0CAN051801, Submittal of Annual Radiological Environmental Operating Report for 2017

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Submittal of Annual Radiological Environmental Operating Report for 2017
ML18129A101
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 05/09/2018
From: Pyle S
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
0CAN051801
Download: ML18129A101 (52)
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Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 0CAN051801 May 9, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Annual Radiological Environmental Operating Report for 2017 Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

REFERENCE:

Entergy letter dated April 26, 2018, Annual Radioactive Effluent Release Report for 2017 (0CAN041802)

Dear Sir or Madam:

In accordance with Arkansas Nuclear One (ANO), Unit 1 Technical Specification (TS) 5.6.2 and Unit 2 TS 6.6.2, the submittal of an annual radiological environmental operating report for the previous year is required by May 15 of each year. The subject ANO report for the calendar year 2017 is enclosed.

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

The radionuclides detected by the radiological environmental monitoring program during 2017 were significantly below the regulatory limits. The operation of the ANO station during 2017 had no harmful radiological effects nor resulted in any irreversible damage to the local environment.

Based on ANOs review, no environmental samples from the monitoring program equaled or exceeded the reporting levels for radioactivity concentration due to ANO effluents when averaged over any calendar quarter. A map of all sampling locations and a corresponding table providing the respective distances and directions from the reactor building is included in the Offsite Dose Calculation Manual submitted as part of the referenced Annual Radioactive Effluent Release Report.

0CAN051801 Page 2 of 2 This letter contains no new commitments.

If you have any questions or require additional information, please contact me.

Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/rwc

Enclosure:

Annual Radiological Environmental Operating Report for 2017 cc: Mr. Kriss Kennedy Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1A 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

Enclosure to 0CAN051801 Annual Radiological Environmental Operating Report for 2017

Enclosure to 0CAN051801 Page 1 of 49 Table of Contents Summary.................................................................................................................................. 2 1.0 Introduction .................................................................................................................... 5 1.1 Radiological Environmental Monitoring Program ................................................ 5 1.2 Pathways Monitored ............................................................................................ 5 1.3 Land Use Census ................................................................................................ 5 2.0 Interpretation and Trends of Results ............................................................................. 16 2.1 Air Particulate and Radioiodine Sample Results ................................................. 16 2.2 Thermoluminescent Dosimetry (TLD) Sample Results ....................................... 16 2.3 Water Sample Results ........................................................................................ 16 2.4 Sediment Sample Results ................................................................................... 19 2.5 Milk Sample Results ............................................................................................ 19 2.6 Fish Sample Results ........................................................................................... 19 2.7 Food Product Sample Results............................................................................. 19 2.8 Interlaboratory Comparison Results .................................................................... 19 2.9 Land Use Census Results ................................................................................... 20 3.0 Radiological Environmental Monitoring Program Summary .......................................... 21 3.1 2017 Program Results Summary ........................................................................ 21 Tables Table 1.1 Radiological Environmental Sampling Program ............................................... 7 Table 2.1 2017 Land Use Census .................................................................................... 20 Table 3.1 Radiological Environmental Monitoring Program Summary ............................. 22 Figures Figure 1-1 TLD Sample Collection Sites - NEAR FIELD................................................... 13 Figure 1-2 TLD Sample Collection Sites - FAR FIELD ..................................................... 14 Figure 1-3 Stormwater Sample Collection Sites - SITE MAP ........................................... 15 Attachments Summary of Monitoring Results ................................................................... 26 Interlaboratory Comparison Program ........................................................... 39 Sediment Dose Calculations ........................................................................ 48

Enclosure to 0CAN051801 Page 2 of 49 Summary The Annual Radiological Environmental Operating Report (AREOR) presents data obtained through analyses of environmental samples collected for Arkansas Nuclear One's (ANOs)

Radiological Environmental Monitoring Program (REMP) for the period January 1, 2017, through December 31, 2017. This report fulfills the requirements of ANO Unit 1 Technical Specification (TS) 5.6.2 and Unit 2 TS 6.6.2.

During 2017, as in previous years, ANO detected tritium 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 tritium levels in the surface water media continue to be below regulatory reporting limits and are consistent with concentrations that would typically be seen at this location as discussed in Section 2.3 of this AREOR.

Gross beta concentrations at the Station 14 (City of Russellville) indicator drinking water location continue to remain consistent with previous operational measurements and similar to the levels detected at the Station 57 (City of Danville) control drinking water location. Slightly elevated levels of gross beta were observed in 2017 samples. These samples were low in activity and occurred in both indicator and control locations. There are no trends of concern from these results. Data from 2015 and 2016 are included in this report.

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

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

In 2017, ANO personnel collected environmental samples for radiological analysis. Personnel 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 2017 data, in most 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 2017. Therefore, no analysis or planned course of action to alleviate problems was necessary.

Enclosure to 0CAN051801 Page 3 of 49 Reporting Levels ANO's review indicates that no samples equaled or exceeded reporting levels for radioactivity concentration in environmental samples due to ANO effluents, as outlined in ODCM Table 2.5-2, when averaged over any calendar quarter. Therefore, 2017 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. In 2011, ANO detected I-131 radioactivity attributed to the Fukushima Daiichi Nuclear Power Plant accident (March 11, 2011).

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

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

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

Sample Deviations Milk The REMP did not include milk sampling within five miles of ANO in 2017 due to unavailability. The ODCM requires collection of milk samples, if available commercially within 5 miles of the plant. ANO personnel collected vegetation samples to monitor the ingestion pathway, as specified in the ODCM, because of milk unavailability.

Lower Levels of Detection (LLDs) during this reporting period were within the acceptable limits required by Table 2.5-1 of the ODCM.

Enclosure to 0CAN051801 Page 4 of 49 Air Samples Listed below are air sampler deviations that occurred during 2017 due to electrical power outages and equipment failure. These deviations did not result in exceeding LLD values specified in the ODCM. As described in ODCM, B 2.5.1, Actions A.1 and A.2, deviations are permitted from the required sampling schedule due to malfunction of sampling equipment and other legitimate reasons.

Station Sampling Period Comment As documented on 3/28/2017, totalizer run time for the listed sampling period was approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> less than expected.

2 3/14/2017 - 3/28/2017 The totalizer was verified to be advancing as required during sample collection. (CR-ANO-C-2017-01121)

Missed Samples Fourth quarter environmental TLD Station #127 missing (CR-ANO-C-2018-00212).

Unavailable Results None Program Modifications ANO Site Procedure OP-1608.005 No changes to OP-1608.005 were made during the year 2017.

ODCM No changes to the ODCM were made during the year 2017.

Attachments contains results of air, TLD, water, sediment, fish, and food product samples collected in 2017. TLDs were analyzed by a vendor (Environmental Dosimetry Company -

EDC). All remaining samples were analyzed by Teledyne Brown Engineering (TBE). contains TBEs participation in the inter-laboratory comparison program during 2017. contains dose calculations performed for sediment using a generalized equation from Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1.

Enclosure to 0CAN051801 Page 5 of 49 1.0 Introduction 1.1 Radiological Environmental Monitoring Program ANO established the REMP to ensure that plant operating controls properly function to minimize any associated radiation endangerment to human health or the environment. The REMP is designed for:

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

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

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

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

1.2 Pathways Monitored The airborne, direct radiation, waterborne and ingestion pathways are monitored as required by the ODCM. A description of the ANO REMP used 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 2017 sampling results and Section 3.0 provides a summary of results for the monitored exposure pathways.

1.3 Land Use Census ANO personnel conduct the land use census every 24 months as required by ODCM Surveillance (S) 2.5.2.1. The land use census was last conducted in 2017. This census serves to identify changes in land use within five miles of ANO that would require modifications to the REMP or ODCM. The most important aspects of this census are to determine the 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 did not perform a garden census since an ODCM Limitation (L) 2.5.2 Note allows the routine sampling of broadleaf vegetation in the highest D/Q sector near the site boundary in lieu of the garden census.

Enclosure to 0CAN051801 Page 6 of 49 The method used by ANO personnel for conducting the land use census was 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 was used to identify commercial milk providers within five-miles of the Unit 1 reactor building.

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

1) Nearest permanent residence
2) Nearest milking animal ANO personnel identify locations on the map, measure distances to ANO (or use a GPS system) and record results.

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

ANO personnel compare results to previous census.

Enclosure to 0CAN051801 Page 7 of 49 TABLE 1.1 RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Station 2 (243° - 0.5 miles) - South Radioiodine and Particulates of the sewage treatment plant.

3 samples close to the Site Boundary, in Station 56 (264° - 0.4 miles) - West (or near) different sectors with the end of the sewage treatment plant.

highest calculated annual average ground level D/Q. Station 1 (88° - 0.5 miles) - Near the meteorology tower. Radioiodine Canister - Analyze at Continuous operation of least once per 14 days for I-131.

Radioiodine and Particulates sampler with sample collection Airborne as required by dust loading but Particulate Sampler - Analyze for 1 sample from the vicinity of a Station 2 (243° - 0.5 miles) - South at least once per 14 days. gross beta radioactivity following community having the highest calculated of the sewage treatment plant.

filter change.

annual average ground level D/Q.

