0CAN050901, Annual Radiological Environmental Operating Report for 2008

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Annual Radiological Environmental Operating Report for 2008
ML091340499
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 05/13/2009
From: David Bice
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
0CAN050901
Download: ML091340499 (55)
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Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4710 David B. Bice Acting Manager, Licensing Arkansas Nuclear One 0CAN050901 May 13, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Annual Radiological Environmental Operating Report for 2008 Arkansas Nuclear One, Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

REFERENCES:

1. Arkansas Nuclear One, Unit 1, Technical Specification 5.6.2
2. Arkansas Nuclear One, Unit 2, Technical Specification 6.6.2

Dear Sir or Madam:

The referenced Arkansas Nuclear One (ANO) Technical Specifications (TSs) require the submittal of an annual radiological environmental operating report for the previous year by May 15 of each year. Attached is the subject ANO report for the calendar year 2008.

This report fulfills the reporting requirements of TSs referenced above.

The radionuclides detected by the radiological environmental monitoring program during 2008 were significantly below the regulatory limits. The operation of the ANO station during 2008 had no harmful effects nor resulted in any irreversible damage to the local environment.

Based on Entergys review, no environmental samples from the monitoring program equated or exceeded the reporting levels for radioactivity concentration due to ANO effluents when averaged over any calendar quarter. Therefore the 2008 results did not require any Radiological Monitoring Program Special Reports.

This letter contains no new commitments.

0CAN050901 Page 2 If you have any questions or require additional information, please contact me.

Sincerely, Original signed by F. Van Buskirk for D. Bice DBB/rwc

Attachment:

Annual Radiological Environmental Operating Report for 2008 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

ARKANSAS NUCLEAR ONE - UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2008

Attachment to 0CAN050901 Page 2 of 53 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 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 24 2.6 Fish Sample Results 24 2.7 Food Product Sample Results 24 2.8 Land Use Census Results 25 2.9 Interlaboratory Comparison Results 25 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

27 3.1 2008 Program Results Summary 27

Attachment to 0CAN050901 Page 3 of 53 LIST OF TABLES TABLE 1.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM 12 TABLE 2.1 2007 LAND USE CENSUS 26 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

28

Attachment to 0CAN050901 Page 4 of 53 LIST OF FIGURES FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD 18 FIGURE 1-2 SAMPLE COLLECTION SITES - FAR FIELD 19 FIGURE 1-3 SAMPLE COLLECTION SITES - SITE MAP 20

Attachment to 0CAN050901 Page 5 of 53 LIST OF ATTACHMENTS ATTACHMENT 1 2008 RADIOLOGICAL MONITORING REPORT

SUMMARY

OF MONITORING RESULTS 32 ATTACHMENT 2 INTERLABORATORY COMPARISON PROGRAM 48 ATTACHMENT 3 SEDIMENT DOSE CALCULATIONS 52

Attachment to 0CAN050901 Page 6 of 53 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, through December 31, 2008. This report fulfills the requirements of ANO Unit 1 Technical Specification 5.6.2 and Unit 2 Technical Specification 6.6.2.

During 2008 as in previous years, Entergy 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 2008 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 Entergy established the REMP prior to the station becoming operational (1974) to provide data on background radiation and radioactivity normally present in the area. Entergy has continued to monitor the environment by sampling air, water, sediment, fish and food products, as well as measuring radiation directly. Entergy 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 pre-operational results to assess any impact ANO operation might have had on the surrounding environment.

Attachment to 0CAN050901 Page 7 of 53 In 2008, 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 2008 data, in many cases, showed undetectable radiation levels in the environment and in all instances, no definable trends related to significant pathways associated with ANO.

Harmful Effects or Irreversible Damage The REMP monitoring did not detect any harmful effects or evidence of irreversible damage in 2008. Therefore, no analysis or planned course of action to alleviate problems was necessary.

Reporting Levels Entergy'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 ODCM Table 2.6-3, when averaged over any calendar quarter. Therefore, 2008 results did not trigger any Radiological Monitoring Program Special Reports.

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

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

The NRC Thermoluminescent Dosimeter Network Program was discontinued in 1998.

Historically these results have compared to those from the ANO REMP. ANO Thermoluminescent Dosimeter results continue to remain similar to the historical average and continue to verify that plant operation is not affecting the ambient radiation levels in the environment.

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

Attachment to 0CAN050901 Page 8 of 53 Sample Deviations Milk The REMP did not include milk sampling within five miles (8 km) of ANO in 2008 due to unavailability. ANO Units 1 and 2 ODCM require collection of milk samples if available commercially within 8 km (5 miles) of the plant. ANO personnel collected vegetation samples to monitor the ingestion pathway, as specified in the ODCM, because of milk unavailability.

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

Air Samples Listed below are air sampler deviations that occurred during 2008 due to hazardous weather conditions, 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 ALL 02/19/08 - 03/04/08 Due to hazardous weather conditions the bi-weekly air sample stations were not collected as scheduled. The air samples were collected the following day (03/05/08).

CR-ANO-C-2008-00445 7 04/15/08 - 04/29/08 Air sample station totalizer recorded ~ 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> run time. Normal run time = 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />. This condition is typical of a power failure.

CR-ANO-C-2008-00909 7 04/29/08 - 05/13/08 Air sample station totalizer not operating.

Totalizer replaced.

CR-ANO-C-2008-00985 1 05/13/08 - 05/27/08 Air sample station found not running.

Estimated air pump off for 208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br />. Reset Ground Fault Circuit Interrupter.

CR-ANO-C-2008-01067 2 11/25/08 - 12/09/08 Air sample station totalizer did not change.

Totalizer replaced.

CR-ANO-C-2008-02584

Attachment to 0CAN050901 Page 9 of 53 Missed Samples There were no missed REMP samples during 2008.

