWY 27 TO DANVILLE INSET DANVILLE (SEE INSET) 9 N W E HWY 154 S

HWY 27 55 HWY 10 Entergy Substation 7

Petit Jean River 57 HWY 10 Cowger Lake City of Danville Arkansas Nuclear One HWY 80 HWY 27 REMP Sample Locations (Far Field)

Attachment to 0CAN041102 Page 21 of 57 FIGURE 1-3 SAMPLE COLLECTION SITES - SITE MAP 58 STR-3 Switch STR-2 Yard STR-4 West Access Road 61 STR-5 60 59 STR-1 N

Lake Dardanelle S

Arkansas Nuclear One REMP Sample Locations Site Map

Attachment to 0CAN041102 Page 22 of 57 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 2010, 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 2010 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 picocuries per cubic meter (pCi/m3).

Monitoring Period Result 2000 - 2009 (Minimum Value) 0.020 2010 Value 0.030 2000 - 2009 (Maximum Value) 0.032 Preoperational 0.050 In the absence of plant-related gamma radionuclides, gross beta activity is attributed to naturally occurring radionuclides. Table 3.1, which include gross beta concentrations and provide 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 (TLD) 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. ANOs 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 8.3 millirem (mrem) shown in Table 3.1 is within the historical bounds of 2000 -

2009 annual average results, which have ranged from 6.7 to 8.8 mrem.

Overall, ANO concluded that the ambient radiation levels are not being affected by plant operations.

2.3 Water Sample Results Analytical results for 2010 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

Attachment to 0CAN041102 Page 23 of 57 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 picocurie per liter (pCi/l).

Monitoring Period Concentration 2000 - 2009 (Minimum Value) 272.0 2010 Value 985.0 2000 - 2009 (Maximum Value) 1023.4 Preoperational Value 200.0 ANO personnel have noted no definable increasing trends associated with the tritium levels at the discharge location. Levels detected during 2010 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 2010 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 the LLD 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 2010 indicator results to preoperational and operational years. Results are reported as annual average pCi/l.

Radionuclide 2010 2000 - 2009 Preoperational Gross Beta 1.55 2.97 2.0 Iodine-131 <LLD <LLD <LLD Gamma <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 2010 and levels of radionuclides remain similar to those obtained in previous operational years.

Groundwater samples were collected from four locations (1 control, and 3 indicator locations). Sample data was compiled, organized and is reviewed annually as a minimum to:

Attachment to 0CAN041102 Page 24 of 57

• Analyze for increasing or decreasing trends at individual sample points, wells or groups of wells.

• Review the radionuclides detected to determine whether changes should be made to the analysis suites or sampling frequencies for each sampling location.

• Evaluate the locations of radionuclides in ground water to determine if changes should be made to the sampling locations.

• Review current investigation levels and determine if changes should be made.

• Determine if any change to the ODCM is required.

• Determine if a corrective actions/remediation is required.

Groundwater samples were analyzed for Tritium and Gamma radionuclides. Tritium and Gamma concentrations were below the LLD limits at the indicator and control locations.

Listed below is a comparison of 2010 indicator results to past operational years. Results are reported as annual average pCi/l. Groundwater data is captured in Tables 8.1 and 8.2.

Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway.

Radionuclide 2010 2006 - 2009 Iodine-131 <LLD <LLD Gamma <LLD <LLD Tritium <LLD <LLD

Attachment to 0CAN041102 Page 25 of 57 2.4 Sediment Sample Results Sediment samples were collected from two locations in 2010 and analyzed for gamma radionuclides. Listed below is a comparison of 2010 indicator results to past operational years. Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway. Results are reported as pCi/kg.

Monitoring Period Concentration 2000 - 2009 (Minimum Value) 41.79 2010 Value 65.55 2000 - 2009 (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 .

2.5 Milk Sample Results Milk samples were not collected during 2010 due to the unavailability of indicator locations within five-miles of ANO.

2.6 Fish Sample Results Fish samples were collected from two locations and analyzed for gamma radionuclides. In 2010, 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 Chernobyl Nuclear Power Plant in 1986 and atmospheric weapons testing.

In 2010, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2010 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.

Attachment to 0CAN041102 Page 26 of 57 2.8 Interlaboratory Comparison Results RBS Environmental Laboratory analyzed interlaboratory comparison samples for ANO to fulfill the requirements of ODCM Section 2.6.3. Attachment 2 contains these results. ANOs review of RBS interlaboratory comparison indicated that 100% of the sample results (42 of

42) were within the acceptable control limits.

2.9 Land Use Census Results The latest land use census (performed in 2009) did not identify any new locations that yielded a calculated dose or dose commitment greater than those currently calculated. (See Table 2.1)

Also, the land use census identified no milk-producing animals within a five-mile radius of the plant site. ANO personnel chose not to perform a garden census in 2009, which is allowed by ODCM Section 2.6.2, in lieu of broadleaf vegetation sampling in the meteorological sector (Sector 13) with the highest D/Q.