Radioiodine and Particulates Station 7 (210° - 19.0 miles) -

1 sample from a control location Entergy Supply Yard on Highway 10 15 - 30 km (10 - 20 miles) distance. in Danville.

Station 1 (88° - 0.5 miles) - On a pole near the meteorology tower.

Station 2 (243° - 0.5 miles) - South Thermoluminescent dosimetry (TLDs) of the sewage treatment plant.

Direct 16 inner ring stations with two or more Station 3 (5 - 0.7 miles) - West of Once per 92 days. Gamma Dose - Once per 92 days.

Radiation dosimeters in each meteorological sector ANO Gate #2 on Highway 333 in the general area of the site boundary. (approximately 0.35 miles)

Station 4 (181° - 0.5 miles) - West of May Cemetery entrance on south side of the road.

Enclosure to 0CAN051801 Page 8 of 49 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Station 56 (264° - 0.4 miles) - West end of the sewage treatment plant.

Station 108 (306° - 0.9 miles) -

South on Flatwood Road on a utility pole.

Station 109 (291° - 0.6 miles) -

Utility pole across from the junction of Flatwood Road and Round Mountain Road.

Station 110 (138° - 0.8 miles) -

Bunker Hill Lane on the first utility TLDs pole on the left.

Direct 16 inner ring stations with two or more Once per 92 days. Gamma Dose - Once per 92 days.

Radiation Station 145 (28° - 0.6 miles) - Near dosimeters in each meteorological sector west entrance to the RERTC on a in the general area of the site boundary 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.

Enclosure to 0CAN051801 Page 9 of 49 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Station 149 (156° - 0.5 miles) - On a utility pole on the south side of May Road.

Station 150 (205° - 0.6 miles) -

TLDs North side of May Road on a utility pole past the McCurley Place turn.

16 inner ring stations with two or more dosimeters in each meteorological sector Station 151 (225° - 0.4 miles) -

in the general area of the Site Boundary. 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.

Direct Radiation Station 6 (111° - 6.8 miles) - Once per 92 days. Gamma Dose - Once per 92 days.

Entergy local office in Russellville (305 South Knoxville Avenue).

Station 7 (210° - 19.0 miles) -

TLDs Entergy Supply Yard on Highway 10 in Danville.

8 stations with two or more dosimeters in special interest areas such as population Station 111 (120° - 2.0 miles) -

centers, nearby residences, schools, and Marina Road on a utility pole on the in 1 - 2 areas to serve as control left just prior to curve.

locations.

Station 116 (318° - 1.8 miles) -

Highway 333 and Highway 64 in London on a utility pole north of the railroad tracks.

Enclosure to 0CAN051801 Page 10 of 49 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Station 125 (46° - 8.7 miles) -

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

Station 127 (100° - 5.2 miles) -

TLDs Arkansas Tech Campus on a utility pole across from Paine Hall.

8 stations with two or more dosimeters in Direct special interest areas such as population Once per 92 days. Gamma Dose - Once per 92 days.

Radiation Station 137 (151° - 8.2 miles) - On centers, nearby residences, schools, and a speed limit sign on the right in in 1 - 2 areas to serve as control front of the Morris R. Moore locations.

Arkansas National Guard Armory.

Station 153 (304° - 9.2 miles) -

Knoxville Elementary School near the school entrance gate on a utility pole.

Surface Water Station 8 (166° - 0.2 miles) - Plant 1 indicator location (influenced by plant discharge canal.

discharge) Gamma isotopic and tritium Once per 92 days.

analyses once per 92 days.

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

discharge)

Waterborne Drinking Water Station 14 (70° - 5.1 miles) -

Russellville city water system from 1 indicator location (influenced by plant the Illinois Bayou. I-131, gross beta, gamma isotopic discharge) Once per 92 days. and tritium analyses once per Station 57 (208° - 19.5 miles) - 92 days.

1 control location (uninfluenced by plant Danville public water supply discharge) treatment on Fifth Street.

Enclosure to 0CAN051801 Page 11 of 49 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Sampling and Collection Requirement Type and Frequency Of Analyses Pathway Distance and Direction Frequency Sediment Station 8 (243° - 0.9 miles) - Plant discharge canal.

1 indicator location (influenced by plant Waterborne discharge) Station 16 (287° - 5.5 miles) - Gamma isotopic analysis once per Once per 365 days.

Panther Bay on south side of 365 days.

1 control location (uninfluenced by plant Arkansas River across from mouth discharge) of Piney Creek.

Milk 1 indicator sample location within five-mile distance if commercially available. Currently, no available milking Gamma isotopic and I-131 Once per 92 days.

animals within 5 miles of ANO. analyses once per 92 days.

1 control sample location at a distance of

>five-miles when an indicator exists.

Fish Station 8 (212° - 0.5 miles) - Plant 1 sample of commercially and/or discharge canal.

recreationally important species in Gamma isotopic on edible portions vicinity of plant discharge. Station 16 (287° - 5.5 miles) - Once per 365 days.

once per 365 days.

Panther Bay on south side of Ingestion 1 sample of same species in area not Arkansas River across from mouth influenced by plant discharge. of Piney Creek.

Food Products 1 sample of broadleaf (edible or non-Station 13 (273° - 0.5 miles) - West edible) near the site boundary from one from ANO toward Gate 4 onto of the highest anticipated annual average Flatwood Road.

ground level D/Q sectors, if milk Gamma. isotopic and I-131 sampling is not performed. Three per 365 days.

analyses three times per 365 days.

Station 55 (217° - 13.1 miles) -

1 sample location of broadleaf vegetation Ozark National Forest north of (edible or non-edible) from a control Danville location 15 - 30 km (10 - 20 miles) distant, if milk sampling is not performed.

Enclosure to 0CAN051801 Page 12 of 49 TABLE 1.1 (continued)

RADIOLOGICAL ENVIRONMENT SAMPLING PROGRAM Exposure Sample Point Description, Distance and Sampling and Collection Type and Frequency Of Requirement Pathway Direction Frequency Analyses 2 sample locations of Groundwater from Station 58 (GWM-1, 22° - 0.3 miles) - Once per 92 days Control, Tritium, Gross Beta a control location up gradient from the North of Protected Area in Owner Control and Gamma Isotopic, once per protected area Area (OCA). West of Security North Check 92 days.

Point, east side of access road.

Station 62 (GWM-101, 34° - 0.5 miles) - Once per 92 days Control, Tritium, Gross Beta North of Protected Area in OCA. East of and Gamma Isotopic, once per outside receiving building. 92 days.

Ground water 2 sample locations of Groundwater from Station 63 (GWM-103, 206° - 0.1 miles) - Once per 92 days Indicator, Tritium, Gross Beta indicator locations down gradient from South of Protected area in OCA. North- and Gamma Isotopic, once per the protected area. east of Stator Rewind Bldg. near wood line. 92 days.

Station 64 (GWM-13, 112° - 0.1 miles) - Once per 92 days Indicator, Tritium, Gross Beta South of Oily Water Separator facility, and Gamma Isotopic, once per northwest corner of U-2 Intake Structure. 92 days.

Inside Protected area.

Enclosure to 0CAN051801 Page 13 of 49 FIGURE 1-1 TLD SAMPLE COLLECTION SITES - NEAR FIELD SR 333 152 3 108 Training 145 Center 146 147 109 13 1 West Access Rd. 10 56 2 8C 36 Scott Ln.

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

Hill Rd.

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

Lake Dardanelle Revised 24May05

Enclosure to 0CAN051801 Page 14 of 49 FIGURE 1-2 TLD SAMPLE COLLECTION SITES - FAR FIELD 1

0° 16 340° 20° 2

US HWY 7 TO HARRISON 320° 40° 15 INTERSTATE 40 TO FORT SMITH 3

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

HWY 64 14 4 SR 24 TO 14 MORELAND 116 280° ARKANSAS RIVER 80° INTERSTATE 40 LONDON 16 US HWY 64 13 J I H G F E D C B A 5 DELAWARE STATE PARK 127 111 ARKANSAS TECH DARDANELLE UNIVERSITY 260° STATE PARK 100° U.S. HWY 22 HWY 524 LAKE DARDANELLE RUSSELLVILLE DARDANELLE STATE PARK 6

DARDANELLE LOCK AND DAM 12 HWY 22 DAM SITE EAST PARK HWY 7T 6

240° 120° HWY 155 HWY 7 SR 247 TO MT. NEBO HWY 27 POTTSVILLE STATE PARK DARDANELLE 137 11 220° HWY 28 140° 7 HWY 7 200° 160° 10 180° 8 HWY 27 TO HWY 7 TO DANVILLE 9

HOT SPRINGS DANVILLE INSET (SEE INSET) N FS Rd 1618A W E 55 AR Hwy 307 FS Rd 36 Ozark National Forest boundary S AR Hwy 27 AR Hwy 10 Entergy Substation Petit Jean River 7

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

Enclosure to 0CAN051801 Page 15 of 49 FIGURE 1-3 STORMWATER AND GROUNDWATER SAMPLE COLLECTION SITES - SITE MAP 62 58 STR-3 Switch STR-2 Yard STR-4 STR-6 West Access Road 64 STR-5 63 STR-1 N

Lake Dardanelle W E S

Arkansas Nuclear One REMP Sample Locations Site Map Stormwater run-off collection sites Groundwater collection sites

Enclosure to 0CAN051801 Page 16 of 49 2.0 Interpretation and Trends of Results 2.1 Air Particulate and Radioiodine Sample Results The REMP has detected radioactivity in the airborne pathway attributable to other sources.