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

Program Modifications ANO made no modifications to the REMP during 2008.

Attachments contains results of air, TLD, water, sediment, fish, and food product samples collected in 2008. TLDs were analyzed by vendor (AREVA). All remaining samples were analyzed by River Bend Stations (RBSs) Environmental Laboratory. also contains RBSs participation in the interlaboratory comparison program during 2008. 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.

Attachment to 0CAN050901 Page 10 of 53 1.0 Introduction 1.1 Radiological Environmental Monitoring Program Entergy established the REMP to ensure that plant operating controls properly function to minimize any associated radiation endangerment to human health or the environment. The REMP is designed for:

  • Analyzing applicable pathways for anticipated types and quantities of radionuclides released into the environment.
  • Considering the possibility of a buildup of long-lived radionuclides in the environment and identifying physical and biological accumulations that may contribute to human exposures.
  • Considering the potential radiation exposure to plant and animal life in the environment surrounding ANO.
  • Correlating levels of radiation and radioactivity in the environment with radioactive releases from station operation.

1.2 Pathways Monitored The airborne, direct radiation, waterborne and ingestion pathways are monitored as required by the 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, 1-2 and 1-3.

Section 2.0 of this report provides a discussion of 2008 sampling results and Section 3.0 provides a summary of results for the monitored exposure pathways.

Attachment to 0CAN050901 Page 11 of 53 1.3 Land Use Census ANO personnel conducts land use census biannually (once every two years) as required by ANO Units 1 and Unit 2 ODCM Section 2.6.2. The latest land use census was conducted in 2007. The purpose of this census is to identify changes in uses of land within five miles of ANO that would require modifications to the REMP or ODCM. The most important criteria during this census are to determine location in each sector of the nearest:

1) Residence
2) Animal milked for human consumption
3) Garden of greater than 500 square feet producing fresh leafy (broadleaf) vegetables *
  • ANO personnel do not perform a garden census since ODCM Section 2.6.2 allows the routine sampling of broadleaf vegetation in the highest D/Q sector near the site boundary in lieu of the garden census.

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 global positioning system) and record results.
  • Locations, if any, are identified which yield a calculated dose or dose commitments greater than those currently calculated in the ODCM.
  • ANO personnel compare results to previous census.

Attachment to 0CAN050901 Page 12 of 53 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 (243° - 0.5 miles) - South of the Continuous operation of Radioiodine Canister - Analyze at (or near) different sectors with the highest sewage treatment plant. sampler with sample least once per 14 days for I-131.

calculated annual average ground level collection as required by Station 56 (264° - 0.4 miles) - West end of the D/Q. dust loading but at least Particulate Sampler - Analyze for sewage treatment plant.

once per 14 days. gross beta radioactivity following filter change.

Radioiodine and Particulates 1 sample from the vicinity of a community Station 6 (111° - 6.8 miles) - Entergy local having the highest calculated annual office in Russellville (305 South Knoxville Avenue).

average ground level D/Q.

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

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

Direct Thermoluminescent dosimetry (TLDs)

Radiation 16 inner ring stations with two or more Station 1 (88° - 0.5 miles) - On a pole near the Once per 92 days. Gamma Dose - Once per 92 days.

dosimeters in each meteorological sector meteorology tower.

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

Station 3 (5° - 0.7 miles) - West of ANO Gate

  1. 2 on Highway 333 (approximately 0.35 miles)

Attachment to 0CAN050901 Page 13 of 53 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 (181° - 0.5 miles) - West of May Once per 92 days. Gamma Dose - Once per 92 dosimeters in each meteorological Cemetery entrance on south side of the road. days.

sector in the general area of the Site Station 56 (264° - 0.4 miles) - West end of the Boundary. sewage treatment plant.

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

Station 109 (291° - 0.6 miles) - Utility pole across from the junction of Flatwood Road and Round Mountain Road.

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

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

Station 146 (45° - 0.6 miles) - South end of east parking lot at RERTC on a utility pole.

Station 147 (61° - 0.6 miles) - West side of Bunker Hill Road, approximately 100 yards from intersection with State Highway 333.

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

Attachment to 0CAN050901 Page 14 of 53 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 (156° - 0.5 miles) - On a utility pole Once per 92 days. Gamma Dose - Once per 92 dosimeters in each meteorological on the south side of May Road. days.

sector in the general area of the Site Station 150 (205° - 0.6 miles) - North side of Boundary. May Road on a utility pole past the McCurley Place turn.

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

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

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

population centers, nearby residences, Station 7 (210° - 19.0 miles) - Entergy Supply schools, and in 1 - 2 areas to serve as Yard on Highway 10 in Danville.

control locations.

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 0CAN050901 Page 15 of 53 Table 1.1 Radiological Environmental Sampling Program Exposure Requirement Sample Point Description, Sampling and Type and Frequency Pathway Distance and Direction Collection Frequency Of Analyses Direct TLDs Radiation 8 stations with two or more dosimeters Station 125 (46° - 8.7 miles) - College Street on Once per 92 days. Gamma Dose - Once per 92 in special interest areas such as a utility pole at the southeast corner of the red days.

brick school building.

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

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

Station 153 (304° - 9.2 miles) - Knoxville Elementary School near the school entrance gate on a utility pole.

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

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

plant discharge)

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

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

Attachment to 0CAN050901 Page 16 of 53 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 plant Station 8 (243° - 0.9 miles) - Plant discharge Once per 365 days. Gamma isotopic analysis once discharge) canal. per 365 days.

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

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

analyses once per 92 days.

available.

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) - Plant discharge Once per 365 days. Gamma isotopic on edible recreationally important species in canal. portions once per 365 days.

vicinity of plant discharge.