Attachment to 0CAN041102 Page 27 of 57 TABLE 2.1 2009 Land Use Census Nearest Residence Within Five Miles Direction Sector Distance (miles)

N 1 0.9 NNE 2 1.3 NE 3 0.9 ENE 4 0.8 E 5 0.8 ESE 6 0.8 SE 7 0.8 SSE 8 0.8 S 9 0.8 SSW 10 0.7 SW 11 2.8 WSW 12 0.7 W 13 0.8 WNW 14 0.8 NW 15 1.0 NNW 16 0.9

Attachment to 0CAN041102 Page 28 of 57 3.0 Radiological Environmental Monitoring Program Summary 3.1 2010 Program Results Summary Table 3.1 summarizes the 2010 REMP results. ANO personnel did not use values reported as <LLD when determining ranges and means for indicator and control locations.

Attachment to 0CAN041102 Page 29 of 57 TABLE 3.1 Radiological 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 2010 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Mean Control Number of

( Units ) of Analyses a Mean ( F ) c Locations Nonroutine

[ Range ] Mean ( F ) c Results e

[ Range ]

Location d Mean ( F ) c

[ Range ]

Air Particulates GB 130 0.01 0.030 ( 78 / 78 ) Station 1 0.031 ( 26 / 26 ) 0.027 ( 52 / 52 ) 0

( pCi/m3 ) [ 0.004 - 0.050 ] ( 88°, 0.5 mi ) [ 0.014 - 0.049 ] [ 0.016 - 0.046 ]

Airborne Iodine I-131 130 0.07 <LLD N/A N/A <LLD 0

( pCi/m3 )

Inner Ring TLDs Gamma 63 (f) 8.2 ( 63 / 64 ) Station 56 10.0 ( 4 / 4 ) N/A 0

( mR/Qtr ) [ 6.3 - 10.0 ] ( 264°, 0.4 mi ) [ 9.4 - 11.1 ]

Special Interest Gamma 28 (f) 7.4 ( 28 / 28 ) Station 116 8.6 ( 4 / 4 ) N/A 0 TLDs [ 5.3 - 8.6 ] ( 318°, 1.8 mi ) [ 7.2 - 9.2 ]

( mR/Qtr )

Control TLD Gamma 4 (f) N/A N/A N/A 6.9 ( 4 / 4 ) 0

( mR/Qtr ) [ 6.3 - 8.3 ]

Attachment to 0CAN041102 Page 30 of 57 TABLE 3.1 Radiological 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 2010 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Control Number of

( Units ) of Analyses a Mean ( F ) c Mean Locations Nonroutine

[ Range ] Mean ( F ) c Results e

[ Range ]

Location d Mean ( F ) c

[ Range ]

Surface Water H-3 8 3000 717.0 ( 3 / 4 ) Station 8 717.0 ( 3 / 4 ) <LLD 0

( pCi/l ) [ 565.0 - 985.0 ] ( 166°, 0.2 mi ) [ 565.0 - 985.0 ]

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 I-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

Attachment to 0CAN041102 Page 31 of 57 TABLE 3.1 Radiological 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 2010 Sample Type Type & LLD b Indicator Locations Location with Highest Annual Control Locations Number of

( Units ) Number Mean ( F ) c Mean Mean ( F ) c Nonroutine of Analyses a [ Range ] [ Range ] Results e Location d Mean ( F ) c

[ Range ]

Drinking Water GB 8 4 1.55 ( 4 / 4 ) Station 14 1.55 ( 4 / 4 ) 2.76 ( 4 / 4 ) 0

( pCi/1 ) [ 0.63 - 2.30 ] ( 70°, 5.1 mi ) [ 0.63 - 2.30 ] [ 2.12 - 3.36 ]

I-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 <LLD <LLD 0 Cs-137 180 65.55 (1/1) Station 8 65.55 (1/1) <LLD 0 (243º, 0.9 ,mi)

Attachment to 0CAN041102 Page 32 of 57 TABLE 3.1 Radiological 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 2010 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Control Number of

( Units ) of Analyses a Mean ( F ) c Mean Locations Nonroutine

[ Range ] Mean ( F ) c Results e

[ Range ]

Location d Mean ( F ) c

[ 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 I-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; I-131 = Iodine-131; H-3 = Tritium; GS = 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.

