ML021560037

2001 Annual Radiological Environmental Operating Report

ML021560037
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/13/2002
From:	Cotton S Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
OCAN050206
Download: ML021560037 (53)

Text

Entergy Operations, Inc.

Russellville, AR 72802 Tel 501858 5000 0CAN050206 May 13, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OPl-17 Washington, DC 20555

Subject:

Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 2001 Annual Radiological Environmental Operating Report

Dear Sir or Madam:

Arkansas Nuclear One (ANO), Units 1 and 2, Technical Specifications 6.12.2.5 (Improved Technical Specification 5.6.2) and 6.9.4, respectively, require the submittal of an annual radiological environmental operating report for the previous calendar year by May 15 of each year. Attached is the annual radiological environmental operating report for ANO for the year 2001. The radionuclides detected by the radiological environmental monitoring program during 2001 were significantly below regulatory limits; therefore, ANO plant operations during 2001 had no harmful effects nor resulted in any irreversible damage to the environment. This report fulfills the reporting requirements referenced above. This submittal contains no commitments. Should you have any questions regarding this submittal, please contact me.

Sincerely, Sherrie R. Cotton Director, Nuclear Safety Assurance SRC/nbm Attachment

0CAN050206 Page 2 cc: Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. William Reckley NRR Project Manager Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 0-7 D1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Thomas W. Alexion NRR Project Manager Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 04-D-03 One White Flint North 11555 Rockville Pike Rockville, MD 20852

Attachment to 0CAN050206 Page 1 of 51 ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2001

Attachment to 0CAN050206 Page 2 of 51 TABLE OF CONTENTS

SUMMARY

6

1.0 INTRODUCTION

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

SUMMARY

27 3.1 2001 Program Results Summary 27

Attachment to 0CAN050206 Page 3 of 51 LIST OF TABLES TABLE 1.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM 12 TABLE 2.1 2001 LAND USE CENSUS 24 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

28

Attachment to 0CAN050206 Page 4 of 51 LIST OF FIGURES FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD 18 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 19 FIGURE 2-1 TLD RADIATION DOSE 25 FIGURE 2-2 DISCHARGE SEDIMENT 26

Attachment to 0CAN050206 Page 5 of 51 LIST OF ATTACHMENTS ATTACHMENT 1 2001 RADIOLOGICAL MONITORING REPORT

SUMMARY

OF MONITORING RESULTS 32 ATTACHMENT 2 SEDIMENT DOSE CALCULATIONS 50

Attachment to 0CAN050206 Page 6 of 51 Summary The Annual Radiological Environmental Operating Report presents data obtained through analyses of environmental samples collected for Arkansas Nuclear One's (ANO's)

Radiological Environmental Monitoring Program (REMP) for the period January 1, 2001 through December 31, 2001. This report fulfills the requirements of ANO Unit 1 Technical Specification 6.12.2.5 and Unit 2 Technical Specification 6.9.4. During 2001 as in previous years, ANO detected radionuclides attributable to plant operations at the discharge location (Station 8). ANO personnel routinely monitor results from this area in order to note any trends. Their review of results from this area indicates the following:

" Manganese-54, Cobalt-58, Cobalt-60 and Niobium-95 were detected in the surface water media during September and October while liquid radwaste discharges were occurring.

However, the levels detected were well below regulatory reporting limits.

"* Tritium levels in the surface water media continue to be below regulatory reporting limits.

" Cobalt-60 and Cesium-137 levels in the sediment media are not demonstrating any increase in comparison to previous years. Review indicates that 2001 levels are less than that of the historical average.

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

Cesium- 137, attributable to fallout from previous atmospheric weapons testing, was detected once at the Station 16 sediment control location during 2001. However, the level detected is less than that of the historical average at this location.

Radiolo2ical 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 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 0CAN050206 Page 7 of 51 In 2001, 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. Their review of 2001 data, in many cases, showed undetectable radiation levels in the environment and near background level in 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 2001. 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, as outlined in Units 1 and 2 Offsite Dose Calculation Manual (ODCM) Table 2.6-3, when averaged over any calendar quarter, due to ANO effluents. Therefore, 2001 results did not trigger any Radiological Monitoring Program Special Reports.

Radioactivity Not Attributable to ANO The ANO REMP detected radioactivity attributable to other sources twice. 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 in certain pathways.

Comparison to Federal and State Programs ANO personnel compared REMP data to federal and state monitoring programs as results became available. Historically, the programs used for comparison have included the U.S.

Nuclear Regulatory Commission (NRC) TLD Direct Radiation Monitoring Network and the Arkansas Department of Health (ADH).

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

The ADH and the ANO REMP entail similar radiological environmental monitoring program requirements. These programs include collocated 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 OCAN050206 Page 8 of 51 Sample Deviations

• Milk The REMP did not include milk sampling within five miles (8 km) of ANO in 2001 due to unavailability. ANO Units 1 and 2 ODCM require collection of milk samples if available commercially within 8 km (5 miles) of the plant. ANO personnel collected vegetation samples to monitor the ingestion pathway, as specified in the ODCM, because of milk unavailability.

• Required Lower Limit of Detection (LLD) Values All LLDs during this reporting period were within the acceptable limits required by the technical specifications.

+ Air Samples Listed below are air sampler deviations that occurred during 2001 due to electrical failures (broken power lines and transformer fire). These deviations did not result in a missed sample and no LLD values were exceeded. As described in footnote (a) to ANO Units 1 and 2 ODCM Table 2.6-2, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons.

Station Sampling Period Run Time (Hours) 2 07131/2001 - 08/14/2001 129.2 08/14/2001 - 00/23/2001 119.8 7 06/19/2001 - 07/03/2001 328.5 07/03/2001 - 07/17/2001 41.3 07/17/2001 - 07/31/2001 286.6

• Missed Samples One third quarter TLD (Station 127) was missed during 2001 due to vandalism. This loss was an isolated instance that did not recur during the year and was replaced with a new TLD by ANO personnel once discovered. The recovery rate for TLDs during 2001 was 99% (95 of 96).

Attachment to OCAN050206 Page 9 of 51

• Surface Water Tritium was initially detected in the first quarter composite for Station 8 (Discharge) at a concentration of 18,559 pCi/l and was documented in CR-ANO-C-2001-00199. ANO's review of liquid radwaste discharges did identify an increase in curies of tritium released, when comparing the fourth quarter of 2000 to the first quarter of 2001. However, it was determined that this was not the cause of the elevated tritium levels detected in the fourth quarter composite sample.