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

Attachment to 0CAN050901 Page 17 of 53 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 (273° - 0.5 miles) - West from ANO Three per 365 days. Gamma isotopic and I-131 edible) near the Site Boundary from toward Gate 4 onto Flatwood Road. analyses three times per 365 one of the highest anticipated annual average ground level D/Q sectors, if days.

milk sampling is not performed.

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

a control location 15 - 30 km (10 - 20 miles) distant, if milk sampling is not performed.

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

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

and discharge canal.

Station 60 (GWM-3, 206° - 0.1 miles) - South of Once per 92 days Indicator, Tritium and Gamma Protected area on OCA. West of Station number 59 near wood line. Isotopic, once per 92 days.

Station 61 (GWM-4, 245° - 0.1 miles) - West of Once per 92 days Indicator, Tritium and Gamma Protected Area no OCA. Edge of parking lot, Isotopic, once per 92 days.

east of equipment laydown area

Attachment to 0CAN050901 Page 18 of 53 FIGURE 1-1 SAMPLE COLLECTION SITES - NEAR FIELD SR 333 152 3 108 Training 145 Center 146 109 147 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 0CAN050901 Page 19 of 55 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 0CAN050901 Page 20 of 55 FIGURE 1-3 SAMPLE COLLECTION SITES - SITE MAP 58 STR-3 Switch STR-2 Yard STR-4 West Access Road 61 STR-5 60 59 STR-1 N

Lake Dardanelle W E S

Arkansas Nuclear One REMP Sample Locations Site Map

Attachment to 0CAN050901 Page 21 of 55 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 2008, 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 2008 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 - 2007 (Minimum Value) 0.020 2008 Value 0.032 2000 - 2007 (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 Entergy 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. Entergys 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. Entergys 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, Entergy considers the difference to be insignificant since the dose rates remain well below the limitations of 10 CFR 20.1301(a)(1) and 10CFR 20.1302(b)(2)(ii), and since there has been no identifiable trends associated with these stations. In addition, Entergy utilized a different vendor for TLD processing in 2008. Therefore, these increases can also be attributed to differences in dosimeter processing.

Attachment to 0CAN050901 Page 22 of 55 Overall, Entergy concluded that the ambient radiation levels are not being affected by plant operations.

2.3 Water Sample Results Analytical results for 2008 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 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 - 2007 (Minimum Value) 272.0 2008 Value 1023.3 2000 - 2007 (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 2008 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 2008 and levels of radionuclides remain similar to those obtained in previous operational years.

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

Drinking water samples were analyzed for gross beta radionuclides, Iodine-131, gamma radionuclides and tritium. Gamma radionuclides, Iodine-131 and tritium concentrations were below the LLD limits at the indicator and control locations, which is consistent with preoperational and operational years. Gross beta concentrations at the indicator and control locations are similar as shown in Table 3.1. Listed below is a comparison of 2008 indicator results to preoperational and operational years. Results are reported as annual average pCi/l.

Attachment to 0CAN050901 Page 23 of 55 Radionuclide 2008 2000 - 2007 Preoperational Gross Beta 1.64 3.24 2.0 Iodine-131 < LLD < LLD < LLD Gammas < LLD < LLD < LLD Tritium < LLD < LLD 200.0 ANO personnel have noted no definable trends associated with drinking water results at the indicator location. Therefore, the operation of ANO had no definable impact on this waterborne pathway during 2008 and levels of radionuclides remain similar to those obtained in previous operational years.

Groundwater samples were collected from four locations (1 - control, and 3 - indicator locations).

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

Listed below is a comparison of 2008 indicator results to past operational years. Results are reported as annual average pCi/l. Groundwater data is captured in Tables 8.1 and 8.2.

Radionuclide 2008 2006 - 2007 Tritium < LLD < LLD Gammas < LLD < LLD 2.4 Sediment Sample Results Sediment samples were collected from two locations in 2008 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 2008 were actually below the minimum range of previous operational levels as seen below. Results are reported as annual average pCi/kg.

Attachment to 0CAN050901 Page 24 of 55 Monitoring Period Concentration 2000 - 2007 (Minimum Value) 97.78 2008 Value 41.79 2000 - 2007 (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 . The annual maximum dose from Cesium-137 to the skin and total body was calculated to be < 0.01 mrem.

Design objectives given in 10CFR50, Appendix I for liquid effluents are annual doses of 3 mrem total body and 10 mrem any organ. The values of < 0.01 mrem for the skin and total body are well within the design objective criteria. Therefore, the level of Cesium-137 detected in 2008 had no significant impact on the environment or public by this waterborne pathway.

2.5 Milk Sample Results Milk samples were not collected during 2008 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.

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 2008, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2008 levels remained undetectable, as has been the case in previous years. Therefore, based on these measurements, ANO operations had no significant radiological impact upon the environment or public by this ingestion pathway.

Attachment to 0CAN050901 Page 25 of 55 2.8 Land Use Census Results The latest land use census (performed in 2007) did not identify any new locations that yielded a calculated dose or dose commitment greater than those currently calculated. (see Table 2.1)

Also, the land use census identified no milk-producing animals within a five-mile radius of the plant site. ANO personnel chose not to perform a garden census in 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 RBSs Environmental Laboratory analyzed interlaboratory comparison samples for ANO to fulfill the requirements of ANO Units 1 and 2 ODCM Section 2.6.3. Attachment 2 contains these results. Entergys review of RBSs interlaboratory comparison indicated that 100% of the sample results (40 of 40) were within the acceptable control limits of the three normalized deviations.

Attachment to 0CAN050901 Page 26 of 55 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 0CAN050901 Page 27 of 55 3.0 Radiological Environmental Monitoring Program Summary 3.1 2008 Program Results Summary Table 3.1 summarizes the 2008 REMP results. ANO personnel did not use values reported as less than the LLD when determining ranges and means for indicator and control locations.