Attachment to 0CAN041102 Page 33 of 57 ATTACHMENT 1 2010 Radiological Monitoring Report Summary of Monitoring Results

Attachment to 0CAN041102 Page 34 of 57 TABLE OF CONTENTS Table 1.1 Air Particulate 35 Table 1.2 Radioiodine Cartridge 36 Table 2.1 Thermoluminescent Dosimeters (Inner Ring) 37 Table 2.2 Thermoluminescent Dosimeters (Special Interest Areas) 38 Table 3.1 Surface Water (Gamma Isotopic) 39 Table 3.2 Surface Water (Tritium) 41 Table 4.1 Drinking Water (Gross beta, I-131 and Gamma Isotopic) 42 Table 4.2 Drinking Water (Tritium) 43 Table 5.1 Sediment 44 Table 6.1 Fish 45 Table 7.1 Food Products 46 Table 8.1 Groundwater Data (Gamma Isotopic) 47 Table 8.2 Groundwater Data (Tritium) 48

Attachment to 0CAN041102 Page 35 of 57 Table 1.1 Sample Type: Air Particulate Analysis: Gross Beta Units: pCi/m3 Start Date End Date Station 1

• Station 2 Station 56 Station 6 Station 7 (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 0.01 0.01 0.01 0.01 0.01 12/22/2009 01/05/2010 0.042 0.037 0.035 0.031 0.036 01/05/2010 01/19/2010 0.045 0.044 0.045 0.037 0.040 01/19/2010 02/02/2010 0.027 0.028 0.028 0.021 0.025 02/02/2010 02/16/2010 0.033 0.050 0.039 0.031 0.035 02/16/2010 03/02/2010 0.028 0.030 0.029 0.024 0.028 03/02/2010 03/16/2010 0.024 0.023 0.024 0.021 0.022 03/16/2010 03/30/2010 0.023 0.021 0.022 0.019 0.020 03/30/2010 04/13/2010 0.027 0.025 0.027 0.022 0.027 04/13/2010 04/27/2010 0.025 0.026 0.028 0.022 0.024 04/27/2010 05/11/2010 0.025 0.024 0.023 0.021 0.022 05/11/2010 05/25/2010 0.020 0.020 0.019 0.016 0.018 05/25/2010 06/08/2010 0.027 0.024 0.026 0.023 0.026 06/08/2010 06/22/2010 0.020 0.018 0.019 0.018 0.017 06/22/2010 07/06/2010 0.026 0.026 0.026 0.020 0.025 07/06/2010 07/20/2010 0.019 0.019 0.018 0.016 0.018 07/20/2010 08/03/2010 0.027 0.024 0.025 0.021 0.024 08/03/2010 08/17/2010 0.004 0.031 0.033 0.025 0.029 08/17/2010 08/31/2010 0.034 0.030 0.030 0.024 0.032 08/31/2010 09/14/2010 0.024 0.022 0.021 0.018 0.021 09/14/2010 09/28/2010 0.039 0.037 0.038 0.033 0.037 09/28/2010 10/12/2010 0.035 0.033 0.034 0.028 0.036 10/12/2010 10/26/2010 0.049 0.045 0.049 0.037 0.046 10/26/2010 11/09/2010 0.048 0.030 0.029 0.026 0.032 11/09/2010 11/23/2010 0.036 0.034 0.034 0.029 0.035 11/23/2010 12/07/2010 0.048 0.042 0.045 0.034 0.041 12/07/2010 12/21/2010 0.046 0.045 0.041 0.035 0.043

• Station with highest annual mean.

Attachment to 0CAN041102 Page 36 of 57 Table 1.2 Sample Type: Radioiodine Cartridge Analysis: Iodine-131 Units: pCi/m3 Start Date End Date Station 1 Station 2 Station 56 Station 6 Station 7 (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 0.07 0.07 0.07 0.07 0.07 12/22/2009 01/05/2010 <0.027 <0.023 <0.022 <0.023 <0.025 01/05/2010 01/19/2010 <0.021 <0.020 <0.018 <0.015 <0.020 01/19/2010 02/02/2010 <0.018 <0.017 <0.017 <0.019 <0.018 02/02/2010 02/16/2010 <0.022 <0.030 <0.017 <0.019 <0.020 02/16/2010 03/02/2010 <0.022 <0.021 <0.024 <0.022 <0.025 03/02/2010 03/16/2010 <0.023 <0.023 <0.020 <0.018 <0.021 03/16/2010 03/30/2010 <0.018 <0.022 <0.020 <0.014 <0.019 03/30/2010 04/13/2010 <0.019 <0.021 <0.017 <0.018 <0.020 04/13/2010 04/27/2010 <0.022 <0.018 <0.017 <0.015 <0.024 04/27/2010 05/11/2010 <0.025 <0.023 <0.025 <0.021 <0.027 05/11/2010 05/25/2010 <0.022 <0.018 <0.022 <0.025 <0.020 05/25/2010 06/08/2010 <0.020 <0.017 <0.019 <0.019 <0.014 06/08/2010 06/22/2010 <0.022 <0.020 <0.016 <0.018 <0.022 06/22/2010 07/06/2010 <0.021 <0.017 <0.015 <0.016 <0.018 07/06/2010 07/20/2010 <0.025 <0.018 <0.018 <0.017 <0.021 07/20/2010 08/03/2010 <0.015 <0.018 <0.017 <0.019 <0.017 08/03/2010 08/17/2010 <0.021 <0.018 <0.022 <0.017 <0.018 08/17/2010 08/31/2010 <0.025 <0.018 <0.022 <0.025 <0.023 08/31/2010 09/14/2010 <0.017 <0.018 <0.018 <0.019 <0.017 09/14/2010 09/28/2010 <0.017 <0.016 <0.018 <0.018 <0.015 09/28/2010 10/12/2010 <0.019 <0.016 <0.018 <0.019 <0.014 10/12/2010 10/26/2010 <0.022 <0.015 <0.015 <0.016 <0.019 10/26/2010 11/09/2010 <0.019 <0.014 <0.014 <0.017 <0.012 11/09/2010 11/23/2010 <0.021 <0.018 <0.019 <0.017 <0.015 11/23/2010 12/07/2010 <0.016 <0.019 <0.021 <0.014 <0.021 12/07/2010 12/21/2010 <0.058 <0.058 <0.054 <0.043 <0.061

