0CAN050803, ISFSI - Annual Radiological Environmental Operating Report for 2007

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ISFSI - Annual Radiological Environmental Operating Report for 2007
ML081340273
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 05/08/2008
From: James D
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
0CAN050803
Download: ML081340273 (52)
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Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Nuclear Safety Assurance Arkansas Nuclear One 0CAN050803 May 8, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Annual Radiological Environmental Operating Report for 2007 Arkansas Nuclear One, Units 1 and 2 Docket Nos. 50-313, 50-368, and 72-13 (ISFSI)

License Nos. DPR-51 and NPF-6 REFERNCES: 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 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 2007.

This report fulfills the reporting requirements referenced above.

The radionuclides detected by the radiological environmental monitoring program during 2007 were significantly below regulatory limits. The operation of the ANO station during 2007 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 2007 results did not require any Radiological Monitoring Program Special Reports.

This submittal contains no commitments.

0CAN050803 Page 2 of 2 Should you have any questions regarding this report, please contact me.

Sincerely, Dale E. James Manager, Licensing DEJ/rwc

Attachment:

Annual Radiological Environmental Operating Report for 2007 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. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437

Attachment 0CAN050803 Annual Radiological Environmental Operating Report for 2007

Attachment to 0CAN050803 Page 1 of 49 ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2007

Attachment to 0CAN050803 Page 2 of 49 TABLE OF CONTENTS

SUMMARY

7

1.0 INTRODUCTION

10 1.1 Radiological Environmental Monitoring Program 10 1.2 Pathways Monitored 10 1.3 Land Use Census 11 2.0 INTERPRETATION AND TRENDS OF RESULTS 21 2.1 Air Particulate and Radioiodine Sample Results 21 2.2 Thermoluminescent Dosimetry Sample Results 21 2.3 Water Sample Results 22 2.4 Sediment Sample Results 23 2.5 Milk Sample Results 23 2.6 Fish Sample Results 23 2.7 Food Product Sample Results 24 2.8 Land Use Census Results 24 2.9 Interlaboratory Comparison Results 24 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

27 3.1 2007 Program Results Summary 27

Attachment to 0CAN050803 Page 3 of 49 LIST OF TABLES TABLE 1.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM 12 TABLE 2.1 2007 LAND USE CENSUS 25 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

28

Attachment to 0CAN050803 Page 4 of 49 LIST OF FIGURES FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD 19 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 20 FIGURE 2-1 TLD RADIATION DOSE 26

Attachment to 0CAN050803 Page 5 of 49 LIST OF ATTACHMENTS ATTACHMENT 1 2007 RADIOLOGICAL MONITORING REPORT

SUMMARY

OF MONITORING RESULTS 32 ATTACHMENT 2 INTERLABORATORY COMPARISON PROGRAM 44 ATTACHMENT 3 SEDIMENT DOSE CALCULATIONS 48

Attachment to 0CAN050803 Page 7 of 49 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, 2007 through December 31, 2007. This report fulfills the requirements of ANO Unit 1 Technical Specification 5.6.2 and Unit 2 Technical Specification 6.6.2.

During 2007 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 2007 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.

In 2007, 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 2007 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.

Attachment to 0CAN050803 Page 8 of 49 Harmful Effects or Irreversible Damage The REMP monitoring did not detect any harmful effects or evidence of irreversible damage in 2007. 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, 2007 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 dosimtery (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.

Sample Deviations

  • Milk The REMP did not include milk sampling within five miles (8 km) of ANO in 2007 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.

Attachment to 0CAN050803 Page 9 of 49

  • 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 2007 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 56 12/21/06 - 01/02/07 Pump found not running. Out of service pump was replaced with a new pump.

2 02/20/07 - 03/06/07 Air sample station totalizer not operating. Sample pump running. Totalizer reset and started.

2 03/06/07 - 03/20/07 Air sample station totalizer not operating.

Totalizer replaced 56 04/17/07 - 05/01/07 Air sample station totalizer not operating. Electric motor volume totalizer was replaced with digital volume totalizer.

  • Missed Samples One first quarter TLD (Station 148) was discovered missing on April 11, 2007 due to the road sign post being removed. The second quarter TLD was placed into service by ANO personnel once discovered. This loss was an isolated instance that did not recur during the year. The recovery rate for TLDs during 2007 was 99% (95 of 96).

After deploying the second quarter environmental TLDs, it was discovered that the deployed set had received a significant transit dose. This dose proved to render the deployed TLDs useless and replacements were sent to ANO by the vendor. This event contributed to a period of 14 days where the direct radiation pathway was not monitored between the removal of the first quarter TLDs and the deployment of the replacement second quarter TLDs.

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

Attachment to 0CAN050803 Page 10 of 49 Program Modifications ANO made no modifications to the REMP during 2007.

Attachments contains results of air, TLD, water, sediment, fish, and food product samples collected in 2007. TLDs were analyzed by vendor (AREVA). All remaining samples were analyzed by River Bend Stations (RBS) Environmental Laboratory. also contains RBS participation in the interlaboratory comparison program during 2007. 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.