Since monthly composite samples are collected for gamma analysis at this location, ANO requested the River Bend Station (RBS) Environmental Laboratory (central location for Entergy Operations' radiological environmental analysis) to perform a tritium analysis on the January, February and March samples. Results from these analyses showed a tritium range from 953 pCi/l to 1,898 pCi/l.

Based on these results, ANO requested the RBS Environmental Laboratory to composite the January, February and March sample for gamma analysis, and perform a tritium analysis. The results of this composite showed a concentration of 1,761 pCi/l. Since it is apparent that the original tritium composite sample may have been contaminated, ANO personnel have elected to report the value of 1,761 pCi/l for the first quarter Station 8 tritium composite. This value is further validated by the Arkansas Department of Health (ADEH) who also obtained a result 1,675 pCi/l on the first quarter split tritium composite sample between ANO and the ADH.

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

Pro2ram Modifications ANO made no modifications to the REMP during 2001.

Attachments contains results of air, TLD, water, sediment, fish, and food products samples collected in 2001. TLDs were analyzed by Waterford-3 Dosimetry. All remaining samples were analyzed by River Bend Station's (RBS) Environmental Laboratory. Attachment 1 also contains RBS' participation in the interlaboratory comparison program during 2001. contains dose calculations performed for sediment using a generalized equation from Regulatory Guide 1.109, "Calculationof Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I"

Attachment to OCAN050206 Page 10 of 51 1.0 Introduction 1.1 Radiological Environmental Monitoring Program ANO established the REMP to ensure that plant operating controls properly function to minimize any associated radiation endangerment to human health or the environment. The REMP is designed for:

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

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

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

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

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

Section 2.0 of this report provides a discussion of 2001 sampling results with Section 3.0 providing a summary of results for the monitored exposure pathways.

1.3 Land Use Census ANO personnel conduct a land use census biannually, 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 is to determine location in each sector of the nearest:

1) Residence

2) Animal milked for human consumption

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

• Attachment to 0CAN050206 Page 11 of 51 The method used by ANO personnel for conducting this land use census is as follows:

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

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

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

1) Nearest permanent residence

2) Nearest milking animal

"* ANO personnel identify locations on the map, measures distances to ANO and records 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 0CAN050206 Page 12 of 51 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 Boundary, in Station 2 (2400 - 0.5 miles) - East of the Continuous operation of Radioiodine Canister - Analyze at (or near) different sectors with the sewage treatment plant. sampler with sample least once per 14 days for 1-131.

highest calculated annual average collection as required by groundlevel D/Q. Station 56 (2730 - 0.4 miles) - West end of dust loading but at least Particulate Sampler - Analyze for once per 14 days. gross beta radioactivity following filter change.

Radioiodine and Particulates 1 sample from the vicinity of a Station 6 (1110 - 7.0 miles) - Entergy local community having the highest office in Russellville (305 South Knoxville calculated annual average groundlevel Avenue).

D/Q.

Radioiodine and Particulates 1 sample from a control location 15-30 Station 7 (2090 - 19.3 miles) - Entergy Supply km (10 -20 miles) distance. Yard on Highway 10 in Danville.

Radioiodine and Particulates One location sampled voluntarily by Station 1 (900 - 0.6 miles) - On a pole near ANO. the meteorology tower.

Direct TLDs Radiation 16 inner ring stations with two or more Station 1 (900 - 0.6 miles) - On a pole near Once per 92 days. Gamma Dose - Once per 92 dosimeters in each meteorological the meteorology tower, days.

sector in the general area of the Site Station 2 (2400 - 0.5 miles) East of the Boundary sewage treatment plant.

Station 3 (60 - 0.7 miles) - Junction of Highway 333 and Flatwood Road.

Attachment to OCAN050206 Page 13 of 51 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 16 inner ring stations with two or more Station 4 (1760 - 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 (2730 - 0.4 miles) - West end of the sewage treatment plant.

Station 108 (3130 - 0.9 miles) - South on Flatwood Road on a utility pole.

Station 109 (2900 - 0.6 miles) - Utility pole across from the junction of Flatwood Road and Round Mountain Road.

Station 110 (1400 - 0.7 miles) - Bunker Hill Lane on the first utility pole on the left.

Station 145 (300 - 0.6 miles) - Near west entrance to the RERTC on a utility pole.

Station 146 (500 - 0.6 miles) - South end of east parking lot at RERTC on a utility pole.

Station 147 (630 - 0.6 miles) - West side of Bunker Hill Road, approximately 100 yards from intersection with State Highway 333.

Station 148 (1220 - 0.5 miles) - Intersection of Bunker Hill Road with Scott Lane on county road sign post.

Attachment to 0CAN050206 Page 14 of 51 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 16 inner ring stations with two or more Station 149 (1500 - 0.6 miles) - On a utility Once per 92 days. Gamma Dose - Once per 92 dosimeters in each meteorological pole on the south side of May Road. days.

sector in the general area of the Site Station 150 (2010 - 0.6 miles) - North side of Boundary May Road on a utility pole.

Station 151 (2200 - 0.4 miles) - West side of sewage treatment plant near the lake on a metal post.

Station 152 (3380 - 0.8 miles) - North side of State Highway 333 on a London City limit sign post.

TLDs 8 stations with two or more Station 6 (1110 - 7.0 miles) - Entergy local dosimeters in special interest areas office in Russellville (305 South Knoxville Avenue).

such as population centers, nearby residences, schools, and in 1 - 2 Station 7 (2090 - 19.3 miles) - Entergy Supply areas to serve as control locations. Yard on Highway 10 in Danville.

Station Il1 (117° - 2.0 miles) - Marina Road on a utility pole on the left just prior to curve.

Station 116 (3200 - 1.9 miles) - Highway 333 and Highway 64 in London on a utility pole north of the railroad tracks.

Attachment to 0CAN050206 Page 15 of 51 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 8 stations with two or more Station 125 (460 - 9.0 miles) - College Street Once per 92 days. Gamma Dose - Once per 92 dosimeters in special interest areas on a utility pole at the southeast corner of the days.

such as population centers, nearby red brick school building.

residences, schools, and in 1 - 2 Station 127 (1020 - 5.3 miles) - Arkansas Tech areas to serve as control locations. Campus on a utility pole across from Paine Hall.

Station 137 (1500 - 8.1 miles) - On a speed limit sign on the right in front of the Morris R.

Moore Arkansas National Guard Armory.

Station 153 (3050 - 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 (1800 - 0.1 miles) - Plant discharge Once per 92 days. Gamma isotopic and tritium plant discharge) canal. analyses once per 92 days.

1 control location (uninfluenced by Station 10 (900 - 0.5 miles) - Plant intake plant discharge) canal.