Attachment to 0CAN041102 Page 37 of 57 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators)

Station 1st Qtr 10 2nd Qtr 10 3rd Qtr 10 4th Qtr 10 Annual Mean (mrem) (mrem) (mrem) (mrem) 10 (mrem) 3 5.6 6.3 5.5 7.1 6.1 145 7.0 8.2 7.7 9.1 8.0 146 7.2 8.7 8.2 9.6 8.4 147 5.5 6.9 6.9 8.2 6.9 1 7.7 8.9 7.8 10.1 8.6 148 Missing 8.2 8.1 9.1 8.5 110 7.3 8.1 8.3 9.3 8.3 149 6.8 7.5 7.4 9.4 7.8 4 6.7 8.2 7.5 9.1 7.9 150 7.9 9.6 8.5 10.5 9.1 151 6.9 8.9 8.5 9.5 8.5 2 7.7 8.6 7.8 9.9 8.5 56

• 9.9 9.4 9.7 11.1 10.0 109 8.4 8.8 9.6 10.0 9.2 108 8.2 8.7 8.8 9.9 8.9 152 6.1 7.1 7.1 7.8 7.0

• Station with highest annual mean.

Attachment to 0CAN041102 Page 38 of 57 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr 10 2nd Qtr 10 3rd Qtr 10 4th Qtr 10 Annual Mean (mrem) (mrem) (mrem) (mrem) 10 (mrem) 6 7.3 6.8 6.7 8.0 7.2 111 4.9 5.4 5.8 6.3 5.6 116

• 7.2 8.7 9.1 9.2 8.6 125 4.6 6.0 4.6 5.9 5.3 127 7.7 8.3 8.4 9.5 8.5 137 7.5 8.7 8.1 9.8 8.5 153 7.1 7.7 8.2 8.8 8.0

• Stations with highest annual mean.

Special Interest Areas - (Control)

Station 1st Qtr 10 2nd Qtr 10 3rd Qtr 10 4th Qtr 10 Annual (mrem) (mrem) (mrem) (mrem) Mean 10 (mrem) 7 6.3 6.3 6.8 8.3 6.9

Attachment to 0CAN041102 Page 39 of 57 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Required LLD 15 15 30 15 30 15 30 15 15 18 60 15 Station 8 (Indicator) 12/31/2009 01/31/2010 <3.65 <4.70 <8.59 <4.12 <10.31 <6.03 <7.57 <9.70 <4.83 <4.25 <21.99 <8.70 Station 10 (Control) 12/31/2009 01/31/2010 <3.86 <3.68 <7.34 <4.49 <8.98 <6.16 <6.49 <8.79 <4.56 <4.38 <21.08 <6.75 Station 8 (Indicator) 01/31/2010 02/28/2010 <2.24 <4.70 <7.54 <3.68 <6.55 <4.33 <7.38 <8.88 <4.93 <3.92 <21.77 <7.02 Station 10 (Control) 01/31/2010 02/28/2010 <4.47 <4.71 <9.95 <4.37 <9.73 <7.50 <8.34 <11.21 <5.52 <4.91 <27.69 <8.52 Station 8 (Indicator) 02/28/2010 03/31/2010 <6.06 <6.99 <17.90 <5.46 <14.49 <10.97 <11.31 <13.23 <7.73 <8.27 <36.70 <10.86 Station 10 (Control) 02/28/2010 03/31/2010 <3.94 <4.30 <8.09 <2.31 <8.15 <5.65 <6.04 <7.19 <4.15 <3.90 <17.15 <6.63 Station 8 (Indicator) 03/31/2010 04/30/2010 <3.71 <2.89 <6.24 <3.65 <7.10 <3.78 <5.76 <4.83 <2.99 <3.42 <13.07 <5.26 Station 10 (Control) 03/31/2010 04/30/2010 <3.81 <3.66 <7.23 <3.83 <8.03 <4.30 <6.60 <6.86 <3.80 <3.95 <17.76 <5.90 Station 8 (Indicator) 04/30/2010 05/31/2010 <4.86 <6.80 <10.84 <6.53 <10.21 <6.25 <7.98 <9.28 <6.63 <5.68 <30.16 <10.57 Station 10 (Control) 04/30/2010 05/31/2010 <4.68 <6.01 <12.57 <5.07 <9.87 <6.24 <10.18 <9.42 <5.83 <5.97 <33.37 <12.11 Station 8 (Indicator) 05/31/2010 06/30/2010 <3.65 <4.03 <6.59 <3.64 <6.56 <4.16 <6.09 <6.13 <4.05 <4.00 <20.56 <7.30 Station 10 (Control) 05/31/2010 06/30/2010 <3.21 <3.08 <7.50 <2.66 <7.05 <4.18 <7.00 <6.05 <3.85 <3.43 <15.40 <3.66

