0CAN101701, Units 1 and 2, Revised Annual Radiological Environmental Operating Report for 2016

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Units 1 and 2, Revised Annual Radiological Environmental Operating Report for 2016
ML17283A244
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 10/10/2017
From: Pyle S
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
0CAN101701
Download: ML17283A244 (46)
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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 0CAN101701 October 10, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Revised Annual Radiological Environmental Operating Report for 2016 Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

REFERENCES:

1. Entergy letter dated April 28, 2017, Annual Radioactive Effluent Release Report for 2016 (0CAN041702) (ML17118A011)
2. Entergy letter dated May 4, 2017, Annual Radiological Environmental Operating Report for 2016 (0CAN051702) (ML17276B200)

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 (AREOR) for the previous year is required by May 15 of each year. The subject ANO report for the calendar year 2016 was submitted on May 4, 2017, as noted in Reference 2 above.

Historically, Attachment 2 of the report, Interlaboratory Comparison Program, has contained a summary of analyses that did not meet specified acceptance criteria. However, due to a change in departmental personnel responsible for AREOR development, Attachment 2 of the Reference 2 report included the specific detailed analyses (instead of a summary of the results),

which contained information marked as confidential to the associated vendor. Therefore, the ANO AREOR for 2016 is hereby resubmitted in its entirety (for convenience), replacing the detailed and confidential information previously included in Attachment 2 with a summary of the analysis comparison results, consistent with historical ANO AREOR reports. Entergy Operations, Inc. (Entergy) requests the NRC replace the previous May 4, 2017 (Reference 2) correspondence accordingly. Except for Attachment 2 of the report, no data contained in the Reference 2 correspondence has been changed or revised.

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

0CAN101701 Page 2 of 2 The radionuclides detected by the radiological environmental monitoring program during 2016 were significantly below the regulatory limits. The operation of the ANO station during 2016 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 Reference 1 correspondence.

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/dbb

Enclosure:

Annual Radiological Environmental Operating Report for 2016 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 0CAN101701 Annual Radiological Environmental Operating Report for 2016

Enclosure to 0CAN101701 Page 1 of 43 Table of Contents Summary.................................................................................................................................. 2 1.0 Introduction .................................................................................................................... 7 1.1 Radiological Environmental Monitoring Program ................................................ 7 1.2 Pathways Monitored ............................................................................................ 7 1.3 Land Use Census ................................................................................................ 7 2.0 Interpretation and Trends of Results ............................................................................. 18 2.1 Air Particulate and Radioiodine Sample Results ................................................. 18 2.2 Thermoluminescent Dosimetry (TLD) Sample Results ....................................... 18 2.3 Water Sample Results ........................................................................................ 18 2.4 Sediment Sample Results ................................................................................... 21 2.5 Milk Sample Results ............................................................................................ 21 2.6 Fish Sample Results ........................................................................................... 21 2.7 Food Product Sample Results............................................................................. 21 2.8 Interlaboratory Comparison Results .................................................................... 21 2.9 Land Use Census Results ................................................................................... 21 3.0 Radiological Environmental Monitoring Program Summary .......................................... 22 3.1 2016 Program Results Summary ........................................................................ 22 Tables Table 1.1 Radiological Environmental Sampling Program ............................................... 9 Table 2.1 2015 Land Use Census .................................................................................... 22 Table 3.1 Radiological Environmental Monitoring Program Summary ............................. 23 Figures Figure 1-1 TLD Sample Collection Sites - NEAR FIELD................................................... 15 Figure 1-2 TLD Sample Collection Sites - FAR FIELD ..................................................... 16 Figure 1-3 Stormwater Sample Collection Sites - SITE MAP ........................................... 17 Attachments Summary of Monitoring Results Interlaboratory Comparison Program Sediment Dose Calculations

Enclosure to 0CAN101701 Page 2 of 43 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, 2016, through December 31, 2016. This report fulfills the requirements of ANO Unit 1 Technical Specification (TS) 5.6.2 and Unit 2 TS 6.6.2.

During 2016, 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 2016 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 2014 and 2015 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 2016, 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 2016 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 2016. Therefore, no analysis or planned course of action to alleviate problems was necessary.

Enclosure to 0CAN101701 Page 3 of 43 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, 2016 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 2016 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 0CAN101701 Page 4 of 43 Air Samples Listed below are air sampler deviations that occurred during 2016 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 02/23/2016, totalizer run time for the listed sampling period was 7 02/9/2016 - 02/23/2016 approximately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> less than expected.

The totalizer was verified to be not advancing as required. (CR-ANO-C-2016-00886)

As documented on 05/17/2016, the sample pump was not working at the time of sample 2 05/03/2016 - 05/17/2016 collection. The run time for this station was approximately two hours less than expected.