These include the 25th Chinese nuclear test explosion in 1980, the radioactive plume release due to reactor core degradation at Chernobyl Nuclear Power Plant in 1986 and the Fukushima Daiichi Nuclear Power Plant accident (Mach 11, 2011).

In 2017 there were no samples above the LLD for I-131. Indicator gross beta air particulate results for 2017 were comparable to results obtained from 2006-2016 of the operational REMP, but less than 2013 when the annual average was 0.043. Also, the 2017 gross beta annual average was less than the average for preoperational levels. Results are reported as annual average picocuries per cubic meter (pCi/m3).

Monitoring Period Result 2006 - 2016 (Minimum Value) 0.018 2017 Average Value 0.019 2006 - 2016 (Maximum Value) 0.043 Preoperational 0.050 In the absence of plant-related gamma radionuclides, gross beta activity is attributed to naturally occurring radionuclides. Table 3.1, which include gross beta concentrations and provide a comparison of the indicator and control means and ranges emphasizes the consistent trends seen in this pathway to support the presence of naturally occurring activity. Therefore, it can be concluded that the airborne pathway continues to be unaffected by ANO operations.

2.2 Thermoluminescent Dosimetry (TLD) Sample Results ANO reports measured dose as net exposure (field reading less transit reading) normalized to 92 days and relies on comparison of the indicator locations to the control as a measure of plant impact. ANOs comparison of the inner ring and special interest area TLD results to the control, as seen in Table 3.1, identified no noticeable trend that would indicate that the ambient radiation levels are being affected by plant operations. In addition, the inner ring annual mean value of 8.19 millirem (mrem) shown in Table 3.1 for 2017 is within the historical bounds of 2006 - 2016 annual average results, which have ranged from 6.9 to 8.5 mrem. Overall, ANO concluded that the ambient radiation levels are not being affected by plant operations.

2.3 Water Sample Results Analytical results for 2017 drinking water and ground water samples were similar to those reported in previous years. Gamma radionuclides analytical results for 2017 surface water samples were similar to those reported in previous years. Tritium detection in ANO surface water indicator samples continues but at levels below those experienced in 2013 and below the ODCM-required LLD. These results are further explained below.

Enclosure to 0CAN051801 Page 17 of 49 Surface water samples were collected and analyzed for gamma radionuclides and tritium.

Gamma radionuclides were below detectable limits which is consistent with results seen in previous operational years. Tritium continues to be detected at the indicator location (Station 8) where previously monitored liquid radioactive effluent from the plant is periodically discharged in accordance with the regulatory criteria established in the ODCM and, for 2017, at levels considerably lower than the ODCM-required LLD of 3000 pCi/l. Furthermore, unlike the elevated tritium levels observed in 2013 attributable to particular plant events, no elevated levels attributable to particular events were observed in 2017. Two samples collected in 2017 were above MDC at Station 8. The mean value reported below uses the positive results plus the MDC for the other sampling events. Results are reported as annual average pCi/l.

Monitoring Period Result 2006 - 2016 (Minimum Value) 554.5 2017 Value 427 2006 - 2016 (Maximum Value) 2940*

Preoperational 200.0

  • Indicates value from 2013 ANO personnel have noted no definable increasing trends associated with the tritium levels at the discharge location. Levels detected during 2017 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 2017 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. Both indicator and control stations showed results above the gross beta MDC for the fourth quarter sampling event in 2017.

Drinking water samples were analyzed for gross beta radionuclides, I-131, gamma radionuclides and tritium. Gamma radionuclides, gross beta radionuclides, I-131 and tritium concentrations were below the LLD limits at the indicator and control locations, which is consistent with 2013 and comparable to the preoperational and 2006 - 2016 operational years as shown below. Results from 2017 are summarized in Table 3.1. Results are reported as annual average pCi/L.

Radionuclide 2017* 2006 - 2016 Mean Preoperational Gross Beta 2.76 2.29 2.0 Iodine-131 <LLD < LLD < LLD Gamma <LLD < LLD < LLD Tritium <LLD < LLD 200.0

  • Value represents 4th quarter sampling results from 2017.

Enclosure to 0CAN051801 Page 18 of 49 ANO personnel have noted no definable trends associated with drinking water results at the indicator location. Therefore, the operation of ANO had no definable impact on this waterborne pathway during 2017 and levels of radionuclides remain similar to those obtained in previous operational years.

Groundwater samples were collected from four REMP locations (2 control, and 2 indicator locations). During 2011, ANO incorporated sixteen additional groundwater monitoring wells into the Groundwater Protection Initiative (GPI) site program. Sample data are compiled, organized and reviewed annually to:

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

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

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

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

Determine if any change to the ODCM is required.

Determine if a corrective action/remediation is required.

Groundwater samples from the four REMP locations were analyzed for tritium and gamma radionuclides. Tritium, gamma, and gross beta concentrations were below the LLD limits at all four locations with the following exceptions. Station 58, control location, showed gross beta results above MDC for the 4th quarter sampling event. Station 63, indicator location, showed gross beta above MDC for the 1st and 4th quarter events and Station 64, indicator location, showed gross beta above MDC for the 4th quarter event. Listed below is a comparison of 2017 indicator results to past operational years. Results are reported as annual average pCi/l.

REMP Groundwater data are captured in Tables 8.1 and 8.2. Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway.

Radionuclide 2017 2006 - 2016 Iodine-131 < LLD < LLD Gamma < LLD < LLD Tritium < LLD < LLD Gross Beta 5.60* < LLD th

  • Highest sample result from 2017 monitoring. Station 58 4 Quarter result.

Enclosure to 0CAN051801 Page 19 of 49 2.4 Sediment Sample Results Sediment samples were collected from two locations in 2017 and analyzed for gamma radionuclides. Listed below is a comparison of 2017 indicator results to the 2006 - 2016 operational years. Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway. Results are reported as pCi/kg.

Monitoring Period Result 2006 - 2016 (Minimum Value) 41.79 2017 Value < LLD 2006 - 2016 (Maximum Value) 661.0 Since reporting levels for radionuclides in sediment have not been established, an evaluation of potential dose to the public from this media was performed as shown in Attachment 3.

2.5 Milk Sample Results Milk samples were not collected during 2017 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 2017, 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 2017, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2017 levels remained undetectable, as has been the case in previous years. Therefore, based on these measurements, ANO operations had no significant radiological impact upon the environment or public by this ingestion pathway.

2.8 Interlaboratory Comparison Results Teledyne Brown Engineering analyzed interlaboratory comparison samples to fulfill the requirements of ODCM Section 2.5.3. Attachment 2 contains these results.

Enclosure to 0CAN051801 Page 20 of 49 2.9 Land Use Census Results The latest land use census (performed in 2017) 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 2017, but instead to sample broadleaf vegetation which is allowed by ODCM Section L 2.5.2. As allowed by NRC Regulatory Guide 1.21, Revision 2, Section 3.2, broadleaf vegetation sampling in the meteorological sector (Sector 13) with a D/Q value within 10% of the sector with the highest D/Q (Sector 12) was performed.

The next land use census is scheduled to be conducted in 2019.

TABLE 2.1 2017 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

Enclosure to 0CAN051801 Page 21 of 49 3.0 Radiological Environmental Monitoring Program Summary 3.1 2017 Program Results Summary Table 3.1 summarizes the 2017 REMP results.

Enclosure to 0CAN051801 Page 22 of 49 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: ANO - Units 1 and 2 Docket No: 50-313 and 50-368.