Drinking Water 1 indicator location (influenced by Station 14 (700 - 5.3 miles) - Russellville city Once per 92 days. 1-131, gross beta, gamma plant discharge) water system from the Illinois Bayou. isotopic and tritium analyses 1 control location (uninfluenced by Station 57 (2080 - 19.5 miles) - Danville public once per 92 days.

plant discharge) water supply treatment on Fifth Street.

Attachment to 0CAN050206 Page 16 of 51 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 Waterborne Sediment 1 indicator location (influenced by Station 8 (2450 - 0.7 miles) - Plant discharge Once per 365 days. Gamma isotopic analysis once plant discharge) canal. per 365 days.

1 control location (uninfluenced by Station 16 (2900 - 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 8 Currently, no available milking animals within 8 Once per 92 days. Gamma isotopic and 1-131 km distant if commercially available. km of ANO. analyses once per 92 days.

1 control sample location at a distant of >8 km, when an indicator exists.

Fish 1 sample of commercially and/or Station 8 (2300 - 0.6 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 (2900 - 5.5 miles) - Panther Bay on influenced by plant discharge. south side of Arkansas River across from mouth of Piney Creek.

Attachment to 0CAN050206 Page 17 of 51 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Ingestion Food Products 1 sample of broadleaf (edible or non- Station 13 (2780 - 0.5 miles) - West from ANO Three per 365 days. Gamma isotopic and 1-131 edible) near the Site Boundary from toward Gate 4 onto Flatwood Road. analyses three times per 365 one of the highest anticipated annual days.

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

1 sample location of broadleaf Station 55 (2090 - 16.6 miles) - Intersection of vegetation (edible or non-edible) from Highway 27 and 154.

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

Attachment to 0CAN050206 Page 18 of 51 FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD HILL DfO STATE PARK (RMWL~ZLVIUEX MAET DOWK

Attachment to OCAN050206 Page 19 of 51 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 11 1

--- 4

Attachment to 0CAN050206 Page 20 of 51 2.0 Interpretation and Trends of Results 2.1 Air Particulate and Radioiodine Sample Results Iodine-131 was not detected in the radioiodine cartridges during 2001, as has been the case in previous years. Indicator gross beta air particulate results for 2001 were similar to those background 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 Preoperational 0.05 1996 -2000 0.02 2001 0.02 Table 3.1, which includes gross beta concentrations, provides a comparison of the indicator and control means, and further emphasizes that the airborne pathway continues to remain at background levels.

2.2 Thermoluminescent Dosimetry Sample Results ANO reports measured dose as net exposure (field reading less [transit + shield reading]) normalized to 92 days and relies on comparison of the indicator locations to the control as a measure of plant impact. Gamma radiation dose in the reporting period was compared to control location readings for previous years as shown in Figure 2-1.

ANO's comparison of the results to the control, as seen in Figure 2-1, indicates that the ambient radiation levels are unaffected by plant operations. Although four of the TLD stations shown in Figure 2-1 were slightly above the historical maximum control location value of 11.0 mrem/quarter, they were all within the upper (+) three standard deviation range of 12.0 mrem for the control. Therefore, levels continue to remain at or near background.

2.3 Water Sample Results Analytical results for 2001 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. During 2001, gamma radionuclides and tritium was detected at the indicator location during liquid radwaste discharges from the plant.

Attachment to 0CAN050206 Page 21 of 51 Tritium was detected at concentrations ranging from 492.0 - 1,761.0 pCi/l with an average concentration of 869.8 pCi/i. However, from 1995 through 2000, tritium concentrations at this location have typically ranged from 430.0 - 5,588 pCi/1.

Therefore, concentrations detected during 2001 are within the typical range of previous operational years and are not demonstrating any increase. Liquid effluent limitations imposed by 10CFR20 were met for all discharges and concentrations detected in the surface water samples were below reporting levels based on the reporting criteria outlined in Units 1 and 2 ODCM Table 2.6-3 when averaged over a calendar quarter.

In addition, the following gamma radionuclides were detected during the reporting period:

Radionuclide Average Concentration Ran2e Manganese-54 17.5 None Cobalt-58 32.9 2.47 - 59.1 Cobalt-60 40.0 4.14 - 70.3 Niobium-95 18.4 16.8-20.0 As already stated above, liquid effluent limitations imposed by IOCFR20 were met for all discharges and concentrations detected in the surface water samples were below reporting levels based on the reporting criteria outlined in Units 1 and 2 ODCM Table 2.6-3 when averaged over a calendar quarter.

Based on the above, the operation of ANO had no impact on this pathway during 2001 and levels of radionuclides remain similar to those obtained in 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 pathway to exist, the City of Russellville has not withdrawn water from Lake Dardanelle in the past several years.

Drinking water samples were analyzed for gross beta radionuclides, Iodine-131, gamma radionuclides and tritium. Gamma radionuclides, Iodine-131 and tritium concentrations were below detectable limits at the indicator and control locations, which is consistent with preoperational and operational years. In addition, gross beta concentrations at the indicator and control locations are similar as shown in Table 3.1.

Listed below is a comparison of 2001 indicator results to preoperational and operational years. Results are reported as annual average pCi/l.

Attachment to 0CAN050206 Page 22 of 51 Radionuclide 2001 1996 - 2000 Preoperational Gross Beta 2.15 3.44 2.0 Iodine-131 <LLD <LLD <LLD Gammas <LLD <LLD <LLD Tritium <LLD 335.0 200.0 Based on this comparison, the operation of ANO had no impact on this pathway during 2001 and radionuclides monitored for this pathway continue to remain at background levels.

2.4 Sediment Sample Results Sediment samples were collected from two locations in 2001 and analyzed for gamma radionuclides. As in previous years, radionuclides attributable to ANO were detected in the discharge sediment. However, Figure 2-3 shows that 2001 levels are below those of previous operational years. 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 all radionuclides to the skin and total body was <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 radionuclides detected in 2001 had no significant impact on the environment or public.

2.5 Milk Sample Results Milk samples were not collected during 2001 due to the unavailability of indicator locations within 8-km of ANO. Since there are no dairies within five miles of the ANO site, it is concluded ANO's operation had no impact on this pathway in 2001.

2.6 Fish Sample Results Fish samples were collected from two locations and analyzed for gamma radionuclides. In 2001, gamma radionuclides were below detectable limits, which is 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 pathway.