(CR-ANO-C-2016-02187)

As documented on 09/06/2016, the totalizer run time for the listed sampling period was 7 08/23/2016 - 09/06/2016 approximately six hours less than expected.

(CR-ANO-C-2016-03639)

As documented on 10/01/2016, ANO Chemistry was notified by the contracted lab for analyzing REMP samples that the air filter 09/06/2016 - 09/20/2016 from Station #56 was unusually light implying 56 and part of 09/20/2016 -

no air flow through the filter. Investigations by 10/04/2016 ANO Chemistry revealed a broken air tube that was repaired on 10/01/2016.

(CR-ANO-C-2016-04112)

As documented on 10/18/2016, the air pump was found to be non-functional on 10/17/2016.

56 10/04/2016-10/18/2016 The pump was replaced on 10/18/2016.

(CR-ANO-C-2016-04428)

As documented on 12/13/16, the air pump was found to be non-functional on 12/12/16. The 6 11/29/16 - 12/12/16 pump was replaced on 12/12/16.

(CR-ANO-C-2016-05352)

As documented on 12/22/16, the air pump was found to be non-functional on 12/22/16. The 6 12/12/16 - 12/22/16 pump was replaced on 12/22/16.

(CR-ANO-C-2016-05453)

Enclosure to 0CAN101701 Page 5 of 43 Missed Samples First quarter environmental TLD Station #149 missing (CR-ANO-C-2016-01646).

Second quarter environmental TLD Station #150 missing (CR-ANO-C-2016-02488).

Third quarter environmental TLD Station #109 missing (CR-ANO-C-2016-04191).

Located missing third quarter TLD at the correct location for Station #109. Also determined that fourth quarter TLD was in wrong location for Station #109 (CR-ANO-C-2017-00124).

Fourth quarter environmental TLD Station #127 missing (CR-ANO-C-2017-00106).

Unavailable Results None Program Modifications The following revisions were made to OP-1608.005, Radiological Environmental Monitoring Program (REMP) in 2016. Collectively, these changes were made through revision to the procedure, OP-1608.005, and Revisions 43 and 44 and to the ODCM.

ANO Site Procedure OP-1608.005 Editorial changes throughout the procedure to improve place-keeping and clarity without changing the process or intent.

Clarification was provided on the way to verify the composite sampler flow rate as 45 - 95 ml/hr. The procedure was changed to provide a place to document this verification.

The reference to a bag holding post-accident snow or ice samples was deleted because container(s) holding collection of samples may be a box or plastic tote. No radiological requirements or controls were diluted or negatively affected by this change because field radiological checks are now required for each sample rather than a collection of samples in a bag.

Deleted the steps that state: Process and analyze samples in accordance with OP-1905.002, Offsite Emergency Monitoring. These samples are not analyzed by ANO Chemistry, but are instead the Offsite Team Coordinators responsibility.

Location of sampling Station #55 was changed due to disturbance of the previously used site.

The TLD at Station 149 was moved from the former location to one across the road on a roadside utility pole. The move was made to minimize TLD disturbance due to vandalism.

The TLD at Station 150 was moved from the former location to a utility pole on the south side of the parking lot entrance. The move was made to minimize TLD disturbance due to vandalism

Enclosure to 0CAN101701 Page 6 of 43 Added references that address the use of calibrated flow meters at the REMP air sampling stations.

Added the requirement for the use of the installation of calibrated flow meters as opposed to periodic verification of installed, non-calibrated meters using a calibrated meter. Also calibrated meters should be changed out every 6 months.

Replaced the use of poly bags with poly bottles to accommodate current counting geometries. Also 3.9 liter jugs replaced one-gallon sample containers. This change does not affect any process, but clarifies the containers required to conform to existing Chemistry counting capabilities.

Clarified the existing process to give correct sequence of steps. This change was prompted by verbal comments from the reviewing NRC Inspector during environmental inspection, June 2016.

ODCM Rev 026 - Changed location of control broadleaf vegetation sample site from current location at intersection of Arkansas Highways 27 and 154 to within the Ozark National Forest at the intersection of Forest Service Roads 36 and 1618A. The change was performed due to forest and broadleaf eradication of previous control location.

Rev 027 - Basis (B) 2.5.1, Radiological Environmental Monitoring, background data is updated to include explanation for sample location choice associated with Air Station #2.

Revised explanation of air station samples in highest D/Q and also in the vicinity of a community. Defined community as it relates to this location.

Attachments contains results of air, TLD, water, sediment, fish, and food product samples collected in 2016. 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 2016. 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 0CAN101701 Page 7 of 43 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 2016 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 2015. 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 concerns 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 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 0CAN101701 Page 8 of 43 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 0CAN101701 Page 9 of 43 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 Radioiodine and Particulates Station 2 (243° - 0.5 miles) - South 3 samples close to the Site Boundary, in of the sewage treatment plant.