Location of Facility: Pope County, Arkansas Reporting Period: January - December 2017 Type / Indicator Location with Highest Annual Control Number of Sample Type b Mean Number of LLD Locations Mean Locations Mean Non-Routine (Units)

Analysesa (F)c [Range] Locationd Mean (F)c [Range] (F)c [Range] Resultse Air Particulates 0.0186 (81 / 81)

Station 6* 0.0203 (27 / 27) 0.0200 (54 / 54)

(pCi/m3) GB / 135 0.01 [0.00893 - 0 (111°, 6.8 mi) [0.0127 - 0.0287] [0.0127 - 0.0290]

0.0285]

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

(f)

Inner Ring TLDs Gamma / 64 8.0 (64 / 64) Station 56 10.0 (4 / 4) N/A 0 (mR/Qtr) [5.5 - 10.0] (264°, 0.4 mi) [9.4 - 10.4]

Special Interest Gamma / 28 (f) 7.2 (27 / 28) Station 137 9.2 (4 / 4) N/A 1 TLDs (mR/Qtr) [5.2 - 9.2] (151° - 8.2mi) [8.1 - 10.4]

Control TLD Gamma / 4 (f)

N/A N/A N/A 6.7 (4 / 4) 0 (mR/Qtr) [6.3 - 7.2]

Enclosure to 0CAN051801 Page 23 of 49 TABLE 3.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

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

Analysesa (F)c [Range] (F)c [Range] Resultse H-3 / 8 3000 450 (4* / 4) Station 8 450 (4* / 4) < LLD 0

[358 - 637] (166°, 0.2 mi) [358 - 637]

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 Surface Water Zn-65 30 < LLD N/A N/A < LLD 0 (pCi/l)

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

Enclosure to 0CAN051801 Page 24 of 49 TABLE 3.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

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

Analysesa (F)c [Range] (F)c [Range] Resultse GB / 8 4 1.48 Station 57* 2.76 2.76 0

[<LLD - 1.48] 208° - 19.5mi [<LLD - 2.76] [<LLD - 2.76]

I-131 / 8 1 < 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 Drinking Water Fe-59 30 < LLD N/A N/A < LLD 0 (pCi/1) 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 GS / 2 Sediment Cs-134 150 < LLD N/A < LLD < LLD 0 (pCi/kg) Cs-137 180 < LLD N/A < LLD < LLD 0

  • Positive GB results.

Enclosure to 0CAN051801 Page 25 of 49 TABLE 3.1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

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

Analysesa (F)c [Range] (F)c [Range] Resultse GS / 2 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 Fish (pCi/kg)

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 I-131 / 6 60 < LLD N/A N/A N/A 0 Food Products GS / 6 (pCi/kg)

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 Table 2.5-1.

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 Table 2.5-1.

Enclosure to 0CAN051801 Page 26 of 49 ATTACHMENT 1

SUMMARY

OF MONITORING RESULTS

Enclosure to 0CAN051801 Page 27 of 49 Table of Contents Table 1.1 Air Particulate Table 1.2 Radioiodine Cartridges Table 2.1 Thermoluminescent Dosimeters (Inner Ring)

Table 2.2 Thermoluminescent Dosimeters (Special Interest Areas)

Table 3.1 Surface Water (Gamma Isotopic)

Table 3.2 Surface Water (Tritium)

Table 4.1 Drinking Water (Gross beta, I-131 and Gamma Isotopic)

Table 4.2 Drinking Water (Tritium)

Table 5.1 Sediment Table 6.1 Fish Table 7.1 Food Products Table 8.1 Groundwater Data (Gross Beta and Gamma Isotopic)

Table 8.2 Groundwater Data (Tritium)

Enclosure to 0CAN051801 Page 28 of 49 Table 1.1 Sample Type: Air Particulate Analysis: Gross Beta Units: pCi/m3 Station 1 Station 2 Station 56 Station 6* Station 7 Start Date End Date (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 0.01 0.01 0.01 0.01 0.01 01/03/2017 01/17/2017 2.29E-02 2.09E-02 1.79E-02 2.59E-02 2.34E-02 01/17/2017 01/31/2017 1.98E-02 1.67E-02 1.70E-02 1.95E-02 1.94E-02 01/31/2017 02/14/2017 2.03E-02 2.23E-02 1.47E-02 1.90E-02 1.99E-02 02/14/2017 02/28/2017 1.62E-02 1.25E-02 1.23E-02 1.53E-02 1.28E-02 02/28/2017 03/14/2017 1.39E-02 1.61E-02 1.17E-02 1.47E-02 1.71E-02 03/14/2017 03/28/2017 1.77E-02 2.07E-02 1.75E-02 1.98E-02 1.86E-02 03/28/2017 04/11/2017 1.35E-02 1.34E-02 8.93E-03 1.48E-02 1.49E-02 04/11/2017 04/25/2017 1.61E-02 1.47E-02 1.29E-02 1.30E-02 1.50E-02 04/25/2017 05/09/2017 1.85E-02 1.75E-02 1.21E-02 1.57E-02 1.73E-02 05/09/2017 05/23/2017 1.63E-02 1.82E-02 1.76E-02 1.80E-02 1.92E-02 05/23/2017 06/06/2017 1.64E-02 1.72E-02 1.18E-02 1.70E-02 1.60E-02 06/06/2017 06/20/2017 1.37E-02 1.42E-02 1.26E-02 1.27E-02 1.29E-02 06/20/2017 06/27/2017 1.88E-02 2.13E-02 1.43E-02 2.13E-02 1.75E-02 06/27/2017 07/11/2017 1.49E-02 1.48E-02 1.44E-02 1.52E-02 1.68E-02 07/11/2017 07/25/2017 2.05E-02 1.85E-02 1.54E-02 2.09E-02 1.77E-02 07/25/2017 08/08/2017 2.12E-02 1.77E-02 1.72E-02 2.02E-02 1.68E-02 08/08/2017 08/22/2017 1.65E-02 1.65E-02 1.25E-02 1.77E-02 1.76E-02 08/22/2017 09/05/2017 2.51E-02 2.76E-02 2.80E-02 2.82E-02 2.58E-02 09/05/2017 09/19/2017 2.52E-02 2.75E-02 2.07E-02 2.83E-02 2.90E-02 09/19/2017 10/03/2017 2.23E-02 2.50E-02 2.00E-02 2.45E-02 2.58E-02 10/03/2017 10/17/2017 2.07E-02 2.12E-02 1.76E-02 2.11E-02 1.91E-02 10/17/2017 10/31/2017 1.32E-02 1.84E-02 1.57E-02 1.88E-02 1.85E-02 10/31/2017 11/14/2017 2.58E-02 2.53E-02 1.73E-02 2.63E-02 2.62E-02 11/14/2017 11/28/2017 2.85E-02 2.80E-02 2.26E-02 2.87E-02 2.84E-02 11/28/2017 12/12/2017 2.46E-02 2.14E-02 1.56E-02 2.21E-02 2.56E-02 12/12/2017 12/19/2017 2.41E-02 2.22E-02 2.04E-02 2.84E-02 2.23E-02 12/19/2017 01/02/2018 2.47E-02 2.40E-02 2.17E-02 2.45E-02 2.55E-02

  • Station with highest annual mean.

Enclosure to 0CAN051801 Page 29 of 49 Table 1.2 Sample Type: Radioiodine Cartridges Analysis: Iodine-131 Units: pCi/m3 Station 1 Station 2 Station 56 Station 6 Station 7 Start Date End Date (Indicator) (Indicator) (Indicator) (Control) (Control)

Required LLD 0.07 0.07 0.07 0.07 0.07 01/03/2017 01/17/2017 < 2.50E-02 < 2.50E-02 < 2.50E-02 < 1.37E-02 < 2.48E-02 01/17/2017 01/31/2017 < 1.18E-02 < 3.03E-02 < 3.03E-02 < 3.02E-02 < 3.02E-02 01/31/2017 02/14/2017 < 5.03E-02 < 5.04E-02 < 5.04E-02 < 2.23E-02 < 5.00E-02 02/14/2017 02/28/2017 < 2.88E-02 < 2.88E-02 < 1.21E-02 < 2.87E-02 < 2.87E-02 02/28/2017 03/14/2017 < 2.96E-02 < 1.53E-02 < 2.96E-02 < 2.95E-02 < 2.94E-02 03/14/2017 03/28/2017 < 2.94E-02 < 1.74E-02 < 2.94E-02 < 2.93E-02 < 2.92E-02 03/28/2017 04/11/2017 < 1.95E-02 < 1.94E-02 < 1.94E-02 < 7.51E-03 < 1.93E-02 04/11/2017 04/25/2017 < 2.38E-02 < 2.38E-02 < 2.38E-02 < 1.00E-02 < 2.37E-02 04/25/2017 05/09/2017 < 1.96E-02 < 3.80E-02 < 3.80E-02 < 3.79E-02 < 3.78E-02 05/09/2017 05/23/2017 < 2.56E-02 < 2.57E-02 < 2.57E-02 < 2.56E-02 < 1.07E-02 05/23/2017 06/06/2017 < 2.29E-02 < 2.29E-02 < 2.30E-02 < 8.88E-03 < 2.28E-02 06/06/2017 06/20/2017 < 1.03E-02 < 2.67E-02 < 2.67E-02 < 2.66E-02 < 2.63E-02 06/20/2017 06/27/2017 < 2.38E-02 < 4.32E-02 < 4.33E-02 < 4.31E-02 < 4.31E-02 06/27/2017 07/11/2017 < 1.22E-02 < 3.14E-02 < 3.15E-02 < 3.12E-02 < 3.09E-02 07/11/2017 07/25/2017 < 3.34E-02 < 3.34E-02 < 3.34E-02 < 3.34E-02 < 1.41E-02 07/25/2017 08/08/2017 < 3.24E-02 < 3.24E-02 < 3.25E-02 < 1.75E-02 < 3.20E-02 08/08/2017 08/22/2017 < 1.27E-02 < 3.04E-02 < 3.04E-02 < 3.03E-02 < 3.02E-02 08/22/2017 09/05/2017 < 1.87E-02 < 3.46E-02 < 3.46E-02 < 3.45E-02 < 3.43E-02 09/05/2017 09/19/2017 < 1.95E-02 < 3.59E-02 < 3.59E-02 < 3.58E-02 < 3.58E-02 09/19/2017 10/03/2017 < 1.45E-02 < 3.46E-02 < 3.46E-02 < 3.51E-02 < 3.53E-02 10/03/2017 10/17/2017 < 2.36E-02 < 4.37E-02 < 4.38E-02 < 4.34E-02 < 4.32E-02 10/17/2017 10/31/2017 < 2.61E-02 < 2.62E-02 < 2.19E-02 < 2.62E-02 < 2.60E-02 10/31/2017 11/14/2017 < 1.68E-02 < 4.00E-02 < 4.00E-02 < 3.99E-02 < 3.98E-02 11/14/2017 11/28/2017 < 1.57E-02 < 3.72E-02 < 3.73E-02 < 3.69E-02 < 3.71E-02 11/28/2017 12/12/2017 < 2.50E-02 < 1.05E-02 < 2.50E-02 < 2.48E-02 < 2.49E-02 12/12/2017 12/19/2017 < 2.43E-02 < 2.91E-02 < 2.91E-02 < 2.92E-02 < 2.89E-02 12/19/2017 01/02/2018 < 1.05E-02 < 2.97E-02 < 2.97E-02 < 2.96E-02 < 2.96E-02