1.0 IINTRODUCTION 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 2007 sampling results and Section 3.0 provides a summary of results for the monitored exposure pathways.

Attachment to 0CAN050803 Page 11 of 49 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 fresh leafy (broadleaf) vegetables
  • 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.
  • 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 0CAN050803 Page 12 of 49 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 Radioiodine and Particulates 2 samples close to the Site Station 2 (243° - 0.5 miles) - Continuous operation of Radioiodine Canister -

Boundary, in (or near) different South of the sewage treatment sampler with sample Analyze at least once sectors with the highest plant. collection as required by per 14 days for I-131.

calculated annual average ground dust loading but at least level D/Q. Station 56 (264° - 0.4 miles) - once per 14 days. Particulate Sampler -

West end of the sewage treatment Analyze for gross beta plant. radioactivity following filter change.

Radioiodine and Particulates 1 sample from the vicinity of a Station 6 (111° - 6.8 miles) -

community having the highest Entergy local office in Russellville calculated annual average (305 South Knoxville Avenue).

groundlevel D/Q.

Radioiodine and Particulates 1 sample from a control location Station 7 (210° - 19.0 miles) -

15-30 km (10 - 20 miles) Entergy Supply Yard on Highway distance. 10 in Danville.

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

Attachment to 0CAN050803 Page 13 of 49 Table 1.1 (continued)

Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct Thermoluminescent dosimetry Radiation (TLDs) 16 inner ring stations with two or Station 1 (88° - 0.5 miles) - On a Once per 92 days. Gamma Dose - Once more dosimeters in each pole near the meteorology tower. per 92 days.

meteorological sector 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 #2 on Highway 333 (approximately 0.35 miles)

Station 4 (181° - 0.5 miles) -

West of May Cemetery entrance on south side of the road.

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.

Attachment to 0CAN050803 Page 14 of 49 Table 1.1 (continued)

Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs (continued)

Radiation Station 110 (138° - 0.8 miles) -

(continued) 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.

Station 149 (156° - 0.5 miles) -

On a utility pole on the south side of May Road.

Attachment to 0CAN050803 Page 15 of 49 Table 1.1 (continued)

Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs (continued)

Radiation Station 150 (205° - 0.6 miles) -

(continued) 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 (continued) Station 6 (111° - 6.8 miles) -

8 stations with two or more Entergy local office in Russellville dosimeters in special interest (305 South Knoxville Avenue).

areas such as population centers, nearby residences, schools, and Station 7 (210° - 19.0 miles) -

in 1 - 2 areas to serve as control Entergy Supply Yard on Highway locations. 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 0CAN050803 Page 16 of 49 Table 1.1 (continued)

Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs (continued) Station 125 (46° - 8.7 miles) -

Radiation College Street on a utility pole at (continued) the southeast corner of the red brick school building.

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 Station 8 (166° - 0.2 miles) - Once per 92 days. Gamma isotopic and plant discharge) Plant discharge canal. tritium analyses once per 92 days.

1 control location (uninfluenced by Station 10 (95° - 0.5 miles) -

plant discharge) Plant intake canal.

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

1 control location (uninfluenced by Station 57 (208° - 19.5 miles) -

plant discharge) Danville public water supply treatment on Fifth Street.

Attachment to 0CAN050803 Page 17 of 49 Table 1.1 (continued)

Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Waterborne Sediment (continued) 1 indicator location (influenced by Station 8 (243° - 0.9 miles) - Once per 365 days. Gamma isotopic plant discharge) Plant discharge canal. analysis once per 365 days.

1 control location (uninfluenced by Station 16 (287° - 5.5 miles) -

plant discharge) Panther Bay on south side of Arkansas River across from mouth of Piney Creek.

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

1 control sample location at a distance of > 8 km, (five-miles) when an indicator exists.

Fish 1 sample of commercially and/or Station 8 (212° - 0.5 miles) - Once per 365 days. Gamma isotopic on recreationally important species in Plant discharge canal. edible portions once per vicinity of plant discharge. 365 days.

1 sample of same species in area Station 16 (287° - 5.5 miles) -

not influenced by plant discharge. Panther Bay on south side of Arkansas River across from mouth of Piney Creek.

Attachment to 0CAN050803 Page 18 of 49 Table 1.1 (continued)

Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Ingestion Food Products (continued) 1 sample of broadleaf (edible or Station 13 (273° - 0.5 miles) - Three per 365 days. Gamma isotopic and non-edible) near the Site West from ANO toward Gate 4 I-131 analyses three Boundary from one of the highest onto Flatwood Road. times per 365 days.

anticipated annual average groundlevel D/Q sectors, if milk sampling is not performed.

1 sample location of broadleaf Station 55 (208° - 16.5 miles) -

vegetation (edible or non-edible) Intersection of Highway 27 and from a control location 15 - 30 km 154.

(10 - 20 miles) distant, if milk sampling is not performed.