(or near) different sectors with the Station 56 (264° - 0.4 miles) - West highest calculated annual average end of the sewage treatment plant.

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

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

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.

Thermoluminescent dosimetry (TLDs) Station 1 (88° - 0.5 miles) - On a 16 inner ring stations with two or more pole near the meteorology tower.

dosimeters in each meteorological sector Station 2 (243° - 0.5 miles) - South in the general area of the site boundary. of the sewage treatment plant.

Direct Station 3 (5 - 0.7 miles) - West of Radiation Once per 92 days. Gamma Dose - Once per 92 days.

ANO Gate #2 on Highway 333 (approximately 0.35 miles)

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

Enclosure to 0CAN101701 Page 10 of 43 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 TLDs Station 56 (264° - 0.4 miles) - West 16 inner ring stations with two or more end of the sewage treatment plant.

dosimeters in each meteorological sector Station 108 (306° - 0.9 miles) -

in the general area of the site boundary 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.

Direct Radiation Station 145 (28° - 0.6 miles) - Near Once per 92 days. Gamma Dose - Once per 92 days.

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.

Enclosure to 0CAN101701 Page 11 of 43 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 TLDs Station 149 (156° - 0.5 miles) - On 16 inner ring stations with two or more a utility pole on the south side of dosimeters in each meteorological sector May Road.

in the general area of the Site Boundary. Station 150 (205° - 0.6 miles) -

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

Station 151 (225° - 0.4 miles) -

West side of sewage treatment plant near the lake on a metal post.

Station 152 (338° - 0.8 miles) -

South side of State Highway 333 on a road sign post.

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

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

centers, nearby residences, schools, and Station 7 (210° - 19.0 miles) -

in 1 - 2 areas to serve as control Entergy Supply Yard on Highway 10 locations. in Danville.

Station 111 (120° - 2.0 miles) -

Marina Road on a utility pole on the left just prior to curve.

Station 116 (318° - 1.8 miles) -

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

Enclosure to 0CAN101701 Page 12 of 43 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 TLDs Station 125 (46° - 8.7 miles) -

8 stations with two or more dosimeters in College Street on a utility pole at the special interest areas such as population southeast corner of the red brick centers, nearby residences, schools, and school building.

in 1 - 2 areas to serve as control Station 127 (100° - 5.2 miles) -

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

Direct Radiation Station 137 (151° - 8.2 miles) - On Once per 92 days. Gamma Dose - Once per 92 days.

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.

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.

Station 10 (95° - 0.5 miles) - Plant analyses once per 92 days.

1 control location (uninfluenced by plant intake canal.

discharge)

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

1 indicator location (influenced by plant Russellville city water system from the Illinois Bayou. I-131, gross beta, gamma isotopic discharge)

Once per 92 days. and tritium analyses once per 1 control location (uninfluenced by plant Station 57 (208° - 19.5 miles) -

92 days.

discharge) Danville public water supply treatment on Fifth Street.

Sediment Station 8 (243° - 0.9 miles) - Plant 1 indicator location (influenced by plant discharge canal.

Waterborne discharge) Station 16 (287° - 5.5 miles) - Gamma isotopic analysis once per Once per 365 days.

1 control location (uninfluenced by plant Panther Bay on south side of 365 days.

discharge) Arkansas River across from mouth of Piney Creek.

Enclosure to 0CAN101701 Page 13 of 43 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 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 Station 16 (287° - 5.5 miles) - Gamma isotopic on edible portions vicinity of plant discharge. Once per 365 days.

Panther Bay on south side of once per 365 days.

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

Food Products 1 sample of broadleaf (edible or non-edible) near the site boundary from one Station 13 (273° - 0.5 miles) - West of the highest anticipated annual average from ANO toward Gate 4 onto ground level D/Q sectors, if milk Flatwood Road. Gamma. isotopic and I-131 sampling is not performed. Three per 365 days.

Station 55 (217° - 13.1 miles) - analyses three times per 365 days 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 0CAN101701 Page 14 of 43 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 0CAN101701 Page 15 of 43 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 0CAN101701 Page 16 of 43 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 0CAN101701 Page 17 of 43 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 0CAN101701 Page 18 of 43 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 2016 there were no samples above the LLD for I-131. Indicator gross beta air particulate results for 2016 were comparable to results obtained from 2005-2015 of the operational REMP, but less than 2013 when the annual average was 0.043. Also, the 2016 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 2005 - 2015 (Minimum Value) 0.018 2016 Average Value 0.040 2005 - 2015 (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 includes gross beta concentrations and provides a comparison of the indicator and control means and ranges, emphasizes the consistent trends seen in this pathway to support the presence of naturally occurring activity. Therefore, it can be concluded that the airborne pathway continues to be unaffected by ANO operations.