Enclosure to 0CAN051801 Page 30 of 49 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators) 1st Qtr 17 2nd Qtr 17 3rd Qtr 17 4th Qtr 17 Annual Mean 17 Station (mrem) (mrem) (mrem) (mrem) (mrem) 1 7.7 7.3 9.2 9.1 8.3 2 6.8 7.8 8.4 9.0 8.0 3 5.1 5.0 6.0 5.9 5.5 4 7.4 7.7 8.6 8.2 7.9

  • 56 9.4 9.9 10.4 10.4 10.0 108 7.5 7.9 8.4 9.2 8.2 109 7.6 7.8 9.6 8.9 8.4 110 7.9 7.6 8.5 8.8 8.2 145 6.4 7.4 7.9 8.8 7.6 146 7.9 10.2 7.8 8.6 8.6 147 6.7 6.3 7.5 8.5 7.2 148 9.0 9.1 8.5 8.6 8.8 149 7.3 7.1 9.0 9.3 8.1 150 8.8 8.7 9.8 10.0 9.3 151 8.2 7.8 8.8 9.8 8.6 152 5.5 6.4 6.8 7.4 6.5
  • Station with highest annual mean. Total Inner Ring Annual Mean - 8.0mrem

Enclosure to 0CAN051801 Page 31 of 49 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr 17 2nd Qtr 17 3rd Qtr 17 4th Qtr 17 Annual Mean 17 (mrem) (mrem) (mrem) (mrem) (mrem) 6 6.8 6.9 6.9 7.0 6.9 111 5.0 5.3 5.8 5.9 5.5 116 8.3 8.8 9.2 9.9 9.0 125 5.0 5.0 5.1 5.8 5.2 127 7.2 7.5 8.0 LOST 7.5

  • 137 8.1 10.4 9.2 9.4 9.2 153 7.2 7.2 7.3 8.2 7.4
  • Stations with highest annual mean. Total Special Interest Annual Mean - 7.2mrem Special Interest Areas - (Control)

Station 1st Qtr 17 2nd Qtr 17 3rd Qtr 17 4th Qtr 17 Annual Mean 17 (mrem) (mrem) (mrem) (mrem) (mrem) 7 6.3 7.0 6.6 7.2 6.7

Enclosure to 0CAN051801 Page 32 of 49 Table 3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/l Location Start Date End Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Required LLD 15 15 30 15 30 15 30 15 15 18 60 15 Station 8 (Indicator) 12/31/2016 01/31/2017 <2.11 <2.31 <5.88 <2.26 <4.66 <2.51 <4.17 <9.71 <2.14 <2.00 <20.0 <6.87 Station 10 (Control) 12/31/2016 01/31/2017 <7.47 <7.91 <14.9 <10.7 <20.2 <9.23 <16.7 <10.7 <9.98 <10.0 <41.9 <12.8 Station 8 (Indicator) 01/31/2017 02/28/2017 <2.03 <2.46 <5.87 <2.13 < 4.61 <2.72 < 4.52 <12.5 <2.40 <2.29 < 21.1 < 6.53 Station 10 (Control) 01/31/2017 02/28/2017 <7.03 <5.46 <11.8 <7.28 <13.2 <7.54 <14.0 <11.9 <7.51 <7.04 <33.7 <10.8 Station 8 (Indicator) 02/29/2017 03/31/2017 <1.63 <1.91 <4.30 <1.61 <3.18 <1.87 <3.57 <10.6 <1.80 <1.75 <16.8 <5.59 Station 10 (Control) 02/29/2017 03/31/2017 <10.2 <9.33 <15.4 <6.38 <17.6 <8.46 <15.7 <13.0 <10.3 <9.49 <36.7 <12.3 Station 8 (Indicator) 03/31/2017 04/30/2017 <2.31 <2.68 <5.50 <2.42 <4.84 <3.09 <5.48 <13.9 <2.88 <2.49 <22.5 <8.42 Station 10 (Control) 03/31/2017 04/30/2017 <4.56 <5.68 <12.5 <4.52 <11.1 <6.75 <10.2 <8.98 <7.23 <6.35 <24.0 <9.54 Station 8 (Indicator) 04/30/2017 05/31/2017 <2.14 <2.33 <4.97 <1.89 <4.07 <2.44 <4.18 <14.9 <2.23 <2.13 <23.4 <5.87 Station 10 (Control) 04/30/2017 05/31/2017 <6.91 <6.93 <15.1 <7.70 <16.8 <6.99 <13.6 <10.2 <7.88 <7.61 <31.6 <11.4 Station 8 (Indicator) 05/31/2017 06/30/2017 <2.18 <2.45 <5.63 <2.06 <4.39 <2.44 <4.32 <13.1 <2.29 <2.06 <22.2 <7.81 Station 10 (Control) 05/31/2017 06/30/2017 <5.12 <6.79 <15.7 <7.11 <11.0 <6.31 <12.0 <10.9 <6.00 <8.36 <27.8 <7.59 Station 8 (Indicator) 06/30/2017 07/31/2017 <1.80 <2.16 <4.96 <2.08 <4.01 <2.18 <3.87 <9.24 <1.94 <2.10 <17.3 <5.58 Station 10 (Control) 06/30/2017 07/31/2017 <9.58 <8.89 <15.4 <9.08 <22.1 <9.36 <16.2 <11.7 <10.4 <9.93 <36.9 <10.4 Station 8 (Indicator) 07/31/2017 08/31/2017 <1.94 <2.14 <5.30 <2.33 <4.17 <2.27 <3.95 <12.9 <2.20 <2.04 <22.2 <8.41 Station 10 (Control) 07/31/2017 08/31/2017 <8.63 <10.7 <18.0 <9.48 <14.8 <7.07 <14.0 <12.5 <9.79 <10.6 <39.6 <11.9 Station 8 (Indicator) 08/31/2017 09/30/2017 <1.76 <2.19 <5.11 <1.77 <3.92 <2.27 <4.15 < 14.5 <2.17 <1.91 <23.6 <7.76 Station 10 (Control) 08/31/2017 09/30/2017 <4.14 <5.15 <10.8 <3.90 <10.4 <4.52 <7.86 <9.22 <4.85 <4.80 <25.8 <6.50 Station 8 (Indicator) 09/30/2017 10/31/2017 <2.33 <2.42 <5.19 <2.15 <4.72 <2.76 <4.63 <12.0 <2.57 <2.47 <21.6 <5.63 Station 10 (Control) 09/30/2017 10/31/2017 <5.39 <5.08 <11.4 <7.47 <13.4 <5.98 <10.8 <8.58 <6.55 <6.77 <27.3 <6.80 Station 8 (Indicator) 10/31/2017 11/30/2017 <2.72 <2.88 <6.10 <2.75 <5.45 <2.86 <4.83 <14.2 <2.77 <2.42 <23.8 <8.89 Station 10 (Control) 10/31/2017 11/30/2017 <5.23 <5.32 <13.5 <5.49 <15.8 <5.83 <11.1 <10.1 <7.44 <6.88 <28.6 <13.4 Station 8 (Indicator) 11/30/2017 12/31/2017 <2.89 <3.25 <6.49 <2.99 <6.67 <3.44 <5.49 <14.4 <3.38 <2.93 <27.7 <8.84 Station 10 (Control) 11/30/2017 12/31/2017 <6.49 <6.97 <14.4 <6.59 <16.5 <8.10 <10.0 <9.39 <6.98 <7.97 <26.1 <6.09