Attachment to 0CAN050803 Page 19 of 49 FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD SR 333 152 3 108 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 0CAN050803 Page 20 of 49 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 A 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 0CAN050803 Page 21 of 49 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 2007, 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 2007 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/m3.

Monitoring Period Result 2000 - 2006 (Minimum Value) 0.020 2007 Value 0.029 2000 - 2006 (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 (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 7.51 mrem shown in Table 3.1 is within the historical bounds of 2000 - 2006 annual average results, which have ranged from 6.7 to 8.8 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. ANOs comparison of the results to the control indicates that the ambient radiation levels are unaffected by plant operations.

Although the third quarter readings for TLD Stations 1, 2, 56, 108, 109 and 151 shown in Figure 2-1 was above the upper (+) three standard deviation range value of 9.7 mrem for the historical maximum control location, ANO considers the difference to be insignificant since.the dose rates remain well below the limitations of 10 CFR 20.1301(a)(1) and 10 CFR 20.1302(b)(2)(ii), and since there has been no identifiable trends associated with these stations. In addition, ANO utilized a different vendor for TLD processing in 2007. Therefore, these increases can also be attributed to differences in dosimeter processing.

Attachment to 0CAN050803 Page 22 of 49 Overall, ANO concluded that the ambient radiation levels are not being affected by plant operations.

2.3 Water Sample Results Analytical results for 2007 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 - 2006 (Minimum Value) 272.0 2007 Value 660.3 2000 - 2006 (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 2007 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 2007 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 Lower Level of Detection (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 2007 indicator results to preoperational and operational years. Results are reported as annual average pCi/l.

Radionuclide 2007 2000 - 2006 Preoperational Gross Beta 5.58 3.54 2.0 Iodine-131 < LLD < LLD < LLD Gammas < LLD < LLD < LLD Tritium < LLD < LLD 200.0

Attachment to 0CAN050803 Page 23 of 49 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 2007 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 2007 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 2007 were actually below the minimum range of previous operational levels as seen below. Results are reported as annual average pCi/kg.

Monitoring Period Concentration 2000 - 2006 (Minimum Value) 97.78 2007 Value 67.41 2000 - 2006 (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 2007 had no significant impact on the environment or public by this waterborne pathway.

2.5 Milk Sample Results Milk samples were not collected during 2007 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 2007, 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.

Attachment to 0CAN050803 Page 24 of 49 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 2007, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2007 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 The land use census did not identify any new locations during the September 2007 survey 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 2007, which is allowed by ANO Units 1 and 2 ODCM Section 2.6.2, in lieu of broadleaf vegetation sampling in the meteorological sector (Sector 13) with the highest D/Q.

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, 2007 Radiological Environmental Monitoring Report, contains these results. ANOs review of RBS interlaboratory comparison indicated that 98% of the sample results (40 of 41) for accuracy and precision were within the acceptable control limits of the three normalized deviations.

There was one result outside the control limits for accuracy in the 2007 Interlaboratory Comparison program participation studies. The RBS normalized-deviation for nuclide Mn-54 in a gamma isotopic water analysis, analytics sample number E5388-125 of 6/14/2007, was +3.89, which is outside the control limit of +/-3.00 for accuracy. ANOs and RBS review indicated no impact on previously reported data. Attachment 2 provides additional discussion regarding the sample result outside the acceptable control limit.

Attachment to 0CAN050803 Page 25 of 49 TABLE 2.1 2007 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 0CAN050803 Page 26 of 49 FIGURE 2-1 TLD RADIATION DOSE mR/qtr 2002 - 2007 TLD Readings 15.00 12.00 2002-2006 Control Location Maxim um (+3 Stde v) 9.00 6.00 2002-2006 Control Location Minim um (-3 Stde v) 3.00 Qtr 1, 2007 Qtr 2, 2007 Qtr 3, 2007 Qtr 4, 2007 0.00 1

108 109 110 111 116 125 127 137 145 146 147 148 149 150 151 152 153 2 3 4 6 7 56

Attachment to 0CAN050803 Page 27 of 49 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

3.1 2007 Program Results Summary Table 3.1 summarizes the 2007 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.

Attachment to 0CAN050803 Page 28 of 49 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 2007 Indicator Number of Type &

Sample Type b Locations Location with Highest Control Locations Number of LLD Non-routine (Units) Analysesa Mean (F)c Annual Mean Mean (F)c [Range]

[Range] Resultse Mean (F)c Locationd

[Range]

Air Particulates GB - 135 0.01 0.029 (81 / 81) Station 1 0.030 (27 / 27) 0.027 (54 / 54) 0 (pCi/m3) [0.021 - 0.046] (88°, 0.5 mi) [0.023 - 0.046] [0.019 - 0.044]

Airborne Iodine I-131 - 135 0.07 < LLD N/A N/A < LLD 0 (pCi/m3)

Inner Ring TLDs Gamma - 63 (f) 7.51 (63 / 63) Station 56 9.3 (4 / 4) N/A 0 (mR/Qtr) [4.25 - 11.51] (264°, 0.4 mi) [7.64 - 11.51]