2.2 Thermoluminescent Dosimetry (TLD) Sample Results ANO reports measured dose as net exposure (field reading less transit reading) normalized to 92 days and relies on comparison of the indicator locations to the control as a measure of plant impact. ANOs comparison of the inner ring and special interest area TLD results to the control, as seen in Table 3.1, identified no noticeable trend that would indicate that the ambient radiation levels are being affected by plant operations. In addition, the inner ring value of 8.0 millirem (mrem) shown in Table 3.1 for 2016 is within the historical bounds of 2005 - 2015 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 2016 drinking water and ground water samples were similar to those reported in previous years. Gamma radionuclides analytical results for 2016 surface water samples were similar to those reported in previous years. Tritium in ANO surface water indicator samples continues to be detected, but at levels below those experienced in 2013 and below the ODCM-required LLD. These results are further explained below.

Enclosure to 0CAN101701 Page 19 of 43 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 2016, 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 2016. Results are reported as annual average pCi/l.

Monitoring Period Result 2005 - 2015 (Minimum Value) 554.5 2016 Value 932.25 2005 - 2015 (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 2016 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 2016 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, 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 2005 - 2015 preoperational and operational years as shown below. Results from 2016 are summarized in Table 3.1. Results are reported as annual average pCi/L.

Radionuclide 2016 2015 2005 - 2014** Preoperational Gross Beta < LLD < LLD* 2.85 2.0 Iodine-131 < LLD < LLD < LLD < LLD Gamma < LLD < LLD < LLD < LLD Tritium < LLD < LLD < LLD 200.0

  • For the control sample collected 1/15/15, gross beta was 3.16 pCi/L which is >MDC, but <LLD; documented via CR-ANO-C-2015-00351.
    • Average of the results from the years 2005-2014

Enclosure to 0CAN101701 Page 20 of 43 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 2016 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. Listed below is a comparison of 2016 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. ANO operations had no significant impact on the environment or public by this waterborne pathway.

Radionuclide 2016 2006 - 2015 Iodine-131 < LLD < LLD Gamma < LLD < LLD Tritium < LLD < LLD Gross Beta 4.32* < LLD**

  • Value from first quarter sampling Station 58.
    • Only 2014 and 2015 data available for review as historical data.

Enclosure to 0CAN101701 Page 21 of 43 2.4 Sediment Sample Results Sediment samples were collected from two locations in 2016 and analyzed for gamma radionuclides. Listed below is a comparison of 2016 indicator results to the 2005 - 2015 operational years. ANO operations had no significant impact on the environment or public by this waterborne pathway. Results are reported as pCi/kg.

Monitoring Period Result 2005 - 2015 (Minimum Value) 41.79 2016 Value < LLD 2005 - 2015 (Maximum Value) 666.8 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 2016 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 2016, 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 2016, food product samples were collected when available from two locations and analyzed for Iodine-131 and gamma radionuclides. The 2016 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.

2.9 Land Use Census Results The latest land use census (performed in 2015) did not identify any new locations that yielded a calculated dose or dose commitment greater than those currently calculated (see Table 2.1).

Enclosure to 0CAN101701 Page 22 of 43 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 2015, 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.

A land use census was not conducted for the year 2016. The next land use census is scheduled to be conducted in 2017.

TABLE 2.1 2015 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 3.0 Radiological Environmental Monitoring Program Summary 3.1 2016 Program Results Summary Table 3.1 summarizes the 2016 REMP results.

Enclosure to 0CAN101701 Page 23 of 43 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 2016 Type / Indicator Location with Highest Annual Mean Control Number of Sample Type Number of LLDb Locations Mean Locations Mean Non-Routine (Units) Locationd Mean (F)c [Range]

Analysesa (F)c [Range] (F)c [Range] Resultse Air Particulates 0.0182 (81 / 81) Station 6* 0.1305 (27 / 27) 0.0182 (54 / 54)

GB / 135 0.01 0 (pCi/m3) [0.015 - 0.072] (243°, 0.5 mi) [0.020 - 0.070] [0.019 - 0.079]

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

(f)

Inner Ring TLDs Gamma / 64 7.70 (61 / 64) Station 56 9.5 (4 / 4) N/A 3 (mR/Qtr) [5.4 - 10.5] (264°, 0.4 mi) [9.2 - 10.5]

Special Interest Gamma / 28 (f) 6.74 (28 / 28) Station 116 8.9 (4 / 4) N/A 0 TLDs (mR/Qtr) [4.3 - 9.0] (318° - 1.8 mi) [8.0 - 9.7]

Control TLD Gamma / 4 (f)

N/A N/A N/A 6.5 (4 / 4) 0 (mR/Qtr) [5.4 - 8.3]

  • As documented on 12/22/16, the air pump was found to be non-functional on 12/22/16. The pump was replaced on 12/22/16. As a result a volume could not be 3

provided to laboratory and the results were given as pCi/Total instead of pCi/m . This has made the annual average high. Without using this data point, the Station 6 average would be 0.0175. Values listed in table do not factor in the 12/22/16 value.