Attachment to 0CAN050901 Page 28 of 55 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 2008 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Mean Control Number of

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

[ Range ] Mean ( F ) c Results e

[ Range ]

Mean ( F ) c Location d [ Range ]

Air Particulates GB 140 0.01 0.032 ( 81 / 81 ) Station 1 0.032 ( 27 / 27 ) 0.030 ( 54 / 54 ) 0

( pCi/m3 ) [ 0.017 - 0.065 ] ( 88°, 0.5 mi ) [ 0.018 - 0.045 ] [ 0.015 - 0.0924 ]

Airborne Iodine I-131 140 0.07 < LLD N/A N/A < LLD 0

( pCi/m3 )

Inner Ring TLDs Gamma 64 (f) 8.1 ( 64 / 64 ) Station 56 9.7 ( 4 / 4 ) N/A 0

( mR/Qtr ) [ 4.9 - 10.6 ] ( 264°, 0.4 mi ) [ 9.1 - 10.6 ]

Special Interest Gamma 28 (f) 7.1 ( 28 / 28 ) Station 127 8.7 ( 4 / 4 ) N/A 0 TLDs [ 4.6 - 9.6 ] ( 100°, 5.2 mi ) [ 8.0 - 9.6 ]

( mR/Qtr )

Gamma 4 (f) N/A N/A N/A 7.3 ( 4 / 4 ) 0 Control TLD [ 7.1 - 7.6 ]

( mR/Qtr )

Attachment to 0CAN050901 Page 29 of 55 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 2008 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Control Number of

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

[ Range ] Mean ( F ) c Results e

[ Range ]

Mean ( F ) c Location d [ Range ]

Surface Water H-3 8 3000 1023.3 ( 4 / 4 ) Station 8 1023.3 ( 3 / 4 ) < LLD 0

( pCi/l ) [ 521.0 - 1548.0 ] ( 166°, 0.2 mi ) [ 521.0 - 1548.0 ]

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

Attachment to 0CAN050901 Page 30 of 55 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 2008 Sample Type Type & LLD b Indicator Locations Location with Highest Annual Control Locations Number of

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

Drinking Water GB 8 4 1.64 ( 3 / 4 ) Station 14 1.64 ( 3 / 4 ) 1.77 ( 4 / 4 ) 0

( pCi/1 ) [ 0.92 - 3.44 ] ( 70°, 5.1 mi ) [ 0.92 - 3.44 ] [ 0.92 - 3.53 ]

I-131 8 1.0 < LLD N/A N/A < LLD 0 H-3 8 2000 < LLD N/A N/A < LLD 0 GS 8 Mn-54 15 < LLD N/A N/A < LLD 0 Fe-59 30 < LLD N/A N/A < LLD 0 Co-58 15 < LLD N/A N/A < LLD 0 Co-60 15 < LLD N/A N/A < LLD 0 Zn-65 30 < LLD N/A N/A < LLD 0 Zr-95 30 < LLD N/A N/A < LLD 0 Nb-95 15 < LLD N/A N/A < LLD 0 Cs-134 15 < LLD N/A N/A < LLD 0 Cs-137 18 < LLD N/A N/A < LLD 0 Ba-140 60 < LLD N/A N/A < LLD 0 La-140 15 < LLD N/A N/A < LLD 0 Bottom Sediment GS 2

( pCi/kg ) Cs-134 150 < LLD N/A N/A < LLD 0 Cs-137 180 41.79 ( 1 / 1 ) Station 8 41.79 ( 1 / 1 ) < LLD 0

[ N/A ] ( 243°, 0.9 mi ) [ N/A ]

Attachment to 0CAN050901 Page 31 of 55 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 2008 Sample Type Type & Number LLD b Indicator Location Location with Highest Annual Control Number of

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

[ Range ] Mean ( F ) c Results e

[ Range ]

Mean ( F ) c Location d [ Range ]

Fish GS 2

( pCi/kg ) Mn-54 130 < LLD N/A N/A < LLD 0 Fe-59 260 < LLD N/A N/A < LLD 0 Co-58 130 < LLD N/A N/A < LLD 0 Co-60 130 < LLD N/A N/A < LLD 0 Zn-65 260 < LLD N/A N/A < LLD 0 Cs-134 130 < LLD N/A N/A < LLD 0 Cs-137 150 < LLD N/A N/A < LLD 0 Food Products 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 0CAN050901 Page 32 of 55 ATTACHMENT 1 2008 Radiological Monitoring Report Summary of Monitoring Results

Attachment to 0CAN050901 Page 33 of 55 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 43 TABLE 6.1 FISH 44 TABLE 7.1 FOOD PRODUCTS 45 TABLE 8.1 GROUNDWATER DATA (I-131 AND GAMMA ISOTOPIC) 46 TABLE 8.2 GROUNDWATER DATA (TRITIUM) 47