Special Interest TLDs Gamma - 28 (f) N/A 0 6.73 (28 / 28) Station 137 7.9 (4 / 4)[

(mR/Qtr) [4.06 - 9.59] (151°, 8.2 mi) 6.75 - 9.22]

Gamma - 4 (f) 6.9 (4 / 4) 0 Control TLD N/A N/A N/A (mR/Qtr) [5.94 - 8.79]

Attachment to 0CAN050803 Page 29 of 49 TABLE 3.1 (continued)

Type & Indicator Number of Sample Type b Locations Location with Highest Control Locations Number of LLD Non-routine (Units) Mean (F)c Annual Mean Mean (F)c [Range]

Analysesa Resultse

[Range]

Mean (F)c Locationd

[Range]

Surface Water H 8 3000 660.3 (3 / 4) Station 8 660.3 (3 / 4) < LLD 0 (pCi/l) [251.0 - 973.9] (166°, 0.2 mi) [251.0 - 973.9]

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 0CAN050803 Page 30 of 49 TABLE 3.1 (continued)

Type & Indicator Number of Sample Type b Locations Location with Highest Control Locations Number of LLD Non-routine (Units) Mean (F)c Annual Mean Mean (F)c [Range]

Analysesa Resultse

[Range]

Mean (F)c Locationd

[Range]

Drinking Water GB - 8 4 1.14 (2 / 4) Station 14 1.14 (2 / 4) 1.78 (4 / 4) 0 (pCi/l) [0.99 - 1.28] (70°, 5.1 mi) [0.99 - 1.28] [0.83 - 2.26]

I-131 - 8 1.0 < LLD N/A N/A < LLD 0 H 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 67.41 (1 / 1) Station 8 67.41 (1 / 1) < LLD 0

[NA] (243°. 0.9 mi) [NA]

Attachment to 0CAN050803 Page 31 of 49 TABLE 3.1 (continued)

Type & Indicator Number of Sample Type Locations Location with Highest Control Locations Number of LLDb Non-routine (Units) Mean (F)c Annual Mean Mean (F)c [Range]

Analysesa Resultse

[Range]

Mean (F)c Locationd

[Range]

Fish GS - 8 (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 0CAN050803 Page 32 of 49 Attachment 1 2007 Radiological Monitoring Report Summary of Monitoring Results

Attachment to 0CAN050803 Page 33 of 49 TABLE OF CONTENTS TABLE 1.1 AIR PARTICULATE 34 TABLE 1.2 RADIOIODINE CARTRIDGE 35 TABLE 2.1 THERMOLUMINESCENT DOSIMETERS (INNER RING) 36 TABLE 2.2 THERMOLUMINESCENT DOSIMETERS (SPECIAL INTEREST AREAS) 37 TABLE 3.1 SURFACE WATER (GAMMA ISOTOPIC) 38 TABLE 3.2 SURFACE WATER (TRITIUM) 40 TABLE 4.1 DRINKING WATER (GROSS BETA, I-131 AND GAMMA ISOTOPIC) 41 TABLE 4.2 DRINKING WATER (TRITIUM) 42 TABLE 5.1 SEDIMENT 42 TABLE 6.1 FISH 43 TABLE 7.1 FOOD PRODUCTS 43

Attachment to 0CAN050803 Page 34 of 49 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 12/19/2006 01/02/2007 0.028 0.028 0.028 0.024 0.024 01/02/2007 01/10/2007 0.028 0.029 0.025 0.022 0.027 01/10/2007 01/23/2007 0.026 0.024 0.026 0.020 0.025 01/23/2007 02/06/2007 0.032 0.032 0.032 0.029 0.035 02/06/2007 02/20/2007 0.033 0.032 0.034 0.027 0.039 02/20/2007 03/06/2007 0.027 0.026 0.026 0.024 0.028 03/06/2007 03/20/2007 0.028 0.029 0.030 0.022 0.028 03/20/2007 04/03/2007 0.025 0.026 0.023 0.021 0.023 04/03/2007 04/17/2007 0.027 0.025 0.026 0.021 0.026 04/17/2007 05/01/2007 0.027 0.027 0.026 0.025 0.026 05/01/2007 05/15/2007 0.025 0.024 0.025 0.021 0.023 05/15/2007 05/29/2007 0.027 0.026 0.029 0.024 0.029 05/29/2007 06/12/2007 0.024 0.024 0.025 0.020 0.022 06/12/2007 06/26/2007 0.028 0.027 0.031 0.026 0.026 06/26/2007 07/10/2007 0.023 0.021 0.022 0.019 0.020 07/10/2007 07/24/2007 0.023 0.023 0.022 0.019 0.021 07/24/2007 08/07/2007 0.037 0.039 0.036 0.031 0.035 08/07/2007 08/21/2007 0.039 0.040 0.039 0.033 0.037 08/21/2007 09/04/2007 0.032 0.032 0.031 0.025 0.032 09/04/2007 09/18/2007 0.025 0.024 0.024 0.022 0.025 09/18/2007 10/02/2007 0.037 0.036 0.035 0.029 0.034 10/02/2007 10/16/2007 0.024 0.024 0.024 0.020 0.022 10/16/2007 10/30/2007 0.024 0.026 0.024 0.022 0.023 10/30/2007 11/13/2007 0.046 0.046 0.045 0.038 0.044 11/13/2007 11/27/2007 0.026 0.025 0.025 0.019 0.023 11/27/2007 12/11/2007 0.040 0.038 0.037 0.030 0.036 12/11/2007 12/20/2007 0.037 0.035 0.034 0.030 0.035

  • Station with highest annual mean.