Enclosure to 0CAN101701 Page 24 of 43 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 932 (4* / 4) Station 8 555 (4* / 4) < LLD 0

[344 - 745] (166°, 0.2 mi) [344 - 745]

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 0CAN101701 Page 25 of 43 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 < LLD N/A N/A < LLD 0 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 0CAN101701 Page 26 of 43 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 0CAN101701 Page 27 of 43 ATTACHMENT 1

SUMMARY

OF MONITORING RESULTS

Enclosure to 0CAN101701 Page 28 of 43 Table of Contents Table 1.1 Air Particulate Table 1.2 Radioiodine Cartridge 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 0CAN101701 Page 29 of 43 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 12/29/2015 01/12/2016 0.023 0.021 0.020 0.019 0.022 01/12/2016 01/26/2016 0.025 0.024 0.020 0.021 0.020 01/26/2016 02/09/2016 0.018 0.020 0.016 0.018 0.015 02/09/2016 02/23/2016 0.018 0.016 0.013 0.016 0.018 02/23/2016 03/08/2016 0.016 0.017 0.016 0.016 0.016 03/08/2016 03/22/2016 0.011 0.009 0.011 0.013 0.011 03/22/2016 04/05/2016 0.017 0.015 0.016 0.013 0.016 04/05/2016 04/19/2016 0.017 0.015 0.014 0.014 0.015 04/19/2016 05/03/2016 0.017 0.002 0.015 0.016 0.015 05/03/2016 05/17/2016 0.020 0.018 0.016 0.017 0.018 05/17/2016 05/31/2016 0.015 0.014 0.013 0.015 0.014 05/31/2016 06/14/2016 0.017 0.016 0.015 0.016 0.015 06/14/2016 06/28/2016 0.019 0.018 0.016 0.017 0.017 06/28/2016 07/12/2016 0.018 0.017 0.013 0.015 0.015 07/12/2016 07/26/2016 0.017 0.016 0.019 0.018 0.017 07/26/2016 08/09/2016 0.017 0.016 0.014 0.016 0.017 08/09/2016 08/23/2016 0.012 0.011 0.014 0.011 0.012 08/23/2016 09/06/2016 0.017 0.022 0.014 0.017 0.020 09/06/2016 09/20/2016 0.014 0.012 0.003 0.015 0.014 09/20/2016 10/04/2016 0.025 0.029 0.030 0.026 0.027 10/04/2016 10/18/2016 0.018 0.019 0.008 0.020 0.018 10/18/2016 11/01/2016 0.026 0.028 0.021 0.027 0.026 11/01/2016 11/15/2016 0.026 0.025 0.024 0.026 0.026 11/15/2016 11/29/2016 0.031 0.029 0.026 0.031 0.032 11/29/2016 12/13/2016 0.019 0.016 0.018 0.005 0.020 12/13/2016 12/22/2016 0.032 0.037 0.029 3.070** 0.037 12/22/2016 01/03/2017 0.017 0.019 0.014 0.018 0.015

  • Station with highest annual mean.
    • As documented on 12/22/16, the air pump was found to be non-functional on 12/22/16. The pump was replaced on 12/22/16. As a result a volume could not be provided to laboratory and the results were given as pCi/Total instead of pCi/m3. This has made the annual average high. Without using this data point, the average would be 0.0175. See Sample Deviations in Summary.