Attachment to 0CAN041102 Page 40 of 57 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Required LLD 15 15 30 15 30 15 30 15 15 18 60 15 Station 8 (Indicator) 06/30/2010 07/31/2010 <5.61 <5.63 <8.93 <5.42 <13.83 <4.91 <7.09 <11.78 <5.37 <5.13 <23.65 <10.27 Station 10 (Control) 06/30/2010 07/31/2010 <6.73 <6.34 <15.24 <6.60 <11.07 <10.66 <13.70 <14.95 <7.64 <6.90 <34.38 <14.23 Station 8 (Indicator) 07/31/2010 08/31/2010 <3.86 <4.95 <8.34 <4.46 <9.74 <6.40 <8.58 <8.77 <5.16 <4.46 <27.58 <8.98 Station 10 (Control) 07/31/2010 08/31/2010 <4.24 <4.83 <5.47 <3.67 <6.76 <4.96 <8.43 <8.37 <4.19 <3.62 <21.92 <6.78 Station 8 (Indicator) 08/31/2010 09/30/2010 <3.98 <3.67 <9.06 <3.72 <11.79 <5.05 <6.37 <7.60 <4.72 <4.43 <22.18 <7.22 Station 10 (Control) 08/31/2010 09/30/2010 <4.84 <5.27 <8.52 <3.34 <9.29 <6.76 <8.99 <8.37 <4.93 <4.17 <23.50 <7.24 Station 8 (Indicator) 09/30/2010 10/31/2010 <4.73 <4.79 <6.46 <4.63 <7.07 <6.46 <8.15 <6.45 <4.29 <4.51 <15.42 <4.63 Station 10 (Control) 09/30/2010 10/31/2010 <3.95 <4.51 <7.94 <3.87 <9.39 <4.76 <8.11 <6.61 <4.52 <4.53 <16.72 <5.42 Station 8 (Indicator) 10/31/2010 11/30/2010 <4.36 <4.53 <7.31 <3.41 <9.10 <5.54 <6.51 <7.20 <3.79 <4.68 <22.78 <6.86 Station 10 (Control) 10/31/2010 11/30/2010 <2.93 <3.41 <7.68 <3.20 <6.64 <4.36 <5.43 <5.98 <3.45 <3.91 <16.58 <6.55 Station 8 (Indicator) 11/30/2010 12/31/2010 <5.60 <6.34 <7.63 <3.48 <10.70 <6.73 <9.31 <12.29 <5.41 <4.14 <25.47 <13.37 Station 10 (Control) 11/30/2010 12/31/2010 <4.20 <3.98 <8.00 <4.17 <9.91 <5.59 <8.35 <11.22 <3.70 <4.64 <26.93 <6.50

Attachment to 0CAN041102 Page 41 of 57 Table 3.2 Sample Type: Surface Water Analysis: Tritium Units: pCi/l Location Begin Date End Date H-3 Required LLD 3000 Station 8 (Indicator) 12/31/2009 03/31/2010 985 Station 10 (Control) 12/31/2009 03/31/2010 < 462 Station 8 (Indicator) 03/31/2010 06/30/2010 601 Station 10 (Control) 03/31/2010 06/30/2010 < 540 Station 8 (Indicator) 06/30/2009 09/30/2010 < 421 Station 10 (Control) 06/30/2010 09/30/2010 < 425 Station 8 (Indicator) 09/30/2010 12/31/2010 565 Station 10 (Control) 09/30/2010 12/31/2010 < 449

Attachment to 0CAN041102 Page 42 of 57 Table 4.1 Sample Type: Drinking Water Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Units: pCi/l Location Collection Gross I-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 Required LLD 4.0 1.0 15 30 15 15 30 30 15 15 18 60 15 Station 14 (Indicator) 03/16/2010 2.30 <0.70 <4.15 <9.37 <4.30 <4.44 <9.79 <7.06 <6.22 <4.29 <6.20 <21.77 <9.88 Station 57 (Control) 03/16/2010 3.36 <0.94 <8.11 <14.75 <8.34 <7.69 <16.52 <13.86 <9.64 <9.40 <8.59 <36.98 <12.95 Station 14 (Indicator) 06/29/2010 1.81 <0.89 <4.96 <11.99 <5.46 <3.97 <11.51 <8.84 <6.37 <4.90 <3.81 <19.29 <10.28 Station 57 (Control) 06/29/2010 2.67 <0.84 <6.09 <14.44 <4.95 < 4.64 <8.67 <12.44 <8.34 <5.72 <7.20 <26.87 <10.34 Station 14 (Indicator) 09/14/2010 0.63 <0.83 <2.96 <10.26 <4.19 <3.47 <8.46 <6.68 <4.53 <4.79 <4.88 <30.34 <13.48 Station 57 (Control) 09/14/2010 2.12 <0.82 <5.97 <10.57 <5.71 <5.35 <10.40 <8.89 <9.79 <5.21 <4.63 <41.61 <12.09 Station 14 (Indicator) 12/07/2010 1.47 <0.79 <3.60 <11.35 <6.01 <4.21 <10.45 <9.34 <7.31 <5.36 <4.80 <36.78 <8.66 Station 57 (Control) 12/07/2010 2.90 <0.84 <4.55 <10.15 <5.00 <4.83 <13.29 <9.79 <7.68 <6.13 <5.80 <28.10 <9.80