Attachment to 0CAN050901 Page 34 of 55 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 12/20/2007 01/02/2008 0.032 0.033 0.031 0.028 0.027 01/02/2008 01/08/2008 0.028 0.032 0.033 0.027 0.028 01/08/2008 01/22/2008 0.038 0.040 0.036 0.034 0.034 01/22/2008 02/05/2008 0.038 0.039 0.040 0.031 0.035 02/05/2008 02/19/2008 0.035 0.033 0.031 0.027 0.030 02/19/2008 03/05/2008 0.026 0.025 0.026 0.022 0.024 03/05/2008 03/18/2008 0.031 0.032 0.031 0.022 0.026 03/18/2008 04/01/2008 0.020 0.023 0.023 0.018 0.021 04/01/2008 04/15/2008 0.021 0.022 0.023 0.020 0.023 04/15/2008 04/29/2008 0.027 0.026 0.027 0.023 0.092 04/29/2008 05/13/2008 0.024 0.024 0.023 0.020 0.023 05/13/2008 05/27/2008 0.032 0.025 0.025 0.021 0.023 05/27/2008 06/10/2008 0.018 0.017 0.017 0.015 0.016 06/10/2008 06/24/2008 0.023 0.024 0.024 0.021 0.022 06/24/2008 07/08/2008 0.029 0.026 0.027 0.022 0.026 07/08/2008 07/22/2008 0.033 0.033 0.033 0.028 0.031 07/22/2008 08/05/2008 0.036 0.036 0.036 0.030 0.034 08/05/2008 08/19/2008 0.038 0.037 0.036 0.030 0.033 08/19/2008 09/02/2008 0.037 0.034 0.035 0.035 0.032 09/02/2008 09/16/2008 0.025 0.023 0.023 0.023 0.023 09/16/2008 09/30/2008 0.045 0.045 0.041 0.041 0.038 09/30/2008 10/14/2008 0.031 0.031 0.029 0.029 0.027 10/14/2008 10/28/2008 0.032 0.034 0.031 0.031 0.029 10/28/2008 11/11/2008 0.037 0.035 0.034 0.034 0.034 11/11/2008 11/25/2008 0.034 0.040 0.031 0.031 0.032 11/25/2008 12/09/2008 0.045 0.043 0.042 0.042 0.041 12/09/2008 12/17/2008 0.035 0.034 0.037 0.037 0.033 12/17/2008 12/29/2008 0.045 0.046 0.065 0.065 0.040

  • Station with highest annual mean.

Attachment to 0CAN050901 Page 35 of 55 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 12/20/2007 01/02/2008 < 0.020 < 0.023 < 0.018 < 0.018 < 0.019 01/02/2008 01/08/2008 < 0.021 < 0.022 < 0.023 < 0.023 < 0.022 01/08/2008 01/22/2008 < 0.012 < 0.012 < 0.012 < 0.012 < 0.016 01/22/2008 02/05/2008 < 0.017 < 0.014 < 0.015 < 0.015 < 0.013 02/05/2008 02/19/2008 < 0.015 < 0.022 < 0.015 < 0.015 < 0.013 02/19/2008 03/05/2008 < 0.017 < 0.013 < 0.013 < 0.013 < 0.018 03/05/2008 03/18/2008 < 0.018 < 0.021 < 0.018 < 0.018 < 0.018 03/18/2008 04/01/2008 < 0.018 < 0.018 < 0.015 < 0.015 < 0.018 04/01/2008 04/15/2008 < 0.018 < 0.023 < 0.020 < 0.020 < 0.015 04/15/2008 04/29/2008 < 0.014 < 0.017 < 0.019 < 0.019 < 0.056 04/29/2008 05/13/2008 < 0.018 < 0.018 < 0.022 < 0.022 < 0.017 05/13/2008 05/27/2008 < 0.005 < 0.020 < 0.023 < 0.023 < 0.016 05/27/2008 06/10/2008 < 0.019 < 0.026 < 0.018 < 0.018 < 0.016 06/10/2008 06/24/2008 < 0.023 < 0.019 < 0.020 < 0.020 < 0.018 06/24/2008 07/08/2008 < 0.019 < 0.019 < 0.022 < 0.022 < 0.021 07/08/2008 07/24/2008 < 0.022 < 0.019 < 0.019 < 0.019 < 0.021 07/24/2008 08/05/2008 < 0.019 < 0.020 < 0.019 < 0.019 < 0.017 08/05/2008 08/19/2008 < 0.017 < 0.020 < 0.019 < 0.019 < 0.019 08/19/2008 09/02/2008 < 0.020 < 0.018 < 0.018 < 0.018 < 0.019 09/02/2008 09/16/2008 < 0.021 < 0.018 < 0.017 < 0.017 < 0.016 09/16/2008 09/30/2008 < 0.020 < 0.023 < 0.025 < 0.025 < 0.021 09/30/2008 10/14/2008 < 0.020 < 0.020 < 0.020 < 0.020 < 0.020 10/14/2008 10/28/2008 < 0.022 < 0.021 < 0.016 < 0.016 < 0.014 10/28/2008 11/11/2008 < 0.019 < 0.019 < 0.019 < 0.019 < 0.014 11/11/2008 11/25/2008 < 0.022 < 0.025 < 0.016 < 0.016 < 0.019 11/25/2008 12/09/2008 < 0.022 < 0.028 < 0.020 < 0.020 < 0.020 12/09/2008 12/17/2008 < 0.040 < 0.056 < 0.048 < 0.048 < 0.042 12/17/2008 12/29/2008 < 0.047 < 0.036 < 0.051 < 0.051 < 0.039

Attachment to 0CAN050901 Page 36 of 55 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators)

Station 1st Qtr 08 2nd Qtr 08 3rd Qtr 08 4th Qtr 08 Annual Mean (mrem) (mrem) (mrem) (mrem) 08 (mrem) 3 5.6 6.5 4.9 6.2 5.8 145 8.5 7.6 8.1 7.9 8.0 146 9.8 7.9 8.2 7.8 8.4 147 7.4 6.5 7.1 7.1 7.0 1 9.1 8.5 8.3 9.6 8.9 148 8.8 7.3 8.4 7.4 8.0 110 8.0 7.8 8.8 8.9 8.4 149 7.8 6.7 8.1 7.4 7.5 4 7.2 7.5 7.4 8.2 7.6 150 8.7 7.5 8.8 8.8 8.5 151 9.0 7.3 9.2 8.9 8.6 2 8.7 8.3 7.8 8.8 8.4 56

  • 9.8 9.1 9.2 10.6 9.7 109 8.8 8.4 9.6 8.9 8.9 108 8.8 7.7 7.9 9.3 8.4 152 7.9 7.4 7.9 8.6 8.0
  • Station with highest annual mean.