Attachment to 0CAN050206 Page 23 of 51 2.7 Food Product Sample Results Food product samples were collected when available from two locations in 2001 and analyzed for Iodine-131 and gamma radionuclides. The 2001 levels remained undetectable, as has been the case in previous years. Therefore, since levels continue to remain at background, it can be concluded that plant operations is not impacting this pathway.

2.8 Land Use Census Results The land use census did not identify any new locations during the September 2001 survey that yielded a calculated dose or dose commitment greater than those currently calculated, even though two new homes under construction were identified in Sectors "S" and "W" and minor adjustments were made to the nearest residence mileage distances (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 2001, 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, 2001 Radiological Environmental Monitoring Report, contains these results. ANO's review of RBS' interlaboratory comparison indicated that 98% of the sample results for accuracy and precision were within the acceptable control limits of the three normalized deviations. For those sample results outside the acceptable control limits, ANO's and RBS's review indicated no impact on previously reported data. Attachment 1 also provides additional discussion regarding sample results outside the acceptable control limits.

Attachment to 0CAN050206 Page 24 of 51 TABLE 2.1 2001 Land Use Census NEAREST RESIDENCE WITHIN FIVE MILES Direction Sector Distance (miles)

N* 1 0.9 NNE 2 1.2 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 2.9 WSW 12 0.7 W* 13 0.9 WNW 14 0.8 NW

• 15 1.0 NNW* 16 0.9

• Changed since previous census.

Attachment to 0CAN050206 Page 25 of 51 Figure 2-1 TLD Radiation Dose 1997 - 2001 ThD Readings 15.0 X X 1997-2000ControlLocation Maximum Value *

• 10.0

• m M] ] M]*[ X X M] X ][ M X M] M X I A*

• X EX X U E A *X A t[E a A A A A *AXA A XA A A A 5.0 A 1997- 2000 Control Location Minimum Value 0.0 A .

TLD Location

• Qtr 1, 2001 m Qtr 2, 2001 A Qtr 3, 2001 x Qtr 4, 2001

Attachment to 0CAN050206 Page 26 of 51 Figure 2-2 Discharge Sediment 1996 - 2001 Gamma Radionuclide Results Discharge Sediment Annual Average pCi/kg 1200 1000 800 600 200 0-ii!iiii~i!iiiiiiiiiii~iiiiiiiil MN-54 CO-58 CO-60 CS-1 34 CS-1 37

• Average based on positive results only.

Attachment to 0CAN050206 Page 27 of 51 3.0 Radiological Environmental Monitoring Program Summary 3.1 2001 Program Results Summary Table 3.1 summarizes the 2001 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 0CAN050206 Page 28 of 51 TABLE 3.1 Radiolo2ical Environmental Monitoring Pro2ram 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 2001 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) C Mean (F) c Nonroutine

[Range I I Range I Results e Mean (F) C Location d [ Range I Air Particulates GB 130 0.01 0.02 ( 78 / 78) Station 1 0.03 (26 / 26) 0.03 ( 52 / 52 0 (pCi/m3) [0.01-0.05] (90°,0.6mi) [0.02-0.05] [0.02-0.10]

Airborne Iodine 1-131 130 0.07 <LLD N/A N/A <LLD 0

( pCi/m3 )

Inner Ring TLDs Gamma 64 (f) 8.2(64/64) Station 151 9.5(4/4) N/A 0

( mR/Qtr ) [ 4.0 - 11.0 ] ( 220', 0.4 mi) [7.0 - 11.0]

Special Interest TLDs Gamma 27 (f) 7.1 (27 / 27) Station 137 8.5 (4 / 4) N/A 0 (mR/Qtr) [5.0-9.0] ( 1500, 8.1mi) [8.0-9.0]

6.0(4/4) 0 Control TLD Gamma 4 (f) N/A N/A N/A [5.0 - 7.0]

(mR/Qtr)

Attachment to OCAN050206 Page 29 of 51 TABLE 3.1 Radiological Environmental Monitorin2 Pro2ram 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 2001 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) c Mean (F) c Nonroutine

[Range ] [Range ] Results e Mean (F) c Location d [ Range I Surface Water H-3 8 3000 869.8(4/4) Station 8 869.8(4/4) <LLD 0 (pCi/I) [492.0 - 1761.0] (1800, 0.1 mi) [492.0 - 1761.01 GS 25 Mn-54 15 17.5(1/13) Station 8 17.5(1/13) <LLD 0

[NA] ( 180, 0.1 mi) [NA]

Fe-59 30 <LLD N/A N/A <LLD 0 Co-58 15 32.9(3/13 ) Station 8 32.9(3/13) <LLD 0

[2.47-59.1] ( 180o, 0.1 mi) [2.47-59.1]

Co-60 15 40.0(3/13) Station 8 40.0(3/13) <LLD 0

[4.14-70.3 ( 180o, 0.1 mi) [4.14-70.3]

Zn-65 30 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 Nb-95 15 18.4(2/13) Station 8 18.4(2/13) <LLD 0

[16.8 - 20.0] (1800, 0.1 mi) [16.8 - 20.0]

1-131 15 <LLD N/A N/A <LLD 0 Cs-134 15 <LLD N/A N/A <LLD 0 Cs-137 18 <LLD N/A N/A <LLD 0 Ba-140 60 <LLD N/A N/A <LLD 0 La- 140 15 <LLD N/A N/A <LLD 0

Attachment to OCAN050206 Page 30 of 51 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 2001 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) c Mean (F) c Nonroutine

[Range] [ Range] Results e Mean (F) c Location d [ Range I Drinking Water GB 8 4 2.15(3/4) Station 14 2.15(3/4) 2.33(3/4) 0 (pCi/1) [1.69 - 2.44] (700, 5.3 mi) [1.69 - 2.44] [2.03 - 2.70 1-131 8 1.0 <LLD N/A N/A <LLD 0 H-3 8 2000 <LLD N/A N/A <LLD 0 GS 8 Mn-54 15 <LLD N/A N/A <LLD 0 Fe-59 30 <LLD N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Co-60 15 <LLD N/A N/A <LLD 0 Zn-65 30 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 Nb-95 15 <LLD N/A N/A <LLD 0 Cs-134 15 <LLD N/A N/A <LLD 0 Cs-137 18 <LLD N/A N/A <LLD 0 Ba-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD 0

Attachment to 0CAN050206 Page 31 of 51 TABLE 3.1 Radioloeical 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 2001 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Mean Control Locations Number of (Units) of Analyses a Mean (F) c Mean (F) c Nonroutine

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

Bottom Sediment GS 3 (pCi/kg) Co-60 (f) 47.7(1/1) Station 8 47.7(1/1) <LLD 0

[ N/A l ( 245-, 0.7 mi) [N/A ]