Attachment to 0CAN050803 Page 35 of 49 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 12/19/2006 01/02/2007 <0.020 <0.021 <0.018 <0.014 <0.018 01/02/2007 01/10/2007 <0.025 <0.023 <0.022 <0.024 <0.022 01/10/2007 01/23/2007 <0.024 <0.023 <0.021 <0.022 <0.025 01/23/2007 02/06/2007 <0.012 <0.012 <0.013 <0.014 <0.015 02/06/2007 02/20/2007 <0.026 <0.025 <0.023 <0.018 <0.025 02/20/2007 03/06/2007 <0.018 <0.016 <0.019 <0.019 <0.023 03/06/2007 03/20/2007 <0.015 <0.015 <0.015 <0.014 <0.016 03/20/2007 04/03/2007 <0.018 <0.023 <0.019 <0.024 <0.015 04/03/2007 04/17/2007 <0.022 <0.018 <0.021 <0.017 <0.025 04/17/2007 05/01/2007 <0.020 <0.022 <0.018 <0.018 <0.019 05/01/2007 05/15/2007 <0.013 <0.009 <0.015 <0.016 <0.010 05/15/2007 05/29/2007 <0.017 <0.018 <0.016 <0.015 <0.015 05/29/2007 06/12/2007 <0.019 <0.020 <0.020 <0.023 <0.015 06/12/2007 06/26/2007 <0.013 <0.015 <0.017 <0.016 <0.009 06/26/2007 07/10/2007 <0.016 <0.016 <0.018 <0.018 <0.010 07/10/2007 07/24/2007 <0.017 <0.018 <0.022 <0.017 <0.017 07/24/2007 08/07/2007 <0.019 <0.020 <0.019 <0.018 <0.016 08/07/2007 08/21/2007 <0.013 <0.014 <0.016 <0.015 <0.013 08/21/2007 09/04/2007 <0.022 <0.017 <0.020 <0.019 <0.015 09/04/2007 09/18/2007 <0.009 <0.009 <0.009 <0.009 <0.009 09/18/2007 10/02/2007 <0.011 <0.017 <0.015 <0.013 <0.012 10/02/2007 10/16/2007 <0.019 <0.019 <0.020 <0.019 <0.015 10/16/2007 10/30/2007 <0.020 <0.020 <0.016 <0.023 <0.017 10/30/2007 11/13/2007 <0.016 <0.017 <0.017 <0.019 <0.019 11/13/2007 11/27/2007 <0.016 <0.020 <0.018 <0.018 <0.016 11/27/2007 12/11/2007 <0.018 <0.019 <0.015 <0.017 <0.014 12/11/2007 12/20/2007 <0.034 <0.044 <0.045 <0.033 <0.047

Attachment to 0CAN050803 Page 36 of 49 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators)

Station 1st Qtr 07 2nd Qtr 07 3rd Qtr 07 4th Qtr 07 Annual Mean 07 (mrem) (mrem) (mrem) (mrem) (mrem) 3 4.90 4.76 6.77 4.25 5.2 145 6.88 6.74 9.81 6.84 7.6 146 8.46 5.98 8.70 7.00 7.5 147 6.27 5.20 8.35 5.89 6.4 1 7.33 6.63 10.47 7.46 8.0 148 Missing 5.82 9.18 7.01 7.3 110 6.87 6.22 8.20 6.39 6.9 149 7.08 6.00 9.68 6.66 7.4 4 7.33 6.07 9.54 6.47 7.4 150 7.96 6.50 8.84 6.83 7.5 151 7.48 6.97 10.40 6.89 7.9 2 7.68 6.91 10.21 6.80 7.9 56* 9.13 7.64 11.51 8.86 9.3 109 8.13 7.12 10.42 7.43 8.3 108 7.77 6.94 10.75 7.03 8.1 152 7.89 5.88 9.24 6.50 7.4

  • Station with highest annual mean.

Attachment to 0CAN050803 Page 37 of 49 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr 07 2nd Qtr 07 3rd Qtr 07 4th Qtr 07 Annual Mean 07 (mrem) (mrem) (mrem) (mrem) (mrem) 6 7.17 5.18 8.74 5.94 6.8 111 5.07 4.96 6.36 4.87 5.3 116 7.46 6.14 9.30 8.34 7.8 125 4.75 4.06 5.30 4.46 4.6 127 7.76 6.54 9.59 6.97 7.7 137* 8.14 6.75 9.22 7.32 7.9 153 7.55 5.59 8.70 6.25 7.0

  • Stations with highest annual mean.