Attachment to 0CAN050901 Page 37 of 55 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr 08 2nd Qtr 08 3rd Qtr 08 4th Qtr 08 Annual Mean (mrem) (mrem) (mrem) (mrem) 08 (mrem) 6 7.6 6.3 6.3 7.3 6.9 111 5.4 4.6 6.7 6.4 5.8 116 8.1 7.3 8.1 7.6 7.8 125 4.9 4.7 5.1 5.9 5.2 127* 9.2 8.0 8.1 9.6 8.7 137 8.7 7.5 7.7 8.1 8.0 153 7.8 7.1 7.7 8.0 7.8

  • Stations with highest annual mean.

Special Interest Areas - (Control)

Station 1st Qtr 08 2nd Qtr 08 3rd Qtr 08 4th Qtr 08 Annual Mean (mrem) (mrem) (mrem) (mrem) 08 (mrem) 7 7.1 7.6 7.1 7.3 7.3

Attachment to 0CAN050901 Page 38 of 55 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn- Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 54 Required LLD 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 12/31/2007 01/31/2008 <4.20 <6.78 <3.76 <3.27 <7.15 <6.15 <4.23 <6.37 <4.19 <3.63 <18.31 <5.42 Station 10 (Control) 12/31/2007 01/31/2008 <2.76 <6.68 <3.15 <3.88 <7.01 <4.91 <4.21 <5.29 <3.63 <2.95 <16.13 <5.13 Station 8 (Indicator) 01/31/2008 02/29/2008 <4.01 <5.52 <3.63 <4.19 <8.70 <5.91 <4.26 <9.89 <3.38 <3.73 <23.09 <7.45 Station 10 (Control) 01/31/2008 02/29/2008 <3.03 <7.29 <3.01 <2.88 <6.36 <5.93 <3.75 <7.21 <3.32 <3.13 <16.75 <6.54 Station 8 (Indicator) 02/28/2008 03/31/2008 <3.01 <6.60 <3.33 <3.15 <5.73 <5.16 <3.85 <4.07 <3.56 <3.34 <13.91 <4.37 Station 10 (Control) 02/28/2008 03/31/2008 <4.39 <8.10 <3.95 <3.88 <7.88 <6.60 <4.09 <6.13 <4.13 <3.61 <15.78 <6.67 Station 8 (Indicator) 03/31/2008 04/30/2008 <5.23 <13.54 <6.21 <4.68 <10.39 <10.46 <5.59 <8.73 <7.67 <7.46 <25.98 <4.37 Station 10 (Control) 03/31/2008 04/30/2008 <3.66 <12.36 <6.49 <4.38 <12.95 <9.07 <7.69 <8.56 <5.16 <5.82 <23.78 <6.34 Station 8 (Indicator) 04/30/2008 05/31/2008 <3.56 <8.79 <5.34 <4.59 <11.36 <6.94 <5.11 <9.45 <4.96 <5.35 <23.63 <7.96 Station 10 (Control) 04/30/2008 05/31/2008 <4.17 <9.37 <3.78 <4.29 <9.59 <8.68 <4.94 <8.67 <4.72 <3.30 <20.33 <8.77 Station 8 (Indicator) 05/31/2008 06/30/2008 <6.82 <14.43 <4.80 <3.89 <13.99 <11.87 <7.84 <8.76 <7.17 <5.82 <29.79 <9.13 Station 10 (Control) 05/31/2008 06/30/2008 <4.85 <9.20 <6.39 <6.29 <7.82 <7.48 <7.49 <9.64 <5.63 <4.53 <23.70 <10.33

Attachment to 0CAN050901 Page 39 of 55 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn- Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 54 Required LLD 15 30 15 15 30 30 15 15 15 18 60 15 Station 8 (Indicator) 06/30/2008 07/31/2008 <4.64 <8.27 <4.15 <4.33 <6.36 <9.26 <5.24 <8.30 <5.32 <4.99 <21.07 <9.58 Station 10 (Control) 06/30/2008 07/31/2008 <3.06 <7.64 <4.17 <3.38 <7.24 <7.79 <5.49 <6.56 <4.01 <3.87 <19.32 <5.73 Station 8 (Indicator) 07/31/2008 08/31/2008 <0.60 <2.19 <0.83 <0.59 <1.33 <1.60 <1.31 <12.79 <0.65 <0.63 <22.44 <7.77 Station 10 (Control) 07/31/2008 08/31/2008 <0.68 <2.34 <0.90 <0.65 <1.41 <1.63 <1.48 <14.88 <0.69 <0.68 <22.61 <7.98 Station 8 (Indicator) 08/31/2008 09/30/2008 <3.55 <6.90 <4.00 <4.82 <6.62 <6.95 <4.37 <6.43 <3.97 <3.60 <22.14 <7.12 Station 10 (Control) 08/31/2008 09/30/2008 <4.64 <9.00 <4.12 <4.11 <8.29 <7.61 <5.49 <9.31 <5.25 <5.08 <22.93 <8.21 Station 8 (Indicator) 09/30/2008 10/31/2008 <3.64 <9.49 <4.48 <3.06 <8.69 <5.69 <3.90 <7.65 <3.71 <3.93 <19.80 <5.87 Station 10 (Control) 09/30/2008 10/31/2008 <3.67 <7.92 <3.85 <2.99 <7.69 <6.43 <3.92 <6.03 <3.62 <3.73 <17.37 <5.10 Station 8 (Indicator) 10/31/2008 11/30/2008 <2.79 <6.14 <3.14 <3.92 <8.05 <6.58 <4.86 <7.59 <3.61 <3.39 <16.07 <5.95 Station 10 (Control) 10/31/2008 11/30/2008 <2.83 <7.17 <3.55 <2.94 <6.12 <4.63 <3.95 <6.46 <3.03 <3.35 <14.40 <5.81 Station 8 (Indicator) 11/30/2008 12/31/2008 <3.52 <10.69 <4.51 <3.24 <7.14 <6.17 <6.14 <11.24 <4.39 <3.39 <26.26 <9.77 Station 10 (Control) 11/30/2008 12/31/2008 <5.63 <9.87 <5.94 <5.19 <7.60 <11.36 <6.72 <13.66 <5.32 <5.31 <36.65 <11.53