Cs-134 150 <LLD N/A N/A <LLD 0 Cs-137 180 650.0(1/1) Station8 650.0(1/1) 36.2(1/2) 0

[ N/A (245, 0.7 mi) [N/A] [N/A]

Fish GS 4 (pCi/kg) Mn-54 130 <LLD N/A N/A <LLD 0 Fe-59 260 <LLD N/A N/A <LLD 0 Co-58 130 <LLD N/A N/A <LLD 0 Co-60 130 <LLD N/A N/A <LLD 0 Zn-65 260 <LLD N/A N/A <LLD 0 Cs-134 130 <LLD N/A N/A <LLD 0 Cs- 137 150 <LLD N/A N/A <LLD 0 Food Products 1-131 6 60 <LLD N/A N/A N/A 0 (pCi/kg)

GS 6 Cs-134 60 <LLD N/A N/A N/A 0 Cs-137 80 <LLD N/A N/A N/A 0 a GB = Gross beta; 1-131 = 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 0CAN050206 Page 32 of 51 Attachment 1 2001 Radiological Monitoring Report Summary of Monitoring Results

Attachment to 0CAN050206 Page 33 of 51 TABLE OF CONTENTS TABLE 1.1 AIR PARTICULATE 34 TABLE 1.2 RADIOIODINE CARTRIDGE 35 TABLE 2.1 THERMOLUMINESCENT DOSIMETERS 36 TABLE 2.2 THERMOLUMINESCENT DOSIMETERS 37 TABLE 3.1 SURFACE WATER (GAMMA ISOTOPIC) 38 TABLE 3.2 SURFACE WATER (TRITIUM) 40 TABLE 4.1 DRINKING WATER (GAMMA ISOTOPIC & 1-131) 41 TABLE 4.2 DRINKING WATER (TRITIUM) 42 TABLE 5.1 SEDIMENT 43 TABLE 6.1 FISH 44 TABLE 7.1 FOOD PRODUCTS 45 TABLE 8.1 INTERLABORATORY COMPARISON 46

Attachment to 0CAN050206 Page 34 of 51 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 4 0.01 0.01 0.01 0.01 0.01 12/19/2000 01/02/2001 0.04 0.04 0.03 0.04 0.04 01/02/2001 01/16/2001 0.03 0.03 0.03 0.03 0.03 01/16/2001 01/30/2001 0.04 0.03 0.03 0.03 0.03 01/30/2001 02/13/2001 0.02 0.02 0.02 0.02 0.02 02/13/2001 02/27/2001 0.02 0.02 0.02 0.02 0.02 02/27/2001 03/13/2001 0.03 0.03 0.03 0.02 0.03 03/13/2001 03/27/2001 0.02 0.02 0.02 0.02 0.02 03/27/2001 04/10/2001 0.02 0.02 0.02 0.02 0.02 04/10/2001 04/24/2001 0.02 0.02 0.02 0.02 0.02 04/24/2001 05/08/2001 0.03 0.02 0.02 0.03 0.02 05/08/2001 05/22/2001 0.02 0.02 0.02 0.02 0.02 05/22/2001 06/05/2001 0.02 0.02 0.01 0.02 0.02 06/05/2001 06/19/2001 0.02 0.02 0.02 0.10 0.02 06/19/2001 07/03/2001 0.02 0.02 0.02 0.02 0.02 07/03/2001 07/17/2001 0.02 0.02 0.02 0.02 0.02 07/17/2001 07/31/2001 0.03 0.03 0.03 0.02 0.02 07/31/2001 08/14/2001 0.02 0.03 0.02 0.02 0.02 08/14/2001 08/28/2001 0.03 0.03 0.03 0.03 0.03 08/28/2001 09/11/2001 0.02 0.01 0.02 0.02 0.02 09/11/2001 09/25/2001 0.04 0.03 0.03 0.03 0.03 09/25/2001 10/09/2001 0.02 0.03 0.02 0.03 0.03 10/09/2001 10/23/2001 0.02 0.02 0.02 0.02 0.03 10/23/2001 11/06/2001 0.02 0.02 0.02 0.02 0.02 11/06/2001 11/20/2001 0.05 0.05 0.04 0.05 0.04 11/20/2001 12/04/2001 0.02 0.02 0.02 0.03 0.02 12/04/2001 12/18/2001 0.02 0.02 0.02 0.02 0.02

Attachment to 0CAN050206 Page 35 of 51 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 4 0.07 0.07 0.07 0.07 0.07 12/19/2000 01/02/2001 <0.01 <0.01 <0.01 <0.01 <0.01 01/02/2001 01/16/2001 <0.01 <0.01 <0.01 <0.01 <0.01 01/16/2001 01/30/2001 <0.02 <0.02 <0.02 <0.02 <0.02 01/30/2001 02/13/2001 <0.02 <0.01 <0.02 <0.02 <0.02 02/13/2001 02/27/2001 <0.02 <0.02 <0.02 <0.02 <0.02 02/27/2001 03/13/2001 <0.01 <0.01 <0.01 <0.01 <0.01 03/13/2001 03/27/2001 <0.01 <0.01 <0.01 <0.01 <0.01 03/27/2001 04/10/2001 <0.02 <0.01 <0.01 <0.01 <0.01 04/10/2001 04/24/2001 <0.01 <0.01 <0.01 <0.01 <0.01 04/24/2001 05/08/2001 <0.02 <0.02 <0.02 <0.02 <0.02 05/08/2001 05/22/2001 <0.01 <0.01 <0.02 <0.01 <0.01 05/22/2001 06/05/2001 <0.01 <0.01 <0.01 <0.01 <0.01 06/05/2001 06/19/2001 <0.01 <0.01 <0.01 <0.05 <0.01 06/19/2001 07/03/2001 <0.02 <0.02 <0.02 <0.02 <0.02 07/03/2001 07/17/2001 <0.02 <0.02 <0.01 <0.02 <0.07 07/17/2001 07/31/2001 <0.01 <0.01 <0.02 <0.01 <0.01 07/31/2001 08/14/2001 <0.02 <0.05 <0.02 <0.02 <0.02 08/14/2001 08/28/2001 <0.02 <0.03 <0.02 <0.02 <0.02 08/28/2001 09/11/2001 <0.02 <0.03 <0.03 <0.02 <0.03 09/25/2001 <0.02 <0.01 <0.02 <0.02 <0.01 09/11/2001 09/25/2001 10/09/2001 <0.01 <0.02 <0.01 <0.01 <0.01 10/09/2001 10/23/2001 <0.02 <0.02 <0.02 <0.02 <0.02 10/23/2001 11/06/2001 <0.02 <0.02 <0.02 <0.02 <0.02 11/06/2001 11/20/2001 <0.02 <0.01 <0.02 <0.02 <0.02 11/20/2001 12/04/2001 <0.01 <0.01 <0.01 <0.02 <0.01 12/04/2001 12/18/2001 <0.01 <0.01 <0.01 <0.01 <0.01