Enclosure to 0CAN051801 Page 33 of 49 Table 3.2 Sample Type: Surface Water Analysis: Tritium Units: pCi/l Location Begin Date End Date H-3 Required LLD 3000 Station 8 (Indicator) 12/31/2016 03/31/2017 637 Station 10 (Control) 12/31/2016 03/31/2017 < 336 Station 8 (Indicator) 03/31/2017 06/30/2017 405 Station 10 (Control) 03/31/2017 06/30/2017 < 305 Station 8 (Indicator) 06/30/2017 09/30/2017 401 Station 10 (Control) 06/30/2017 09/30/2017 < 364 Station 8 (Indicator) 09/30/2017 12/31/2017 < 358 Station 10 (Control) 09/30/2017 12/31/2017 < 355

Enclosure to 0CAN051801 Page 34 of 49 Table 4.1 Sample Type: Drinking Water Analysis: Gross Beta, Iodine-131, Gamma Isotopic Units: pCi/l Collection Gross Location Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Date Beta Required LLD 4.0 15 15 30 15 30 15 30 1.0 15 18 60 15 Station 14 (Indicator) 01/03/2017 <1.50 <6.11 <7.21 <13.6 <9.29 <14.9 <5.17 <15.9 <0.752 <5.37 <7.74 <29.6 <10.3 Station 57 (Control) 01/03/2017 < 1.70 <6.82 <8.14 <16.2 <7.39 <14.2 <7.85 <9.88 <0.483 <7.92 <7.47 <39.9 <12.8 Station 14 (Indicator) 03/28/2017 <1.60 <5.72 <5.21 <14.5 <5.71 <10.3 <6.14 <9.93 <0.418 <5.25 <5.21 <20.5 <7.03 Station 57 (Control) 03/28/2017 <2.81 <6.07 <5.29 <12.8 <6.46 <14.6 <6.43 <11.2 <0.468 <7.01 <6.14 <24.7 <7.10 Station 14 (Indicator) 06/20/2017 <2.48 <4.25 <4.47 <8.58 <4.80 <8.35 <4.43 <7.41 <0.405 <4.98 <4.64 <16.6 <6.36 Station 57 (Control) 06/20/2017 <2.62 <5.66 <3.71 <8.41 <5.54 <10.5 <4.99 <8.32 <0.413 <6.36 <5.77 <19.6 <6.31 Station 14 (Indicator) 10/03/2017 1.48 <7.78 <5.07 <10.7 <5.25 <12.0 <6.99 <8.88 <0.179 <5.61 <6.06 <24.4 <7.02 Station 57 (Control) 10/03/2017 2.76 <5.58 <5.86 <10.6 <6.09 <11.9 <5.88 <10.6 <0.193 <5.67 <5.12 <29.5 <8.16

Enclosure to 0CAN051801 Page 35 of 49 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 2000 Station 14 (Indicator) 01/03/2017 < 400 Station 57 (Control) 01/03/2017 < 386 Station 14 (Indicator) 03/28/2017 < 348 Station 57 (Control) 03/28/2017 < 338 Station 14 (Indicator) 06/20/2017 < 227 Station 57 (Control) 06/20/2017 < 241 Station 14 (Indicator) 10/03/2017 < 366 Station 57 (Control) 10/03/2017 < 364 Table 5.1 Sample Type: Sediment Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Cs-134 Cs-137 Required LLD 150 180 Station 8 (Indicator) 9/13/2017 < 103 < 73.8 Station 16 (Control)* 9/13/2017 < 80.4 < 75.3

Enclosure to 0CAN051801 Page 36 of 49 Table 6.1 Sample Type: Fish Analysis: Gamma Isotopic Units: pCi/kg Location Collection Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Required LLD 130 130 260 130 260 130 150 Station 8 (Indicator) 10/10/2017 < 53.30 < 48.80 < 85.60 < 57.10 < 93.80 < 58.20 < 50.20 Station 16 (Control) 10/10/2017 < 62.50 < 63.30 < 140.0 < 60.10 < 95.9 < 74.30 < 53.4 Table 7.1 Sample Type: Food Products Analysis: Iodine-131, Gamma Isotopic Units: pCi/kg Location Collection Date I-131 Cs-134 Cs-137 Required LLD 60 60 80 Station 13 (Indicator) 06/20/2017 < 51.4 < 44.1 < 43.7 Station 55 (Control) 06/20/2017 < 46.3 < 41.4 < 45.6 Station 13 (Indicator) 07/11/2017 < 59.0 < 40.5 < 40.0 Station 55 (Control) 07/11/2017 < 56.4 < 44.1 < 43.6 Station 13 (Indicator) 08/08/2017 < 46.2 < 39.8 < 45.5 Station 55 (Control) 08/08/2017 < 50.7 < 51.1 < 30.9

Enclosure to 0CAN051801 Page 37 of 49 Table 8.1 Sample Type: Groundwater Analysis: Iodine-131, Gamma Isotopic Units: pCi/l Collection Sample # Gr-B Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Date Required LLD 4.00 15 15 30 15 30 15 30 15 15 18 60 15 58* 03/22/2017 < 2.24 < 5.60 < 6.45 < 14.2 < 6.98 < 11.1 < 6.97 < 8.59 < 9.14 < 6.49 < 5.26 < 27.9 < 10.0 62* 03/22/2017 < 2.94 < 6.41 < 5.69 < 13.9 < 6.04 < 11.6 < 5.97 < 11.7 < 11.1 < 7.07 < 7.24 < 28.5 < 8.81 63 03/22/2017 3.47 < 6.20 < 7.83 < 15.3 < 8.34 < 16.3 < 7.14 < 15.1 < 11.0 < 8.53 < 7.62 < 33.7 < 10.3 64 03/23/2017 < 3.37 < 5.56 < 4.55 < 12.2 < 6.05 < 12.7 < 5.90 < 9.52 < 9.25 < 5.92 < 6.48 < 26.0 < 5.88 58* 06/13/2017 < 2.01 < 4.68 < 5.53 < 10.9 < 5.90 < 9.11 < 5.98 < 9.33 < 14.3 < 5.41 < 4.85 < 32.8 < 6.40 62* 06/13/2017 < 3.06 < 4.31 < 3.98 < 10.1 < 5.25 < 8.94 < 5.34 < 9.11 < 14.6 < 5.86 < 4.99 < 30.0 < 11.1 63 06/13/2017 < 3.09 < 5.95 < 5.81 < 12.1 < 6.22 < 9.97 < 5.42 < 7.82 < 14.0 < 6.03 < 5.72 < 38.4 < 13.3 64 06/14/2017 < 3.12 < 5.73 < 4.90 < 13.3 < 6.72 < 9.57 < 6.17 < 9.57 < 13.9 < 6.41 < 6.18 < 35.2 < 10.8 58* 09/12/2017 < 2.08 < 5.62 < 5.63 < 15.4 < 5.60 < 10.7 < 5.70 < 9.60 < 14.8 < 6.71 < 5.42 < 32.5 < 11.6 62* 09/12/2017 < 3.90 < 3.93 < 4.28 < 11.5 < 4.27 < 8.48 < 4.41 < 8.18 < 12.0 < 3.94 < 4.81 < 31.4 < 7.27 63 09/12/2017 < 2.28 < 4.46 < 5.37 < 12.0 < 4.74 < 9.11 < 5.13 < 10.1 < 12.6 < 5.37 < 4.32 < 36.0 < 9.88 64 09/13/2017 < 3.04 < 4.88 < 5.47 < 9.81 < 5.04 < 10.7 < 6.56 < 10.2 < 14.3 < 5.62 < 6.10 < 33.2 < 9.92 58* 12/13/2017 5.61 < 7.32 < 6.33 < 15.7 < 9.76 < 20.5 < 8.93 < 12.8 < 14.6 < 11.5 < 6.17 < 39.2 < 11.2 62* 12/13/2017 < 2.57 < 5.32 < 6.83 < 15.5 < 7.19 < 17.1 < 6.90 < 9.62 < 11.9 < 9.57 < 7.62 < 33.7 < 14.9 63 12/13/2017 4.60 < 7.63 < 8.91 < 11.2 < 6.61 < 18.0 < 8.62 < 11.8 < 12.1 < 8.40 < 8.14 < 44.4 < 12.5 64 12/14/2017 3.40 < 7.08 < 7.08 < 14.2 < 7.49 < 19.5 < 9.12 < 13.4 < 14.3 < 7.88 < 7.67 < 39.1 < 9.18

  • Identifies Control Locations

Enclosure to 0CAN051801 Page 38 of 49 Table 8.2 Sample Type: Groundwater Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 3000 Station 58 (Control) 03/17/2016 < 286 Station 62 (Control) 03/17/2016 < 288 Station 63 (Indicator) 03/16/2016 < 287 Station 64 (Indicator) 03/16/2016 < 289 Station 58 (Control) 06/01/2016 < 373 Station 62 (Control) 06/01/2016 < 380 Station 63 (Indicator) 06/01/2016 < 376 Station 64 (Indicator) 06/02/2016 < 379 Station 58 (Control) 09/13/0216 < 300 Station 62 (Control) 09/13/0216 < 284 Station 63 (Indicator) 09/13/0216 < 303 Station 64 (Indicator) 09/14/2016 < 290 Station 58 (Control) 12/14/2016 < 347 Station 62 (Control) 12/14/2016 < 339 Station 63 (Indicator) 12/14/2016 < 341 Station 64 (Indicator) 12/15/2016 < 357

Enclosure to 0CAN051801 Page 39 of 49 ATTACHMENT 2 INTERLABORATORY COMPARISON PROGRAM

Enclosure to 0CAN051801 Page 40 of 49 INTERLABORATORY COMPARISON PROGRAM (ICP)

Summary of Results The Teledyne Brown Engineering (TBE) Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

A. Analytics Evaluation Criteria Analytics evaluation report provides a ratio of TBEs result and Analytics known value. Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal quality control (QC) requirements based on the DOE MAPEP criteria.

B. ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the U.S. Environmental Protection Agency (EPA), National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements, or ERAs standard operating procedure for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

C. DOE Evaluation Criteria MAPEPs evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

Acceptable (flag = A) - result within +/- 20% of the reference value Acceptable with Warning (flag = W) - result falls in the +/- 20% to +/- 30% of the reference value Not Acceptable (flag = N) - bias is greater than 30% of the reference value Note: The DOE MAPEP samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

For the TBE laboratory, 168 out of 173 analyses performed met the specified acceptance criteria. Five analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program.

1. The ERA April 2017 two nuclides in water were evaluated as Not Acceptable. (NCR 17-09)
a. The Zn-65 result of 39.3 pCi/L, exceeded the lower acceptance limit of 47.2. The known value was unusually low for this study. The sample was run in duplicate on two different detectors. The results of each were 39.3 +/- 18.2 pCi/L (46% error and lower

Enclosure to 0CAN051801 Page 41 of 49 efficiency) and 59.3 +/- 8.23 pCi/L (13.9% error and higher efficiency). The result from the 2nd detector would have been well within the acceptable range (47.2 - 65.9) and 110.2% of the known value of 53.8 pCi/L.

b. The Sr-89 result of 40.7 pCi/L exceeded the lower acceptance limit of 53.8. All associated QC and recoveries were reviewed and no apparent cause could be determined for the failure. The prior three cross-check results were from 99 - 115% of the known values and the one that followed this sample (November, 2017) was 114%

of the known value.

2. The DOE MAPEP August 2017 air particulate U-238 result of 0.115 +/- 0.025 Bq/sample was higher than the known value of 0.087 +/- 0.002 with a ratio of 1.32, therefore the upper ratio of 1.30 (acceptable with warning) was exceeded. TBEs result with error easily overlaps with the acceptable range. MAPEP does not evaluate results with any associated error.

Also, the spike level for this sample was very low (2.35 pCi) compared to TBEs normal lab control sample (LCS) of 6 pCi. TBE considers this result as passing. (NCR 17-15)

3. The Analytics September 2017 soil Cr-51 result was evaluated as Not Acceptable (Ratio of TBE to known result at 0.65). The reported value was 0.230 +/- 0.144 pCi/g and the known value was 0.355 +/- 0.00592 pCi/g. The sample was counted overnight for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />, however the Cr-51 was spiked at a very low level and had a counting error of 65%. Cr-51 has a 27-day half-life, making low-level quantification even more difficult. The error does not appear to have been taken into consideration for this result. If it had been evaluated with the error, the highest result would have been 105% of the reference value, which is acceptable. Also, the known value is significantly lower than TBEs typical minimum detectable concentration (MDC) for this nuclide in a soil matrix and would typically not be reported to clients (unless specified). The results of all of the previous cross-checks have been in the acceptable (80 - 120%) range. TBE will evaluate further upon completion of the next ICP sample. (NCR 17-16)
4. The ERA November 2017 water Sr-90 sample was evaluated as Not Acceptable. TBEs result of 27.1 pCi/L exceeded the lower acceptance range (30.8 - 48.0 pCi/L). After reviewing the associated QC data for this sample, it was determined that although the spike recovery for Sr-90 was within our laboratory guidelines (70% -130%), both the spike result and our ERA result were biased low. The original cross-check sample was completely consumed and we were unable to reanalyze before submitting the result. We have modified our preparation process to avoid this situation for future cross-check samples. We also have enhanced Laboratory Information Management System (LIMS) programming to force a LSC duplicate when a workgroup includes cross-check samples (as opposed to running a duplicate). (NCR 17-19)

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data.

Enclosure to 0CAN051801 Page 42 of 49 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Ratio of TBE to Identification Known Month/Year Matrix Nuclide Units Reported (a) Analytics Evaluation(b)

Number Value Value Result March 2017 E11811 Milk Sr-89 pCi/L 87 97.7 0.89 A Sr-90 pCi/L 12.4 16.2 0.77 A E11812 Milk Ce-141 pCi/L 135 145 0.93 A Co-58 pCi/L 153 150 1.02 A Co-60 pCi/L 182 183 1.00 A Cr-51 pCi/L 258 290 0.89 A Cs-134 pCi/L 104 120 0.87 A Cs-137 pCi/L 142 140 1.02 A Fe-59 pCi/L 135 129 1.05 A I-131 pCi/L 92.6 97.9 0.95 A Mn-54 pCi/L 173 164 1.05 A Zn-65 pCi/L 208 199 1.04 A E11813 Charcoal I-131 pCi 92 93.9 0.98 A E11814 AP Ce-141 pCi 99.9 101 0.99 A Co-58 pCi 95.4 104 0.92 A Co-60 pCi 140 127 1.10 A Cr-51 pCi 211 201 1.05 A Cs-134 pCi 82.1 83.2 0.99 A Cs-137 pCi 92.8 97.0 0.96 A Fe-59 pCi 107 89.3 1.20 A Mn-54 pCi 106 114 0.93 A Zn-65 pCi 137 138 0.99 A E11816 Soil Ce-141 pCi/g 0.258 0.250 1.03 A Co-58 pCi/g 0.241 0.258 0.93 A Co-60 pCi/g 0.312 0.315 0.99 A Cr-51 pCi/g 0.439 0.500 0.88 A Cs-134 pCi/g 0.176 0.207 0.85 A Cs-137 pCi/g 0.304 0.317 0.96 A Fe-59 pCi/g 0.210 0.222 0.95 A Mn-54 pCi/g 0.292 0.283 1.03 A Zn-65 pCi/g 0.353 0.344 1.03 A E11815 Water Fe-55 pCi/L 1600 1890 0.85 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30

Enclosure to 0CAN051801 Page 43 of 49 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Ratio of TBE to Identification Known Month/Year Matrix Nuclide Units Reported (a) Analytics Evaluation(b)

Number Value Value Result June 2017 E11844 Milk Sr-89 pCi/L 81.3 92.6 0.88 A Sr-90 pCi/L 12.1 13.5 0.90 A E11846 Milk Ce-141 pCi/L 142 151 0.94 A Co-58 pCi/L 147 155 0.95 A Co-60 pCi/L 185 191 0.97 A Cr-51 pCi/L 321 315 1.02 A Cs-134 pCi/L 168 188 0.89 A Cs-137 pCi/L 148 150 0.99 A Fe-59 pCi/L 116 115 1.01 A I-131 pCi/L 102 93.6 1.09 A Mn-54 pCi/L 168 172 0.98 A Zn-65 pCi/L 195 204 0.96 A E11847 Charcoal I-131 pCi 87.9 84.8 1.04 A E11845 AP Sr-89 pCi 70.8 79.1 0.90 A Sr-90 pCi 9.10 11.5 0.79 W E11816 AP Ce-141 pCi 112 116 0.96 A Co-58 pCi 119 119 1.00 A Co-60 pCi 171 146 1.17 A Cr-51 pCi 270 241 1.12 A Cs-134 pCi 152 144 1.05 A Cs-137 pCi 114 115 0.99 A Fe-59 pCi 94.1 88.3 1.07 A Mn-54 pCi 139 132 1.06 A Zn-65 pCi 141 156 0.90 A E11849 Water Fe-55 pCi/L 1840 1890 0.97 A July 2017 E11901 AP GR-A pCi 50.1 44.2 1.13 A GR-B pCi 218 233 0.93 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30

Enclosure to 0CAN051801 Page 44 of 49 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Ratio of TBE to Identification Known Month/Year Matrix Nuclide Units Reported (a) Analytics Evaluation(b)