Attachment to 0CAN041102 Page 43 of 57 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 2000 Station 14 (Indicator) 03/16/2010 <466 Station 57 (Control) 03/16/2010 <465 Station 14 (Indicator) 06/29/2010 <543 Station 57 (Control) 06/29/2010 <540 Station 14 (Indicator) 09/14/2010 <431 Station 57 (Control) 09/14/2010 <432 Station 14 (Indicator) 12/07/2010 <422 Station 57 (Control) 12/07/2010 <394

Attachment to 0CAN041102 Page 44 of 57 Table 5.1 Sample Type: Sediment Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Cs-134 Cs-137 Required LLD 150 180 Station 8 (Indicator) 9/15/2010 <116.25 65.55 Station 16 (Control) 9/15/2010 <82.79 <63.21

Attachment to 0CAN041102 Page 45 of 57 Table 6.1 Sample Type: Fish Analysis: Gamma Isotopic Units: pCi/kg Location Collection Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Date Required LLD 130 260 130 130 260 130 150 Station 8 (Indicator) 9/09/2010 <18.22 <128.00 <37.69 <16.93 <42.16 <11.40 <14.04 Station 16 (Control) 9/07/2010 <15.07 <114.35 <28.32 <19.00 <46.16 <15.12 <11.99

Attachment to 0CAN041102 Page 46 of 57 Table 7.1 Sample Type: Food Products Analysis: Iodine-131 and Gamma Isotopic Units: pCi/kg Location Collection Date I-131 Cs-134 Cs-137 Required LLD 60 60 80 Station 13 (Indicator) 06/29/2010 < 58.76 < 34.58 < 37.99 Station 55 (Control) 06/29/2010 < 59.00 < 33.40 < 33.39 Station 13 (Indicator) 07/21/2010 < 55.98 < 40.05 < 47.89 Station 55 (Control) 07/21/2010 < 58.57 < 44.79 < 58.84 Station 13 (Indicator) 08/25/2010 < 59.86 < 48.41 < 40.80 Station 55 (Control) 08/25/2010 < 58.49 < 56.05 < 43.08

Attachment to 0CAN041102 Page 47 of 57 Table 8.1 Sample Type: Groundwater Analysis: Iodine-131 and Gamma Isotopic Units: pCi/l Sample Collection I-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140

1. Date Required LLD 15 15 30 15 15 30 30 15 15 18 60 15 58* 01/27/201

< 4.88 < 13.48 < 5.28 <2.92 < 13.64 < 5.77 < 7.24 < 6.40 < 5.18 < 30.29 < 13.28 0 < 12.62 59 01/27/201

< 3.97 < 16.34 < 6.05 < 4.74 < 10.18 < 8.49 < 6.83 < 4.84 < 4.80 < 36.47 < 7.85 0 < 14.66 60 01/27/201 <10.3

< 5.43 0 < 13.82 < 12.58 < 5.66 < 3.35 < 9.44 3 < 5.87 < 4.40 < 4.56 < 33.61 < 12.43 61 01/27/201

< 4.28 < 7.10 < 4.41 < 3.48 < 10.96 < 8.52 < 5.47 < 5.48 < 6.05 < 32.66 < 8.93 0 < 11.26 58* 05/18/201

< 1.53 < 1.21 < 2.92 < 2.90 < 2.01 < 1.26 < 1.31 < 19.64 < 7.28 0 < 14.96 < 1.31 < 3.67 59 05/18/201

< 1.29 < 3.33 < 1.50 < 1.31 < 2.76 < 2.93 < 2.29 < 1.39 < 1.32 < 21.87 < 7.49 0 < 14.82 60 05/18/201 0 < 15.00 < 1.15 < 3.56 < 1.50 < 1.18 < 2.46 < 2.74 < 2.19 < 1.22 < 1.24 < 19.03 < 7.44 61 05/18/201

< 1.89 < 5.28 < 2.15 < 1.80 < 4.22 < 4.08 < 3.43 < 2.01 < 1.88 < 30.12 < 11.20 0 < 13.69 58* 08/17/201