Enclosure to 0CAN101701 Page 30 of 43 Table 1.2 Sample Type: Radioiodine Cartridge 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 12/29/2015 01/12/2016 < 0.010 < 0.024 < 0.024 < 0.024 < 0.024 01/12/2016 01/26/2016 < 0.018 < 0.034 < 0.034 < 0.034 < 0.034 01/26/2016 02/09/2016 < 0.027 < 0.027 < 0.027 < 0.027 < 0.011 02/09/2016 02/23/2016 < 0.013 < 0.031 < 0.031 < 0.031 < 0.036 02/23/2016 03/08/2016 < 0.035 < 0.019 < 0.035 < 0.035 < 0.035 03/08/2016 03/22/2016 < 0.025 < 0.010 < 0.025 < 0.025 < 0.025 03/22/2016 04/05/2016 < 0.032 < 0.031 < 0.032 < 0.032 < 0.018 04/05/2016 04/19/2016 < 0.012 < 0.030 < 0.030 < 0.029 < 0.029 04/19/2016 05/03/2016 < 0.019 < 0.019 < 0.019 < 0.019 < 0.007 05/03/2016 05/17/2016 < 0.009 < 0.024 < 0.024 < 0.024 < 0.024 05/17/2016 05/31/2016 <0.035 < 0.035 < 0.015 < 0.035 < 0.035 05/31/2016 06/14/2016 < 0.045 < 0.019 < 0.045 < 0.045 < 0.045 06/14/2016 06/28/2016 < 0.050 < 0.027 < 0.050 < 0.050 < 0.049 06/28/2016 07/12/2016 < 0.037 <0.036 < 0.020 < 0.037 < 0.037 07/12/2016 07/26/2016 < 0.012 < 0.023 < 0.023 < 0.023 < 0.022 07/26/2016 08/09/2016 < 0.022 < 0.022 < 0.022 < 0.012 < 0.022 08/09/2016 08/23/2016 < 0.022 < 0.008 < 0.022 < 0.022 < 0.022 08/23/2016 09/06/2016 < 0.033 < 0.033 < 0.033 < 0.033 < 0.014 09/06/2016 09/20/2016 < 0.047 < 0.047 < 0.020 < 0.047 < 0.047 09/20/2016 10/04/2016 < 0.026 < 0.026 < 0.070 < 0.026 < 0.010 10/04/2016 10/18/2016 < 0.017 < 0.032 < 0.032 < 0.032 < 0.032 10/18/2016 11/01/2016 < 0.060 < 0.032 < 0.060 < 0.059 < 0.059 11/01/2016 11/15/2016 < 0.029 < 0.029 < 0.029 < 0.029 < 0.011 11/15/2016 11/29/2016 < 0.047 < 0.021 < 0.016 < 0.040 < 0.040 11/29/2016 12/13/2016 < 0.035 < 0.035 < 0.035 < 0.034 < 0.014 12/13/2016 12/22/2016 < 0.038 < 0.038 < 0.038 < 7.99* < 0.038 12/22/2016 01/03/2017 < 0.051 < 0.051 < 0.026 < 0.050 < 0.050

  • Due to a pump issue at station 6 a volume could not be provided to the lab. This result is in pCi/Total. See Sample Deviations in Summary.

Enclosure to 0CAN101701 Page 31 of 43 Table 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring (Indicators) 1st Qtr 16 2nd Qtr 16 3rd Qtr 16 4th Qtr 16 Annual Mean 16 Station (mrem) (mrem) (mrem) (mrem) (mrem) 1 8.3 8.2 8.9 9.1 8.6 2 7.8 6.9 7.9 10.0 8.1 3 5.5 4.9 4.7 6.8 5.5 4 7.9 7.1 7.3 8.5 7.7

  • 56 9.9 8.7 9.2 10.5 9.6 108 8.2 7.6 8.3 9.4 8.4 109 8.4 8.2 8.6 7.6 8.2 110 7.4 7.4 8.2 9.6 8.1 145 7.8 7.0 8.0 9.8 8.1 146 8.6 7.7 7.7 8.9 8.2 147 6.5 5.8 6.9 8.1 6.8 148 7.0 8.0 7.1 9.3 7.9 149 Lost 7.0 7.4 9.1 7.8 150 7.2 Lost 8.6 9.5 8.4 151 9.3 8.6 9.2 9.7 9.0 152 6.5 6.3 5.7 7.8 6.5
  • Station with highest annual mean.

Enclosure to 0CAN101701 Page 32 of 43 Table 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - (Population Centers & Schools)

Station 1st Qtr 16 2nd Qtr 16 3rd Qtr 16 4th Qtr 16 Annual Mean 16 (mrem) (mrem) (mrem) (mrem) (mrem) 6 7.2 6.0 6.2 7.8 6.8 111 5.5 4.8 4.8 6.0 5.3

  • 116 9.5 8.0 8.2 9.7 8.9 125 5.2 4.6 4.7 5.7 5.0 127 7.6 6.6 6.8 Lost 7.0 137 9.2 7.8 8.4 9.4 8.7 153 7.0 6.9 7.6 7.4 7.2
  • Stations with highest annual mean.