Special Interest Areas - (Control)

Station 1st Qtr 07 2nd Qtr 07 3rd Qtr 07 4th Qtr 07 Annual Mean 07 (mrem) (mrem) (mrem) (mrem) (mrem) 7 6.84 6.12 8.79 5.94 6.9

Attachment to 0CAN050803 Page 38 of 49 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Required LLD 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 12/31/2006 01/31/2007 <3.25 <8.16 <3.94 <3.84 <9.02 <6.58 <4.70 <6.71 <4.54 <4.13 <18.47 <4.89 Station 10 (Control) 12/31/2006 01/31/2007 <3.85 <6.66 <3.75 <2.95 <5.91 <7.14 <4.85 <7.79 <4.02 <3.60 <17.24 <6.87 Station 8 (Indicator) 01/31/2007 02/28/2007 <2.24 <5.79 <2.41 <2.45 <4.63 <4.13 <3.13 <14.06 <2.26 <2.15 <23.28 <7.45 Station 10 (Control) 01/31/2007 02/28/2007 <2.17 <5.49 <2.45 <2.28 <3.96 <4.51 <3.58 <14.61 <2.23 <2.33 <21.68 <8.28 Station 8 (Indicator) 02/28/2007 03/31/2007 <5.74 <14.72 <5.64 <6.30 <13.22 <10.08 <7.77 <12.12 <5.32 <7.55 <48.49 <11.58 Station 10 (Control) 02/28/2007 03/31/2007 <5.53 <13.77 <4.29 <5.69 <15.92 <10.92 <7.85 <14.18 <6.64 <6.54 <27.91 <13.00 Station 8 (Indicator) 03/31/2007 04/30/2007 <6.53 <12.16 <6.11 <6.53 <16.74 <9.30 <9.77 <9.40 <7.50 <7.19 <26.85 <9.91 Station 10 (Control) 03/31/2007 04/30/2007 <5.58 <8.42 <5.60 <5.80 <12.41 <10.37 <7.75 <8.63 <6.93 <7.27 <26.46 <7.39 Station 8 (Indicator) 04/30/2007 05/31/2007 <5.22 <8.95 <5.19 <5.04 <9.89 <6.99 <5.17 <8.39 <4.90 <4.33 <19.45 <5.13 Station 10 (Control) 04/30/2007 05/31/2007 <5.39 <11.26 <5.21 <5.19 <13.43 <11.20 <8.14 <9.64 <5.68 <6.28 <23.63 <8.10 Station 8 (Indicator) 05/31/2007 06/30/2007 <4.24 <12.04 <5.18 <5.09 <11.64 <9.86 <7.15 <12.16 <5.30 <5.31 <25.17 <13.05 Station 10 (Control) 05/31/2007 06/30/2007 <4.97 <11.60 <6.12 <4.83 <13.10 <8.38 <6.02 <12.27 <5.54 <5.60 <32.40 <12.03

Attachment to 0CAN050803 Page 39 of 49 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Required LLD 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 06/30/2007 07/31/2007 <4.29 <7.98 <4.11 <3.33 <7.61 <6.58 <4.51 <4.64 <3.90 <3.19 <14.39 <5.64 Station 10 (Control) 06/30/2007 07/31/2007 <4.37 <7.86 <4.27 <3.85 <7.47 <7.79 <4.75 <4.62 <4.34 <4.33 <14.57 <2.99 Station 8 (Indicator) 07/31/2007 08/31/2007 <3.25 <7.02 <4.47 <4.40 <6.98 <8.10 <4.86 <9.69 <4.12 <3.51 <27.48 <10.17 Station 10 (Control) 07/31/2007 08/31/2007 <2.90 <8.74 <4.18 <3.72 <7.01 <7.30 <5.22 <10.68 <4.03 <3.57 <25.95 <5.20 Station 8 (Indicator) 08/31/2007 09/30/2007 <5.12 <9.81 <4.55 <5.28 <10.39 <5.00 <4.43 <9.01 <3.73 <3.99 <21.13 <7.78 Station 10 (Control) 08/31/2007 09/30/2007 <5.51 <10.91 <6.02 <5.30 <14.90 <8.68 <5.94 <12.76 <6.32 <6.47 <29.38 <10.26 Station 8 (Indicator) 09/30/2007 10/31/2007 <5.08 <10.73 <4.10 <3.36 <8.81 <8.42 <5.03 <7.52 <5.02 <4.68 <16.83 <9.70 Station 10 (Control) 09/30/2007 10/31/2007 <4.50 <10.75 <5.61 <2.72 <11.05 <8.33 <8.12 <10.13 <4.94 <4.73 <23.91 <8.38 Station 8 (Indicator) 10/31/2007 11/30/2007 <5.18 <11.49 <4.24 <3.99 <11.11 <7.79 <7.48 <9.79 <4.26 <3.83 <22.26 <8.80 Station 10 (Control) 10/31/2007 11/30/2007 <4.65 <10.90 <5.45 <5.12 <11.90 <11.46 <7.18 <11.41 <4.48 <5.72 <34.90 <10.83 Station 8 (Indicator) 11/30/2007 12/31/2007 <2.63 <7.39 <3.50 <3.13 <6.74 <5.92 <3.79 <5.71 <3.37 <3.29 <15.37 <5.26 Station 10 (Control) 11/30/2007 12/31/2007 <4.09 <7.72 <3.57 <4.27 <7.25 <5.84 <4.23 <7.67 <3.54 <3.39 <18.55 <6.35