Attachment to 0CAN050901 Page 40 of 55 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) 12/31/2007 03/31/2008 1548 Station 10 (Control) 12/31/2007 03/31/2008 < 585 Station 8 (Indicator) 03/31/2008 06/30/2008 1213 Station 10 (Control) 03/31/2008 06/30/2008 < 560 Station 8 (Indicator) 06/30/2008 09/30/2008 811 Station 10 (Control) 06/30/2008 09/30/2008 < 567 Station 8 (Indicator) 09/30/2008 12/31/2008 521 Station 10 (Control) 09/30/2008 12/31/2008 < 589

Attachment to 0CAN050901 Page 41 of 55 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) 03/25/2008 < 1.14 <0.89 <3.67 <7.96 <3.04 <2.75 <10.52 <6.71 <4.63 <4.53 <3.72 <19.76 <6.84 Station 57 (Control) 03/25/2008 1.31 <0.85 <3.56 <7.41 <4.34 <3.94 <8.49 <6.96 <4.25 <3.64 <3.92 <15.11 <6.32 Station 14 (Indicator) 06/24/2008 1.39 <0.81 <4.19 <5.92 <3.38 <3.51 <6.62 <6.30 <4.31 <3.81 <3.47 <16.49 <5.83 Station 57 (Control) 06/24/2008 0.92 <0.84 <3.19 <7.46 <4.20 <3.68 <8.57 <6.30 <3.61 <3.89 <4.17 <18.88 <6.91 Station 14 (Indicator) 09/30/2008 0.92 <0.88 <3.34 <6.57 <3.23 <2.88 <7.86 <6.47 <4.39 <2.72 <3.45 <16.07 <7.54 Station 57 (Control) 09/30/2008 2.13 <0.90 <2.68 <7.84 <2.83 <2.96 <5.62 <5.51 <3.78 <2.98 <2.62 <16.87 <5.96 Station 14 (Indicator) 12/17/2008 3.44 <0.90 <4.13 <8.06 <6.68 <4.86 <13.52 <9.23 <8.65 <4.94 <5.73 <46.67 <14.34 Station 57 (Control) 12/17/2008 3.53 <0.90 <6.33 <11.87 <5.63 <5.80 <8.21 <10.71 <5.91 <4.44 <6.25 <3.90 <11.23

Attachment to 0CAN050901 Page 42 of 55 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 2000 Station 14 (Indicator) 03/25/2008 < 579 Station 57 (Control) 03/25/2008 < 580 Station 14 (Indicator) 06/24/2008 < 584 Station 57 (Control) 06/24/2008 < 567 Station 14 (Indicator) 09/30/2008 < 567 Station 57 (Control) 09/30/2008 < 580 Station 14 (Indicator) 12/17/2008 < 559 Station 57 (Control) 12/17/2008 < 557

Attachment to 0CAN050901 Page 43 of 55 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) 10/30/2008 < 120.20 41.79 Station 16 (Control) 09/28/2008 < 85.30 < 72.76

Attachment to 0CAN050901 Page 44 of 55 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) 10/28/2008 < 9.96 < 45.00 < 12.63 < 11.66 < 28.29 < 10.45 < 13.70 Station 16 (Control) 10/23/2008 < 8.19 < 35.34 < 11.02 < 12.92 < 27.51 < 7.55 < 10.08

Attachment to 0CAN050901 Page 45 of 55 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) 06/24/2008 < 56.76 < 44.56 < 48.69 Station 55 (Control) 06/24/2008 < 52.27 < 41.65 < 42.20 Station 13 (Indicator) 07/22/2008 < 57.30 < 42.20 < 38.30 Station 55 (Control) 07/22/2008 < 58.05 < 42.92 < 54.99 Station 13 (Indicator) 08/19/2008 < 58.59 < 52.14 < 43.55 Station 55 (Control) 08/19/2008 < 55.13 < 36.76 < 33.58

Attachment to 0CAN050901 Page 46 of 55 Table 8.1 Sample Type: Groundwater Analysis: Iodine-131 and Gamma Isotopic Units: pCi/l Sample Collection I-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140