Attachment to 0CAN050206 Page 36 ofS1 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators)

Station 1st Qtr '01 2nd Qtr '01 3rd Qtr '01 4th Qtr '01 Annual Mean '01 (mrem) (mrem) (mrem) (mrem) (mrem) 3 9.0 6.0 4.0 6.0 6.3 145 8.0 8.0 6.0 9.0 7.8 146 9.0 10.0 7.0 8.0 8.5 147 7.0 9.0 5.0 6.0 6.8 1 8.0 9.0 7.0 9.0 8.3 148 9.0 9.0 6.0 9.0 8.3 110 7.0 9.0 7.0 8.0 7.8 149 8.0 8.0 7.0 9.0 8.0 4 7.0 9.0 7.0 9.0 8.0 150 11.0 9.0 6.0 9.0 8.8 151

• 11.0 10.0 7.0 10.0 9.5 2 8.0 9.0 8.0 10.0 8.8 56 9.0 10.0 8.0 11.0 9.3 109 9.0 9.0 7.0 11.0 9.0 108 8.0 9.0 7.0 9.0 8.3 152 9.0 9.0 6.0 9.0 8.3

• Location with highest annual mean.

Attachment to 0CAN050206 Page 37 of 51 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr '01 2nd Qtr '01 3rd Qtr '01 4th Qtr '01 Annual Mean '01 (mrem) (mrem) (mrem) (mrem) (mrem) 6 7.0 8.0 6.0 8.0 7.3 111 6.0 7.0 5.0 7.0 6.3 116 7.0 7.0 6.0 9.0 7.3 125 5.0 5.0 5.0 6.0 5.3 127 7.0 8.0 Missing 9.0 8.0 137

• 8.0 9.0 8.0 9.0 8.5 153 7.0 8.0 6.0 9.0 7.5

• Location with highest annual mean.

Special Interest Areas - (Control)

Station 1st Otr '01 2nd Otr '01 3rd Otr '01 4th Otr '01 Annual Mean '01 (mrem) (mrem) (mrem) (mrem) (mrem) 7 6.0 6.0 5.0 7.0 6.0

Attachment to OCAN050206 Page 38 of 51 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Date Required LLD 4 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 12/31/2000 01/31/2001 <3.46 <8.93 <3.56 <2.69 <10.70 <6.46 <4.81 <7.77 <3.94 <4.13 <19.80 <7.24 Station 10 (Control) 12/31/2000 01/31/2001 <4.20 <7.45 <3.68 <3.64 <8.50 <6.59 <4.75 <6.06 <3.27 <3.82 <16.10 <8.08 Station 8 (Indicator) 01/31/2001 02/28/2001 <2.72 <6.25 <3.36 <2.49 <6.84 <5.22 <3.43 <5.19 <3.90 <3.76 <13.60 <4.12 Station 10 (Control) 01/31/2001 02/28/2001 <3.48 <6.89 <3.70 <3.32 <6.44 <5.39 <4.52 <5.57 <3.41 <4.39 <18.10 <5.37 Station 8 (Indicator) 02/28/2001 03/31/2001 <2.78 <5.95 <2.50 <3.42 <4.55 <6.04 <2.75 <5.36 <3.49 <4.56 <13.00 <5.95 Station 10 (Control) 02/28/2001 03/31/2001 <3.96 <7.77 <6.08 <3.07 <12.80 <5.69 <6.50 <8.50 <4.71 <4.96 <23.90 <9.19 Station 8 (Indicator) 03/31/2001 04/30/2001 <2.92 <5.86 <4.08 <3.63 <7.26 <6.73 <3.73 <8.10 <4.14 <3.06 <19.50 <8.20 Station 10 (Control) 03/31/2001 04/30/2001 <3.10 <6.71 <3.44 <3.27 <6.32 <6.36 <3.73 <8.76 <2.78 <3.59 <24.70 <8.14 Station 8 (Indicator) 04/30/2001 05/31/2001 <3.73 <7.25 <3.82 <2.67 <10.10 <6.82 <3.81 <8.21 <4.06 <3.95 <16.30 <7.73 Station 10 (Control) 04/30/2001 05/31/2001 <4.38 <6.96 <3.50 <3.87 <4.38 <6.08 <4.04 <7.02 <4.10 <4.10 <19.20 <5.90 Station 8 (Indicator) 05/31/2001 06/30/2001 <6.29 <9.59 <6.35 <5.00 <11.40 <7.57 <5.89 <7.70 <4.07 <5.64 <19.30 <6.53 Station 10 (Control) 05/31/2001 06/30/2001 <5.60 <9.85 <5.94 <4.24 <11.30 <8.70 <5.02 <7.43 <5.02 <5.48 <22.80 <8.22

Attachment to 0CAN050206 Page 39 of 51 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/I Location Start Date End Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Date Required LLD 4 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 06/30/2001 07/31/2001 <3.99 <5.91 <3.19 <3.20 <7.31 <5.53 <3.67 <5.24 <4.03 <3.52 <13.80 <6.74 Station 10 (Control) 06/30/2001 07/31/2001 <1.77 <5.83 <3.13 <3.19 <7.14 <6.64 <3.37 <5.01 <3.26 <3.18 <12.10 <4.70 Station 8 (Indicator) 07/31/2001 08/31/2001 <4.59 <6.50 <2.95 <4.81 <7.66 <6.73 <4.74 <6.25 <4.12 <3.65 <16.90 <5.97 Station 10 (Control) 07/31/2001 08/31/2001 <4.05 <5.96 <3.83 <3.12 <8.87 <5.52 <4.09 <6.06 <3.25 <3.84 <18.50 <5.28 Station 8 (Indicator) 08/31/2001 09/30/2001 <12.10 <14.50 37.20 45.50 <18.20 <14.20 16.80 <13.6 <7.23 <6.93 <39.60 <7.88 Station 8 (Indicator)