< 4.89 < 9.94 < 5.53 < 4.64 < 10.20 < 9.84 < 7.42 < 4.88 < 5.01 < 33.06 < 10.84 0 < 14.16 59 08/17/201 <11.2 0 < 13.35 < 4.98 < 9.81 < 4.97 <1.84 < 11.88 1 < 7.61 < 5.60 < 5.33 < 28.92 < 10.98 60 08/17/201

< 3.44 < 11.19 < 5.50 < 4.58 < 10.11 < 8.47 < 4.72 < 5.09 < 3.48 < 27.32 < 10.68 0 < 14.19

Attachment to 0CAN041102 Page 48 of 57 61 08/17/201 0 < 12.52 < 3.95 < 8.36 < 4.91 < 5.53 < 9.96 < 7.29 < 6.64 < 5.24 < 4.12 < 27.93 < 12.17 58* 11/02/201

< 4.39 < 8.81 < 2.77 < 4.07 < 8.08 < 7.01 < 4.82 < 4.33 < 3.65 < 20.88 < 8.93 0 < 9.75 59 11/02/201 0 < 6.13 < 3.91 < 7.22 < 3.84 < 3.65 < 7.01 < 5.74 < 5.17 < 3.58 < 2.89 < 15.77 < 6.63 60 11/02/201

< 5.27 < 10.81 < 5.35 < 4.56 < 10.34 < 7.50 < 7.72 < 5.06 < 4.76 < 25.51 < 9.83 0 < 9.61 61 11/02/201

< 3.39 < 5.26 < 3.33 < 3.79 < 7.06 < 6.58 < 3.85 < 3.35 < 3.08 < 17.68 < 6.76 0 < 6.76

• Identifies Control Locations

Attachment to 0CAN041102 Page 49 of 57 Table 8.2 Sample Type: Groundwater Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 3000 Station 58 (Control) 01/27/2010 < 549 Station 59 (Indicator 01/27/2010 < 526 Station 60 (Indicator) 01/27/2010 < 529 Station 61 (Indicator) 01/27/2010 < 523 Station 58 (Control) 05/18/2010 < 501 Station 59 (Indicator) 05/18/2010 < 496 Station 60 (Indicator) 05/18/2010 < 498 Station 61 (Indicator) 05/18/2010 < 500 Station 58 (Control) 08/17/2010 < 437 Station 59 (Indicator) 08/17/2010 < 430 Station 60 (Indicator) 08/17/2010 < 433 Station 61 (Indicator) 08/17/2010 < 455 Station 58 (Control) 11/02/2010 < 419 Station 59 (Indicator) 11/02/2010 < 424 Station 60 (Indicator) 11/02/2010 < 418 Station 61 (Indicator) 11/02/2010 < 421

Attachment to 0CAN041102 Page 50 of 57 ATTACHEMENT 2 Interlaboratory Comparison Program

Attachment to 0CAN041102 Page 51 of 57 Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Calendar Year: 2010 1st Quarter dated March 18, 2010 Analytics Gamma Range of E7024-125 in Water 0.80 to 1.25 Nuclide RBS RBS 1-s* Ref Lab Ref Lab Resolution RBS/Ref Pass Mean pCi/L Value Uncertainty Lab Ratio /

pCi/L pCi/L pCi/L Fail I-131 74.9 5.30 72.2 1.21 59.7 1.04 Pass Ce-141 268 7.10 263 4.40 59.8 1.02 Pass Cr-51 418 1.66 364 6.08 59.9 1.15 Pass Cs-134 182 4.80 179 2.99 59.9 1.02 Pass Cs-137 168 5.20 159 2.66 59.8 1.06 Pass Co-58 145 6.30 144 2.40 60.0 1.01 Pass Mn-54 222 5.60 209 3.49 59.9 1.06 Pass Fe-59 151 8.70 138 2.31 59.7 1.09 Pass Zn-65 266 9.80 256 4.27 60.0 1.04 Pass Co-60 185 4.60 185 3.08 60.1 1.00 Pass Analytics Gross Range of E7025-125 Beta in 0.80 to 1.25 Water Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass Mean pCi/L Value uncertainty Lab Ratio /

pCi/L pCi/L pCi/L Fail Cs-137 270 9.90 260 4.35 59.8 1.04 Pass Analytics I-131 Range of E7026-125 cartridge 0.80 to 1.25 Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass Mean pCi/eac Value uncertainty Lab Ratio /

pCi/each h pCi/each pCi/each Fail I-131 84.5 3.70 85.6 1.43 59.9 0.99 Pass

• 1-s = one sigma

Attachment to 0CAN041102 Page 52 of 57 Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Tritium and Gamma Isotopic Analytics Gamma Range of E7027-125 in Milk 0.80 to 1.25 Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass Mean pCi/L Value uncertainty Lab Ratio /

pCi/L pCi/L pCi/L Fail I-131 75.7 2.80 74.0 1.24 59.7 1.02 Pass Ce-141 257 5.20 261 4.36 59.9 0.98 Pass Cr-51 364 17.7 361 6.03 59.9 1.01 Pass Cs-134 176 1.40 178 2.97 59.9 0.99 Pass Cs-137 163 6.00 158 2.64 59.8 1.03 Pass Co-58 142 1.00 143 2.38 60.1 0.99 Pass Mn-54 209 9.20 207 3.46 59.8 1.01 Pass Fe-59 154 0.80 137 2.29 59.8 1.12 Pass Zn-65 256 9.40 254 4.24 59.9 1.01 Pass Co-60 176 10.2 183 3.06 59.8 0.96 Pass