Special Interest Areas - (Control)

Station 1st Qtr 16 2nd Qtr 16 3rd Qtr 16 4th Qtr 16 Annual Mean 16 (mrem) (mrem) (mrem) (mrem) (mrem) 7 6.6 5.4 6.0 7.8 6.5

Enclosure to 0CAN101701 Page 33 of 43 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) 12/31/2015 01/31/2016 < 1.55 < 1.75 < 3.90 < 1.63 < 3.28 < 1.90 < 3.24 < 10.3 < 1.49 < 1.74 < 16.9 < 5.23 Station 10 (Control) 12/31/2015 01/31/2016 < 1.97 < 1.90 < 3.92 < 2.06 < 4.07 < 1.80 < 3.47 < 2.78 < 1.73 < 2.02 < 8.38 < 2.85 Station 8 (Indicator) 01/31/2016 02/29/2016 < 3.05 < 3.16 < 6.78 < 2.90 < 6.60 < 3.68 < 5.75 < 11.9 < 2.76 < 3.06 < 23.2 < 6.48 Station 10 (Control) 01/31/2016 02/29/2016 < 5.95 < 5.90 < 1.28 < 6.20 < 14.0 < 5.63 < 9.70 < 7.73 < 5.49 < 6.91 < 25.2 < 6.99 Station 8 (Indicator) 02/29/2016 03/31/2016 < 1.86 < 1.84 < 4.80 < 1.83 < 3.55 < 2.05 < 3.35 < 10.5 < 1.63 < 1.67 < 17.4 < 6.71 Station 10 (Control) 02/29/2016 03/31/2016 < 8.29 < 7.46 < 17.5 < 8.31 < 15.4 < 5.88 < 14.2 < 14.0 < 6.09 < 7.85 < 39.1 < 9.95 Station 8 (Indicator) 03/31/2016 04/30/2016 < 1.26 < 1.47 < 3.18 < 1.50 < 2.78 < 1.63 < 2.68 < 6.94 < 1.26 < 1.42 < 12.8 < 3.77 Station 10 (Control) 03/31/2016 04/30/2016 < 4.91 < 4.73 < 10.1 < 3.79 < 8.60 < 4.56 < 9.18 < 6.94 < 4.34 < 5.47 < 22.1 < 6.38 Station 8 (Indicator) 04/30/2016 05/31/2016 < 1.83 < 1.98 < 4.52 < 1.70 < 3.34 < 2.01 < 3.88 < 14.3 < 1.68 < 1.86 < 21.7 < 6.93 Station 10 (Control) 04/30/2016 05/31/2016 < 6.16 < 6.02 < 10.9 < 8.32 < 18.0 < 7.52 < 14.0 < 12.6 < 6.43 < 6.28 < 33.6 < 11.0 Station 8 (Indicator) 05/31/2016 06/30/2016 < 1.25 < 1.42 < 3.14 < 1.23 < 2.44 < 1.74 < 2.65 < 14.1 < 1.20 < 1.38 < 19.3 < 4.43 Station 10 (Control) 05/31/2016 06/30/2016 < 5.64 < 5.39 < 11.4 < 4.85 < 11.2 < 6.15 < 8.72 < 13.6 < 5.08 < 5.33 < 25.7 < 11.9 Station 8 (Indicator) 06/30/2016 07/31/2016 < 2.50 < 2.80 < 6.35 < 2.30 < 5.31 < 2.82 < 4.78 < 14.4 < 2.53 < 2.51 < 25.0 < 8.45 Station 10 (Control) 06/30/2016 07/31/2016 < 7.50 < 7.95 < 16.7 < 6.56 < 16.1 < 8.10 < 13.6 < 8.53 < 5.24 < 6.40 < 35.0 < 10.8 Station 8 (Indicator) 07/31/2016 08/31/2016 < 1.41 < 1.78 < 3.86 < 1.52 < 3.05 < 1.81 < 3.21 < 14.9 < 1.37 < 1.55 < 22.9 < 6.92 Station 10 (Control) 07/31/2016 08/31/2016 < 1.86 < 1.95 < 4.41 < 1.79 < 3.55 < 2.00 < 3.37 < 5.52 < 1.74 < 1.91 < 12.0 < 3.85 Station 8 (Indicator) 08/31/2016 09/30/2016 < 1.67 < 1.84 < 4.13 < 1.61 < 3.20 < 2.03 < 3.30 < 9.68 < 1.47 < 1.62 < 17.3 < 5.52 Station 10 (Control) 08/31/2016 09/30/2016 < 5.04 < 5.10 < 11.0 < 5.37 < 12.1 < 6.73 < 9.27 < 9.51 < 4.76 < 5.78 < 24.4 < 7.81 Station 8 (Indicator) 09/30/2016 10/31/2016 < 1.58 < 1.95 < 4.66 < 1.69 < 3.21 < 2.01 < 3.32 < 14.4 < 1.58 < 1.63 < 22.7 < 6.73 Station 10 (Control) 09/30/2016 10/31/2016 < 9.33 < 8.19 < 14.3 < 7.70 < 15.9 < 8.91 < 11.8 < 9.74 < 7.54 < 9.32 < 32.3 < 12.6 Station 8 (Indicator) 10/31/2016 11/30/2016 < 1.93 < 2.21 < 4.79 < 1.89 < 3.90 < 2.41 < 4.04 < 11.1 < 1.88 < 1.93 < 19.5 < 6.85 Station 10 (Control) 10/31/2016 11/30/2016 < 6.76 < 6.50 < 10.3 < 7.55 < 12.2 < 5.62 < 10.7 < 9.23 < 5.28 < 5.99 < 21.4 < 8.37 Station 8 (Indicator) 11/30/2016 12/31/2016 < 1.66 < 1.68 < 4.05 < 1.58 < 3.49 < 2.07 < 3.21 < 9.00 < 1.55 < 1.67 < 1.59 < 5.31 Station 10 (Control) 11/30/2016 12/31/2016 < 6.82 < 7.27 < 11.1 < 7.79 < 13.0 < 7.50 < 12.4 < 9.94 < 5.20 < 7.03 < 27.5 < 8.58