• 08/31/2001 09/30/2001 17.50 <11.00 59.10 70.30 <9.78 <12.90 20.00 <14.0 <5.85 <5.78 <38.60 <8.51 Station 10 (Control) 08/31/2001 09/30/2001 <4.80 <12.10 <4.77 <6.37 <13.40 <8.42 <8.04 <11.4 <5.69 <6.32 <29.80 <9.47 Station 8 (Indicator) 09/30/2001 10/31/2001 <4.48 <7.16 2.47 4.14 <8.14 <6.53 <5.25 <6.12 <4.19 <3.27 <20.80 <6.88 Station 10 (Control) 09/30/2001 10/31/2001 <2.92 <9.20 <4.09 <3.28 <7.54 <5.86 <3.40 <6.90 <3.73 <2.89 <19.80 <6.72 Station 8 (Indicator) 10/31/2001 11/30/2001 <3.18 <9.94 <4.01 <2.70 <6.15 <5.98 <5.58 <13.0 <3.85 <4.51 <29.40 <9.78 Station 10 (Control) 10/31/2001 11/30/2001 <2.54 <7.90 <3.74 <2.39 <5.47 <7.95 <4.84 <11.6 <3.92 <3.66 <22.50 <9.73 Station 8 (Indicator) 11/30/2001 12/31/2001 <3.20 <7.37 <2.71 <3.86 <7.07 <5.75 <4.13 <7.91 <3.16 <3.28 <19.10 <7.16 Station 10 (Control) 11/30/2001 12/31/2001 <4.43 <8.78 <3.85 <4.68 <8.37 <5.33 <4.41 <6.88 <3.62 <3.68 <20.30 <5.70 sample.

Attachment to 0CAN050206 Page 40 of 51 Table 3.2 Sample Type: Surface Water Analysis: Tritium Units: pCi/1 Location Begin Date End Date H-3 Required LLD 4 3000 Station 8 (Indicator) 12/31/2000 03/31/2001 1,761.00 Station 10 (Control) 12/31/2000 03/31/2001 <565.00 Station 8 (Indicator) 03/31/2001 06/30/2001 537.00 Station 10 (Control) 03/31/2001 06/30/2001 <527.00 Station 8 (Indicator) 06/30/2001 09/30/2001 492.00 Station 10 (Control) 06/30/2001 09/30/2001 <541.00 Station 8 (Indicator) 09/30/2001 12/31/2001 689.00 Station 10 (Control) 09/30/2001 12/31/2001 <537.00

Attachment to 0CAN050206 Page 41 of 51 Table 4.1 Sample Type: Drinking Water Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Units: pCi/I Location Collection Gross 1-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Date Beta Required LLD 4 4.0 1.0 15 30 15 15 30 30 15 15 18 60 15 Station 14 (Indicator) 03/07/2001 2.44 <0.89 <1.19 <2.31 <1.18 <1.18 <2.38 <2.23 <1.37 <1.30 <1.38 <6.25 <1.92 Station 57 (Control) 03/07/2001 2.03 <0.83 <0.99 <2.11 <1.04 <1.02 <2.02 <1.90 <1.11 <1.16 <1.03 <5.02 <1.74 Station 14 (Indicator) 06/12/2001 <1.59 <0.88 <4.87 <5.60 <4.77 <4.86 <11.80 <5.87 <5.48 <5.11 <4.03 <22.10 <10.70 Station 57 (Control) 06/12/2001 <1.65 <0.89 <3.71 <6.75 <4.82 <4.80 <5.81 <4.58 <5.42 <5.51 <4.31 <18.00 <7.40 Station 14 (Indicator) 09/19/2001 1.69 <0.90 <3.33 <9.40 <4.14 <3.67 <9.33 <8.65 <6.25 <5.26 <5.62 <12.30 <6.93 Station 57 (Control) 09/19/2001 2.70 <0.90 <6.35 <7.09 <5.54 <5.75 <8.56 <11.60 <4.42 <5.17 <6.12 <24.60 <4.03 Station 14 (Indicator) 12/07/2001 2.33 <0.98 <3.17 <8.37 <2.97 <3.34 <8.77 <6.63 <4.51 <3.80 <3.42 <14.70 <5.10 Station 57 (Control) 12/07/2001 2.25 <0.90 <2.91 <5.63 <2.41 <2.61 <5.32 <4.61 <2.95 <3.26 <3.04 <11.40 <3.81

Attachment to 0CAN050206 Page 42 of 51 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/1 Location Collection Date H-3 Required LLD 4 2000 Station 14 (Indicator) 03/07/2001 <561.00 Station 57 (Control) 03/07/2001 <560.00 Station 14 (Indicator) 06/12/2001 <524.00 Station 57 (Control) 06/12/2001 <520.00 Station 14 (Indicator) 09/19/2001 <560.00 Station 57 (Control) 09/19/2001 <558.00 Station 14 (Indicator) 12/07/2001 <549.00 Station 57 (Control) 12/07/2001 <544.00

Attachment to OCAN050206 Page 43 of 51 Table 5.1 Sample Type: Sediment Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Co-60 Cs-134 Cs-137 Required LLD -- NA 150 180 Station 8 (Indicator) 09/21/2001 47.70 <150.00 650.00 Station 16 (Control) 09/25/2001 <99.9 <122.00 <98.70 Station 16 (Control) 09/25/2001 <78.3 <102.00 36.20

Attachment to 0CAN050206 Page 44 of 51 Table 6.1 Sample Type: Fish Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Required LLD 4 130 260 130 130 260 130 150 Station 8 (Indicator) 09/11/2001 <8.73 <26.00 <10.30 <8.90 <19.20 <6.55 <8.00 Station 16 (Control) 09/11/2001 <15.70 <64.60 <21.90 <9.48 <43.70 <10.60 <12.90 Station 8 (Indicator) 09/20/2001 <15.40 <48.50 <14.10 <17.40 <34.70 <13.30 <11.70 Station 16 (Control) 09/20/2001 <7.53 <22.90 <7.82 <6.79 <24.10 <7.36 <7.40

Attachment to 0CAN050206 Page 45 of 51 Table 7.1 Sample Type: Food Products Analysis: Iodine-131 and Gamma Isotopic Units: pCi/kg Location Collection Date 1-131 Cs-134 Cs-137 Required LLD + 60 60 80 Station 13 (Indicator) 06/12/2001 <28.90 <21.30 <16.80 Station 55 (Control) 06/13/2001 <55.00 <28.00 <26.00 Station 13 (Indicator) 07/11/2001 <59.50 <42.00 <34.40 Station 55 (Control) 07/11/2001 <43.50 <39.70 <56.00 Station 13 (Indicator) 08/08/2001 <59.70 <25.10 <33.40 Station 55 (Control) 08/08/2001 <45.00 <16.50 <25.90