Attachment to 0CAN041102 Page 53 of 57 Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Gamma Isotopic Calendar Year: 2010 *2nd Quarter dated June 17, 2010

• • 3rd Quarter dated Sept. 16, 2010 Analytics Gross Range of E7111-125* Beta 0.80 to filter 1.25 Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass/

Mean pCi/filter Value uncertainty Lab Ratio Fail pCi/filter pCi/filter pCi/filter Cs-137 60.5 0.33 54.0 0.902 59.9 1.12 Pass Analytics H-3 Range of E7255-125 in water 0.80 to

• • 1.25 Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass/

Mean pCi/L Value uncertainty Lab Ratio Fail pCi/L pCi/L pCi/L H-3 3568 224.5 4020 67.2 59.8 0.89 Pass Analytics Gamma Range of E7256-125 Filter 0.80 to

• • 1.25 Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass/

Mean pCi/filter Value Uncertainty Lab Ratio Fail pCi/filter pCi/filter pCi/filter Ce-141 101.6 3.6 99.5 1.66 59.9 1.02 Pass Cr-51 173.0 16.4 179 2.98 60.1 0.97 Pass Cs-134 71.8 3.5 71.1 1.19 59.7 1.01 Pass Cs-137 75.7 2.5 72.2 1.21 59.7 1.05 Pass Co-58 59.1 2.2 56.3 0.940 59.9 1.05 Pass Mn-54 99.8 3.8 91.3 1.52 60.1 1.09 Pass Fe-59 79.8 1.3 69.7 1.16 60.1 1.14 Pass Zn-65 158.2 11.4 156 2.60 60.0 1.01 Pass Co-60 132.3 1.3 130 2.18 59.6 1.02 Pass

Attachment to 0CAN041102 Page 54 of 57 Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Gamma Isotopic Analytics Gamm Range of E7257-125 a Soil 0.80 to

• • 1.25 Nuclide RBS RBS 1-s Ref Lab Ref Lab Resolution RBS/Ref Pass/

Mean pCi/g Value Uncertainty Lab Ratio Fail pCi/g pCi/g pCi/g Ce-141 0.478 0.012 0.486 0.00812 59.9 0.98 Pass Cr-51 0.848 0.031 0.872 0.0146 59.7 0.97 Pass Cs-134 0.325 0.026 0.347 0.00579 59.9 0.94 Pass Cs-137 0.465 0.003 0.443 0.00740 59.9 1.05 Pass Co-58 0.270 0.009 0.275 0.00459 59.9 0.98 Pass Mn-54 0.445 0.015 0.446 0.00745 59.9 1.00 Pass Fe-59 0.350 0.015 0.340 0.00568 59.9 1.03 Pass Zn-65 0.778 0.014 0.761 0.0127 59.9 1.02 Pass Co-60 0.637 0.011 0.638 0.0107 59.6 1.00 Pass CHEMISTRY SURVEILLANCE PROGRAM RADIOCHEMISTRY QUALITY CONTROL ACCEPTANCE CRITERIA This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.

In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratorys value to its associated uncertainty. As that ratio, referred to in this program as Resolution, increases the acceptability of a licensees measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases.

RESOLUTION (1) RATIO FOR AGREEMENT (2)

<4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 51 to 200 0.80 to 1.25

>200 0.85 to 1.18 (1)

Resolution = (NRC Reference Value/Reference Uncertainty)

(2)

Ratio = (Licensee Value/NRC Reference Value)

Attachment to 0CAN041102 Page 55 of 57 Interlaboratory Comparison Program Summary RBS Environmental Laboratory analyzed interlaboratory comparison samples to fulfill the requirements of the ODCM. The interlaboratory comparison results indicated that 100% of the sample results for accuracy and precision were within the acceptable control limits.

Attachment to 0CAN041102 Page 56 of 57 ATTACHMENT 3 Sediment Dose Calculations

Attachment to 0CAN041102 Page 57 of 57 Sediment Dose Calculations Sediment Sample Results Dose calculation for the discharge sediment was performed using generalized equation found in Regulatory Guide 1.109, Revision 1, 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/m2; C = 2010 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/m2, and W = Shore-width factor (0.1) given in Table A-2 of Regulatory Guide 1.109.

(Dose from Sediment in mrem/Year)

Radionuclide 2010 Conversion Total Conversion Total Maximum Factor Skin Dose Factor Body Dose Concentration For Skin For Total Body Cs-137 65.55 4.90 E-09 8.61 E-05 4.20 E-09 7.38 E-05 TOTAL 8.61 E-05 7.38 E-05