Attachment to 0CAN050803 Page 40 of 49 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) 12/31/2006 03/31/2007 973.9 Station 10 (Control) 12/31/2006 03/31/2007 <535.4 Station 8 (Indicator) 03/31/2007 06/30/2007 251.0 Station 10 (Control) 03/31/2007 06/30/2007 <550.2 Station 8 (Indicator) 06/30/2007 09/30/2007 <532.0 Station 10 (Control) 06/30/2007 09/30/2007 <531.1 Station 8 (Indicator) 09/30/2007 12/31/2007 756.0 Station 10 (Control) 09/30/2007 12/31/2007 <570.1

Attachment to 0CAN050803 Page 41 of 49 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) 03/20/2007 1.28 <0.86 <7.21 <10.85 <6.60 <4.29 <13.03 <11.22 <7.54 <7.12 <6.30 <29.37 <9.91 Station 57 (Control) 03/20/2007 2.26 <0.86 <5.42 <11.16 <5.08 <3.42 <11.47 <11.55 <7.77 <6.33 <5.40 <28.16 <11.42 Station 14 (Indicator) 06/19/2007 <1.20 <0.90 <6.50 <14.82 <7.84 <5.35 <8.06 <12.72 <9.97 <6.20 <5.73 <32.31 <9.94 Station 57 (Control) 06/19/2007 0.83 <0.71 <7.31 <15.82 <5.33 <5.57 <12.43 <9.12 <8.63 <7.55 <6.08 <29.49 <11.89 Station 14 (Indicator) 09/18/2007 0.99 <0.82 <5.72 <14.30 <6.34 <5.64 <14.36 <7.43 <8.14 <5.73 <7.00 <24.81 <8.66 Station 57 (Control) 09/18/2007 1.93 <0.90 <7.62 <11.84 <6.73 <4.80 <9.21 <12.13 <7.14 <6.54 <7.10 <27.37 <10.27 Station 14 (Indicator) 12/19/2007 <1.31 <0.89 <3.03 <10.05 <3.40 <29.85 <8.79 <6.67 <4.02 <3.94 <3.49 <25.40 <7.57 Station 57 (Control) 12/20/2007 2.09 <0.90 <2.98 <7.24 <2.75 <3.24 <6.13 <6.36 <4.18 <3.33 <3.21 <23.47 <6.89

Attachment to 0CAN050803 Page 42 of 49 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 2000 Station 14 (Indicator) 03/20/2007 <574 Station 57 (Control) 03/20/2007 <572 Station 14 (Indicator) 06/19/2007 <522 Station 57 (Control) 06/19/2007 <526 Station 14 (Indicator) 09/18/2007 <526 Station 57 (Control) 09/18/2007 <528 Station 14 (Indicator) 12/19/2007 <577 Station 57 (Control) 12/20/2007 <591 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) 10/09/2007 <131.21 67.41 Station 16 (Control) 10/09/2007 <138.36 <112.29

Attachment to 0CAN050803 Page 43 of 49 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 130 260 130 130 260 130 150 Station 8 (Indicator) 12/04/2007 <21.83 <72.51 <21.57 <20.41 <34.23 <16.58 <16.95 Station 16 (Control) 12/21/2007 <15.24 <45.48 <17.26 <18.96 <39.24 <14.20 <10.71 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) 06/19/2007 <59.91 <39.53 <36.66 Station 55 (Control) 06/19/2007 <57.36 <45.00 <28.49 Station 13 (Indicator) 07/24/2007 <56.07 <42.96 <31.63 Station 55 (Control) 07/24/2007 <57.17 <48.46 <36.63 Station 13 (Indicator) 08/21/2007 <59.88 <34.09 <39.63 Station 55 (Control) 08/21/2007 <59.28 <34.23 <25.75

Attachment to 0CAN050803 Page 44 of 49 ATTACHMENT 2 Interlaboratory Comparison Program

Attachment to 0CAN050803 Page 45 of 49 Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Sample Study Date Analysis Known RBS RBS RBS Type (units) Valuea Value N-Devb N-Rangec Charcoal E5390-125 6/14/2007 I-131 7.91E+01 7.97E+01 0.13 0.01 Cartridge (pCi/cartridg e)

Water E5389-125 6/14/2007 BETA 1.99E+02 2.25E+02 1.49 0.06 (pCi/liter) E5388-125 6/14/2007 Cr-51 4.11E+02 4.20E+02 0.75 0.20 (d)