Attachment to 0CAN050206 Page 46 of 51 Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Gross Beta, Iodine- 13 1 and Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value a Value N-Dev b N-Range' Air Filter E2818-125 09/20/01 BETA 90.0 L 17.3 93.0 0.60 0.065 (pCi/filter) I Charcoal E2673A-125 06/14/01 1-131 80.0 +/- 13.9 79.8 -0.04 0.148 Cartridge (pCi/cartridge) E2908-125 12/06/01 1-131 91.0 +/- 90.8 -0.03 0.467 15.8 Water E2576-125 03/22/01 BETA 168 +/- 43.7 162 -0.44 0.211 (pCi/liter) E2574-125 03/22/01 CR-51 242 +/- 21.0 240 -0.29 0.391 MN-54 101 +/- 8.75 104 1.03 0.234 CO-58 48.0 +/- 8.66 47.2 -0.28 0.189 FE-59 84.0 1 8.66 89.5 1.91 0.992 CO-60 147 12.7 144 -0.63 0.643 ZN-65 186 32.2 180 -0.59 0.064 1-131 90.0 +/-15.6 89.6 -0.08 0.965 CS-134 129 +/- 11.2 132 0.90 0.733 CS-137 102 +/- 8.83 101 -0.37 0.845 CE-141 94.0 L 8.66 93.4 -0.21 0.697 E2575-125 03/22/01 CR-51 242 +/- 21.0 251 1.24 2.734 (Duplicate) MN-54 101 +/- 8.75 103 0.57 0.234 CO-58 48.0 +/- 8.66 52.3 1.48 0.295 FE-59 84.0 +/- 8.66 91.6 2.63 0.697 CO-60 147 +/- 12.7 140 -1.57 0.321 ZN-65 186 +/- 32.2 187 0.09 0.349 1-131 90.0 +/-15.6 93.7 0.72 1.523 CS-134 129 +/- 11.2 128.7 -0.09 0.733 CS-137 102 +/- 8.83 99.8 -0.76 0.220 CE-141 94.0 +/- 8.66 94.9 0.32 0.591

Attachment to 0CAN050206 Page 47 of 51 Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Tritium and Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value ' Value N-Dev b N-Range' Water E2674-125 06/14/01 H-3 7494 +/- 1298 7635 0.33 0.130 (pCi/liter) E2816-125 09/20/01 CR-51 265 +/- 23.0 269 0.48 1.382 MN-54 149 +/- 12.9 155 1.39 0.000 CO-58 128 +/- 11.1 127 -0.27 0.369 FE-59 62.0 + 8.66 70.0 2.84 0.473 CO-60 193 +/- 16.7 197 0.78 0.551 ZN-65 184 31.9 185 0.06 0.032 1-131 60.0 10.4 59.0 -0.19 0.276 CS-134 116 10.1 109 -2.09 0.204 CS-137 232 20.1 233 0.15 0.815 CE-141 88.0 8.66 91.0 1.17 1.004 E2817-125 9/20/01 CR-51 265 23.0 269 0.57 0.401 (Duplicate) MN-54 149 12.9 155 1.47 0.159 CO-58 128 11.1 128 0.09 0.646 FE-59 62.0 +/- 8.66 71 3.24 d 0.366 CO-60 193 + 16.7 195 0.30 0.796 ZN-65 184 31.9 189 0.44 0.225 1-131 60.0 - 10.4 59.7 -0.09 0.226 CS-134 116 10.1 111 -1.39 0.306 CS-137 232 20.1 230 -0.35 0.153 CE-141 88.0 + 8.66 94 2.24 0.236

Attachment to 0CAN050206 Page 48 of 51 Table 8.1 Sample Type: Interlaboratory Comparison Analysis: Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value a Value N-Dev b N-Range' Sediment E2909-125 12/6/01 CR-51 0.631 +/- 0.055 0.613 -0.97 0.600 (pCi/gram) MN-54 0.189 +/- 0.033 0.207 1.69 0.241 Co-58 0.115 +/- 0.010 0.117 0.68 0.267 FE-59 0.129 +/- 0.022 0.145 2.10 0.545 CO-60 0.449 +/- 0.039 0.465 1.21 0.465 ZN-65 0.262 +/- 0.045 0.288 1.70 0.187 CS-134 0.252 +/- 0.022 0.250 -0.29 0.319 CS-137 0.531+/- 0.046 0.537 0.39 0.707 CE-141 0.481 +/- 0.042 0.498 1.20 0.069 NOTES:

(a) The "known" values are listed with a range reflecting control (3 sigma) limits.

(b) The normalized deviation from the "known" value is computed from the deviation and the standard error of the mean; +/-2.000 is the warning limit and +/-3.000 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) The results reported were out of the control limits.

Attachment to 0CAN050206 Page 49 of 51 Interlaboratory Comparison Program Exceptions There was one result outside the control limits for accuracy in the 2001 cross check program participation studies. This result was in a gamma isotopic analysis of water sample.

The study result outside the control limits for accuracy was in the analysis of the September 20, 2001 Fe-59 nuclide sample study, which is a duplicate sample for that study. The Fe-59 result was within control limits for the other water sample in this quarterly study. RBS normalized-deviation for the analysis was +3.24 with control limits of +/-3.00. This high bias result is considered conservative and is considered as having no impact on past results of the program. The bias high result for Fe-59 is contributed to coincidence summing effects. A coincidence summing correction was employed in the past, but was discontinued due to the production of non-conservative low-bias results.

Fe-59 results were all within control limits in other crosscheck samples for the year 2001.

The normalized-deviations for Fe-59 in other samples during year 2001 were 1.91, 2.63, 2.84, and 2.10.

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

Environmental samples are analyzed and reported with a ninety-five percent confidence level that the analytical result with its associated error encompasses the "true" value.

Ninety-six percent of RBS environmental crosscheck results were within control limits for accuracy and precision during 2001.

Attachment to OCAN050206 Page 50 of 51 ATTACHMENT 2 Sediment Dose Calculations

Attachment to OCAN050206 Page 51 of 51 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 = 2001 maximum radionuclide concentration in pCi/kg; U = Maximum exposure time given in Table E-5 of Regulatory Guide 1.109 (67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> for teenager);

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

(Dose from Sediment in Millirem/Year)

Radionuclide 2001 Maximum Conversion Factor Total Conversion Factor Total Concentration For Skin Skin Dose For Total Body Body Dose Co-60 47.7 2.00 E-08 2.56 E-04 1.70 E-08 2.17 E-04 Cs-137 650.0 4.90 E-09 8.54 E-04 4.20 E-09 7.32 E-04 TOTAL 1.11 E-03 9.49 E-04