Number Value Value Result September E11914 Milk Sr-89 pCi/L 84.3 82.7 1.02 A 2017 Sr-90 pCi/L 12.6 12.1 1.04 A E11915 Milk Ce-141 pCi/L 93.9 87.0 1.08 A Co-58 pCi/L 115 117 0.98 A Co-60 pCi/L 265 262 1.01 A Cr-51 pCi/L 273 217 1.26 W Cs-134 pCi/L 186 201 0.93 A Cs-137 pCi/L 175 172 1.02 A Fe-59 pCi/L 137 125 1.09 A I-131 pCi/L 78.0 71.0 1.10 A Mn-54 pCi/L 128 123 1.04 A Zn-65 pCi/L 206 184 1.12 A E11916 Charcoal I-131 pCi 71.9 64.4 1.12 A E11917 AP Ce-141 pCi 80.1 86.3 0.93 A Co-58 pCi 110 116 0.95 A Co-60 pCi 277 260 1.07 A Cr-51 pCi 275 215 1.28 W Cs-134 pCi 192 199 0.96 A Cs-137 pCi 165 170 0.97 A Fe-59 pCi 122 124 0.98 A Mn-54 pCi 120 122 0.99 A Zn-65 pCi 175 183 0.96 A E11918 Water Fe-55 pCi/L 1630 1630 1.00 A E11919 Soil Ce-141 pCi/g 0.136 0.142 0.96 A Co-58 pCi/g 0.179 0.191 0.94 A Co-60 pCi/g 0.405 0.429 0.94 A Cr-51 pCi/g 0.230 0.355 0.65 N(1)

Cs-134 pCi/g 0.272 0.328 0.83 A Cs-137 pCi/g 0.336 0.356 0.94 A Fe-59 pCi/g 0.210 0.205 1.02 A Mn-54 pCi/g 0.210 0.201 1.05 A Zn-65 pCi/g 0.301 0.301 1.00 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) See NCR 17-16

Enclosure to 0CAN051801 Page 45 of 49 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Ratio of TBE to Identification Known Month/Year Matrix Nuclide Units Reported (a) Analytics Evaluation(b)

Number Value Value Result December E12054 Milk Sr-89 pCi/L 92.1 92.3 1.00 A 2017 Sr-90 pCi/L 18.3 16.9 1.09 A E12055 Milk Ce-141 pCi/L 97.8 98.3 0.99 A Co-58 pCi/L 92.3 89.9 1.03 A Co-60 pCi/L 176 173 1.02 A Cr-51 pCi/L 226 242 0.93 A Cs-134 pCi/L 118 125 0.95 A Cs-137 pCi/L 148 141 1.05 A Fe-59 pCi/L 123 113 1.08 A I-131 pCi/L 66.0 57.8 1.14 A Mn-54 pCi/L 173 161 1.08 A Zn-65 pCi/L 233 211 1.10 A E12056 Charcoal I-131 pCi 48.1 47.5 1.01 A E12057A AP Ce-141 pCi 108 111 0.97 A Co-58 pCi 89.5 102 0.88 A Co-60 pCi 223 196 1.14 A Cr-51 pCi 311 274 1.13 A Cs-134 pCi 141 142 1.00 A Cs-137 pCi 162 160 1.01 A Fe-59 pCi 121 129 0.94 A Mn-54 pCi 177 182 0.97 A Zn-65 pCi 203 239 0.85 A E12058 Water Fe-55 pCi/L 1970 1740 1.13 A E12059 AP Sr-89 pCi 71.2 87.4 0.81 A Sr-90 pCi 12.9 16.0 0.81 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30

Enclosure to 0CAN051801 Page 46 of 49 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptable (b)

Month/Year Matrix Nuclide Units Reported (a) Evaluation Number Value Range Value February 17-MaS36 Soil Ni-63 Bq/kg -5.512 92.3 (1) A 2017 Sr-90 Bq/kg 571 624 437 - 811 A 17-MaW36 Water Am-241 Bq/L 0.693 0.846 0.592 - 1.100 A Ni-63 Bq/L 13.4 12.2 8.5 - 15.9 A Pu-238 Bq/L 0.7217 0.703 0.492 - 0.914 A Pu-239/240 Bq/L 0.9277 0.934 0.654 - 1.214 A 17-RdF36 AP U-234/233 Bq/sample 0.0911 0.104 0.073 - 0.135 A U-238 Bq/sample 0.0967 0.107 0.075 - 0.139 A 17-RdV36 Vegetation Cs-134 Bq/sample 6.44 6.95 4.87 - 9.04 A Cs-137 Bq/sample 4.61 4.60 3.22 - 5.98 A Co-57 Bq/sample -0.0229 (1) A Co-60 Bq/sample 8.52 8.75 6.13 - 11.38 A Mn-54 Bq/sample 3.30 3.28 2.30 - 4.26 A Sr-90 Bq/sample 1.30 1.75 1.23 - 2.28 W Zn-65 Bq/sample 5.45 5.39 3.77 - 7.01 A August 17-MaS37 Soil Ni-63 Bq/kg 1130 1220 854 - 1586 A 2017 Sr-90 Bq/kg 296 289 202 - 376 A 17-MaW37 Water Am-241 Bq/L 0.838 0.892 0.624 - 1.160 A Ni-63 Bq/L -0.096 (1) A Pu-238 Bq/L 0.572 0.603 0.422 - 0.784 A Pu-239/240 Bq/L 0.863 0.781 0.547 - 1.015 A 17-RdF37 AP U-234/233 Bq/sample 0.103 0.084 0.059 - 0.109 W U-238 Bq/sample 0.115 0.087 0.061 - 0.113 N(2) 17-RdV37 Vegetation Cs-134 Bq/sample 2.34 2.32 1.62 - 3.02 A Cs-137 Bq/sample 0.05 (1) A Co-57 Bq/sample 3.32 2.8 2.0 - 3.6 A Co-60 Bq/sample 2.09 2.07 1.45 - 2.69 A Mn-54 Bq/sample 2.90 2.62 1.83 - 3.41 A Sr-90 Bq/sample 1.17 1.23 0.86 - 1.60 A Zn-65 Bq/sample 6.07 5.37 3.76 - 6.98 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOE/MAPEP evaluation:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) False Positive Test (2) See NCR 17-15

Enclosure to 0CAN051801 Page 47 of 49 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptable (b)

Month/Year Matrix Nuclide Units Reported (a) Evaluation Number Value Limits Value March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 - 133 A April 2017 RAD-109 Water Ba-133 pCi/L 49.2 49.7 40.8 - 55.1 A Cs-134 pCi/L 83.2 90.1 74.0 - 99.1 A Cs-137 pCi/L 202 206 185 - 228 A Co-60 pCi/L 51.2 54.7 49.2 - 62.7 A Zn-65 pCi/L 39.3 53.8 47.2 - 65.9 N(1)

GR-A pCi/L 53.6 75.0 39.5 - 92.3 A GR-B pCi/L 42.7 38.5 25.5 - 46.0 A U-Nat pCi/L 50.1 55.6 45.2 - 61.7 A H-3 pCi/L 7080 6850 5920 - 7540 A Sr-89 pCi/L 40.7 66.2 53.8 - 74.3 N(1)

Sr-90 pCi/L 26.9 26.7 19.3 - 31.1 A I-131 pCi/L 26.7 29.9 24.9 - 34.9 A September MRAD-27 AP GR-A pCi/sample 40.9 50.1 16.8 - 77.8 A 2017 GR-B pCi/sample 58.0 61.8 39.1 - 90.1 A October RAD-111 Water Ba-133 pCi/L 71.3 73.7 61.7 - 81.1 A 2017 Cs-134 pCi/L 43.0 53.0 42.8 - 58.3 A Cs-137 pCi/L 48.2 52.9 47.6 - 61.1 A Co-60 pCi/L 69.0 69.5 62.6 - 78.9 A Zn-65 pCi/L 335 348 313 - 406 A GR-A pCi/L 32.5 35.6 18.3 - 45.8 A GR-B pCi/L 24.3 25.6 16.0 - 33.6 A U-Nat pCi/L 36.6 37.0 30.0 - 40.9 A H-3 pCi/L 6270 6250 5390 - 6880 A I-131 pCi/L 26.4 24.2 20.1 - 28.7 A November 111317O Water Sr-89 pCi/L 57.1 50.0 39.4 - 57.5 A 2017 Sr-90 pCi/L 27.1 41.8 30.8 - 48.0 N(2)

(a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 17-09 (2) See NCR 17-19

Enclosure to 0CAN051801 Page 48 of 49 ATTACHMENT 3 SEDIMENT DOSE CALCULATIONS

Enclosure to 0CAN051801 Page 49 of 49 SEDIMENT DOSE CALCULATIONS Sediment Sample Results Sediment samples were collected from two locations in 2017 and analyzed for gamma radionuclides. Although Cesium-137 has been detected in years prior to 2017, all gamma radionuclides from 2017 samples were below detectable limits. These results are consistent with 2016 results where all gamma radionuclides were also below detectable limits. Therefore, ANO operations had no significant impact on the environment or public by this waterborne pathway.

In previous reports, ANO has included annual maximum dose calculations to the skin and total body. However since gamma radionuclides were below detectable limits, no calculation is being provided since there is no associated dose.

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