Mn-54 1.33E+02 1.48E+02 3.89 0.04 Co-58 1.59E+02 1.64E+02 1.01 0.06 Fe-59 1.34E+02 1.45E+02 2.83 0.16 Co-60 1.91E+02 1.95E+02 0.75 0.09 Zn-65 2.68E+02 2.82E+02 0.87 0.13 I-131 1.02E+02 1.02E+02 -0.02 0.16 Cs-134 1.94E+02 1.93E+02 -0.11 0.24 Cs-137 1.35E+02 1.40E+02 1.21 0.32 Ce-141 1.60E+02 1.63E+02 0.57 0.38 E5467-125 9/13/2007 H-3 1.20E+04 1.11E+04 -1.26 0.06 E5391-125 6/12/2007 Cr-51 5.12E+02 5.17E+02 0.12 0.06 Milk (pCi/liter) Mn-54 1.66E+02 1.82E+02 1.14 0.11 Co-58 1.98E+02 2.02E+02 0.24 0.05 Fe-59 1.67E+02 1.85E+02 1.23 0.09 Co-60 2.38E+02 2.37E+02 -0.03 0.02 Zn-65 3.34E+02 3.72E+02 1.98 0.07 I-131 7.01E+01 7.03E+01 0.05 0.20 Cs-134 2.42E+02 2.42E+02 0.02 0.07 Cs-137 1.69E+02 1.70E+02 0.06 0.03 Ce-141 2.00E+02 2.03E+02 0.16 0.05

Attachment to 0CAN050803 Page 46 of 49 Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Tritium and Gamma Isotopic Sample Study Date Analysis Known RBS RBS RBS Type Valuea Value N-Devb N-Rangec (units)

E5468-125 9/13/2007 BETA 3.23E+01 2.81E+01 -1.46 0.03 Air Filter E5469-125 9/13/2007 Cr-51 1.25E+02 1.22E+02 -0.09 0.03 (pCi/Filter)

Mn-54 7.26E+01 7.82E+01 1.93 0.14 Co-58 4.94E+01 4.87E+01 -0.23 0.19 Fe-59 4.79E+01 5.17E+01 1.33 0.04 Co-60 6.41E+01 6.48E+01 0.26 0.03 Zn-65 8.76E+01 9.96E+01 2.38 0.09 Cs-134 6.38E+01 6.12E+01 -0.89 0.08 Cs-137 5.65E+01 5.85E+01 0.69 0.11 Ce-141 9.14E+01 9.12E+01 -0.06 0.12 E5470-125 9/13/2007 Cr-51 3.91E-01 3.83E-01 -0.07 0.03 Sediment (pCi/gram) Mn-54 2.27E-01 2.43E-01 0.24 0.01 Co-58 1.54E-01 1.38E-01 -0.36 0.04 Fe-59 1.49E-01 1.48E-01 -0.03 0.02 Co-60 2.00E-01 1.94E-01 -0.11 0.01 Zn-65 2.73E-01 3.00E-01 1.74 0.09 Cs-134 1.99E-01 2.03E-01 0.07 0.02 Cs-137 2.73E-01 2.99E-01 0.33 0.02 Ce-141 2.85E-01 2.81E-01 -0.05 0.03 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; +/-2.00 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; +2.000 is the warning limit and +3.000 is the control limit.

This is a measure of precision of the analytical methods.

(d) Results reported were outside Control Limits.

Attachment to 0CAN050803 Page 47 of 49 Interlaboratory Comparison Program Exceptions There was one result outside the control limits for accuracy in the 2007 Interlaboratory Comparison program participation studies. The RBS normalized-deviation for nuclide Mn-54 in a gamma isotopic water analysis, Analytics sample number E5388-125 of 6/14/2007, was

+3.89, which is outside the control limit of +/-3.00 for accuracy. This high bias result is considered conservative and is considered as having no impact on past results of the program. The results for Mn-54 in all other program samples were within control limits for the year 2007; with normalized-deviations of 0.24 in sediment sample analysis; 1.93 in an air filter sample analysis; and 1.14 in a milk sample analysis. Reanalysis of the 2007 water sample produced results very similar to the original averaged result.

A review concerning the high bias was performed with no obvious issues associated with the counting of the water samples. Analytics was contacted concerning this result. A possible explanation offered from Analytics was that the effect of coincidence summing in calibration sources containing Y-88 and Co-60 may cause a lower efficiency for energies associated with Mn-54. The lower efficiency will result in a higher concentration for Mn-54. This phenomenon can sometimes also be seen with energies associated with Fe-59 and Zn-65.

Attachment to 0CAN050803 Page 48 of 49 ATTACHMENT 3 Sediment Dose Calculations

Attachment to 0CAN050803 Page 49 of 49 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/m2; C = 2007 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 Millirem/Year) 2007 Conversion Conversion Total Skin Total Body Radionuclide Maximum Factor For Factor For Dose Dose Concentration Skin Total Body Cs-137 67.41 4.90 E-09 8.85 E-05 4.20 E-09 7.59 E-05 TOTAL 8.85 E-05 7.59 E-05

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