  1. Date Required LLD 15 15 30 15 15 30 30 15 15 18 60 15 58* 3/12/2008 <13.96 < 4.21 < 9.85 < 4.47 < 3.66 < 7.5 < 8.37 < 5.83 < 3.99 < 5.04 < 27.12 < 9.46 59 3/12/2008 < 14.60 < 3.52 < 10.46 < 5.19 < 3.65 < 7.68 < 5.50 < 6.74 < 4.81 < 4.61 < 24.50 < 10.53 60 3/12/2008 < 14.49 < 4.18 < 9.48 < 5.57 < 4.38 < 11.39 < 9.00 < 7.38 < 5.17 < 3.80 < 28.34 < 10.12 61 3/12/2008 < 14.87 < 4.48 < 7.19 < 3.98 < 4.48 < 6.36 < 8.04 < 6.17 < 5.57 < 4.65 < 27.16 < 12.14 58* 6/17/2008 < 13.54 < 11.2 < 17.3 < 11.6 < 11.5 < 21.3 < 20.8 < 11.4 < 12.0 < 12.7 < 53.5 < 9.9 59 6/17/2008 < 13.54 < 11.2 < 17.3 < 11.6 < 11.5 < 21.3 < 20.8 < 11.4 < 12.0 < 12.7 < 53.5 < 9.9 60 6/17/2008 < 13.54 < 11.2 < 17.3 < 11.6 < 11.5 < 21.3 < 20.8 < 11.4 < 12.0 < 12.7 < 53.5 < 9.9 61 6/17/2008 < 13.54 < 11.2 < 17.3 < 11.6 < 11.5 < 21.3 < 20.8 < 11.4 < 12.0 < 12.7 < 53.5 < 9.9 58* 8/18/2008 < 14.82 < 0.70 < 2.86 < 1.00 < 0.64 < 1.45 < 1.97 < 1.87 < 0.69 < 0.67 < 46.29 < 12.00 59 8/18/2008 < 14.99 < 0.67 < 2.72 < 0.98 < 0.64 < 1.34 < 1.76 < 1.82 < 0.66 < 0.63 < 45.38 < 14.55 60 8/18/2008 < 13.99 < 0.58 < 2.58 < 0.89 < 0.53 < 1.20 < 1.67 < 1.64 < 0.57 < 0.54 < 50.67 < 14.52 61 8/18/2008 < 14.51 < 0.57 < 2.40 < 0.86 < 0.51 < 1.21 < 1.62 < 1.67 < 0.56 < 0.51 < 48.63 < 12.02 58* 11/19/2008 < 14.49 < 4.28 < 12.47 < 6.26 < 5.29 < 14.20 < 9.67 < 8.23 < 4.87 < 6.40 < 33.23 < 12.16 59 11/19/2008 < 12.30 < 5.44 < 9.87 < 4.57 < 2.86 < 9.16 < 7.83 < 6.12 < 4.96 < 5.80 < 26.33 < 10.86 60 11/19/2008 < 14.97 <4.84 < 7.92 < 5.67 < 4.41 < 13.32 < 8.50 < 6.45 < 5.44 < 5.35 < 36.47 < 7.39 61 11/19/2008 < 14.62 < 5.28 < 12.04 < 6.37 < 2.03 < 9.17 < 10.6 < 7.49 < 5.18 < 5.46 < 28.30 < 9.22
  • Identifies Control Locations

Attachment to 0CAN050901 Page 47 of 55 Table 8.2 Sample Type: Groundwater Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 3000 Station 58 (Control) 03/12/2008 < 583 Station 59 ((Indicator 03/12/2008 < 582 Station 60 (Indicator) 03/12/2008 < 581 Station 61 (Indicator) 03/12/2008 < 583 Station 58 (Control) 06/17/2008 < 569 Station 59 ((Indicator) 06/17/2008 < 563 Station 60 (Indicator) 06/17/2008 < 579 Station 61 (Indicator) 06/17/2008 < 572 Station 58 (Control) 08/18/2008 < 567 Station 59 ((Indicator) 08/18/2008 < 565 Station 60 (Indicator) 08/18/2008 < 581 Station 61 (Indicator) 08/18/2008 < 566 Station 58 (Control) 11/19/2008 < 566 Station 59 ((Indicator) 11/19/2008 < 585 Station 60 (Indicator) 11/19/2008 < 581 Station 61 (Indicator) 11/19/2008 < 591

Attachment to 0CAN050901 Page 48 of 55 ATTACHMENT 2 INTERLABORATORY COMPARISON PROGRAM

Attachment to 0CAN050901 Page 49 of 55 Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Gross Beta, Iodine-131 and Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value a Value N-Dev b N-Range c Charcoal E5390-125 6/14/2007 I-131 7.91E+01 7.97E+01 0.13 0.01 Cartridge (pCi/cartridge

)

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 Mn-54 1.33E+02 1.48E+02 3.89(d) 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 Milk E5391-125 6/12/2007 Cr-51 5.12E+02 5.17E+02 0.12 0.06 (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 0CAN050901 Page 50 of 55 Table 9.1 Sample Type: Interlaboratory Comparison Analysis: Tritium and Gamma Isotopic Sample Type Study Date Analysis Known RBS RBS RBS (units) Value a Value N-Dev b N-Range c Air Filter E5468-125 9/13/2007 BETA 3.23E+01 2.81E+01 -1.46 0.03 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 Sediment E5470-125 9/13/2007 Cr-51 3.91E-01 3.83E-01 -0.07 0.03 Mn-54 2.27E-01 2.43E-01 0.24 0.01 (pCi/gram)

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 0CAN050901 Page 51 of 55 Interlaboratory Comparison Program Exceptions RBS Environmental Laboratory analyzed interlaboratory comparison samples to fulfill the requirements of Technical Requirements Manual 3.12.3. The interlaboratory comparison results indicated that 100% of the sample results for accuracy and precision were within the acceptable control limits.

Attachment to 0CAN050901 Page 52 of 55 ATTACHMENT 3 SEDIMENT DOSE CALCULATIONS

Attachment to 0CAN050901 Page 53 of 55 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= 2008 maximum radionuclide concentration in pCi/kg; U= Maximum exposure time given in Table E-5 of Regulatory Guide 1.109 (67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> for teenager);

D= External dose conversion factor for standing on contaminated ground given in Table E-6 of Regulatory Guide 1.109 in mrem/hr per pCi/m2, and W= Shore-width factor (0.1) given in Table A-2 of Regulatory Guide 1.109.

(Dose from Sediment in mrem/Year)

Radionuclide 2008 Conversion Total Conversion Total Maximum Factor Skin Dose Factor Body Dose Concentration For Skin For Total Body Cs-137 41.79 4.90 E-09 5.49 E-05 4.20 E-09 4.70 E-05 TOTAL 5.49 E-05 4.70 E-05

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