Enclosure to 0CAN101701 Page 34 of 43 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) 01/04/2016 03/31/2016 354 Station 10 (Control) 01/31/2016 03/31/2016 < 326 Station 8 (Indicator) 03/31/2016 06/30/2016 771 Station 10 (Control) 03/31/2016 06/30/2016 < 399 Station 8 (Indicator) 06/30/2016 09/30/2016 654 Station 10 (Control) 06/30/2016 09/30/2016 < 396 Station 8 (Indicator) 09/30/2016 12/31/2016 1760 Station 10 (Control) 09/30/2016 12/31/2016 < 321

Enclosure to 0CAN101701 Page 35 of 43 Table 4.1 Sample Type: Drinking Water Analysis: Gross Beta, Iodine-131, Gamma Isotopic Units: pCi/l Collection Gross Location I-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Date Beta Required LLD 4.0 1.0 15 15 30 15 30 15 30 15 18 60 15 Station 14 (Indicator) 01/12/2016 < 2.79 < 0.271 < 7.59 < 6.46 < 15.6 < 7.48 < 15.6 < 6.59 < 9.87 < 7.86 < 8.01 < 44.9 < 13.7 Station 57 (Control) 01/12/2016 < 1.65 < 0.260 < 7.10 < 6.66 < 14.5 < 9.16 < 12.7 < 6.48 < 14.8 < 6.21 < 7.82 < 28.7 < 15.0 Station 14 (Indicator) 03/29/2016 < 1.61 < 0.588 < 7.15 < 7.22 < 20.0 < 6.61 < 11.8 < 9.35 < 10.3 < 8.89 < 7.68 < 36.9 < 5.90 Station 57 (Control) 03/29/2016 < 1.51 < 0.437 < 7.67 < 8.62 < 13.5 < 6.80 < 16.3 < 9.76 < 11.7 < 7.53 < 8.15 < 35.8 < 11.5 Station 14 (Indicator) 06/28/2016 < 1.47 < 0.697 < 7.78 < 5.97 < 12.8 < 7.88 < 16.8 < 8.27 < 11.5 < 6.72 < 8.94 < 33.1 < 13.7 Station 57 (Control) 06/28/2016 < 2.31 < 0.603 < 5.34 < 12.1 < 24.2 < 4.25 < 18.2 < 8.22 < 14.4 < 8.97 < 6.76 < 28.9 < 14.9 Station 14 (Indicator) 09/20/2016 < 1.82 < 0.722 < 8.38 < 8.12 < 17.5 < 8.43 < 17.4 < 10.1 < 13.2 < 7.65 < 8.78 < 36.7 < 13.1 Station 57 (Control) 09/20/2016 < 1.88 < 0.502 < 4.99 < 4.83 < 14.4 < 6.10 < 12.6 < 7.92 < 7.71 < 5.93 < 6.86 < 33.6 < 7.56

Enclosure to 0CAN101701 Page 36 of 43 Table 4.2 Sample Type: Drinking Water Analysis: Tritium Units: pCi/l Location Collection Date H-3 Required LLD 2000 Station 14 (Indicator) 01/12/2016 < 393 Station 57 (Control) 01/12/2016 < 397 Station 14 (Indicator) 03/29/2016 < 358 Station 57 (Control) 03/29/2016 < 356 Station 14 (Indicator) 06/28/2016 < 356 Station 57 (Control) 06/28/2016 < 351 Station 14 (Indicator) 09/20/2016 < 305 Station 57 (Control) 09/20/2016 < 307 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) 9/27/2016 < 64.90 < 83.90 Station 16 (Control)* 9/27/2016 < 71.30 < 74.10

Enclosure to 0CAN101701 Page 37 of 43 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) 9/14/2016 < 49.20 < 39.60 < 135.0 < 42.90 < 118.0 < 41.70 < 39.40 Station 16 (Control) 9/14/2016 < 58.30 < 60.00 < 140.0 < 66.90 < 145.0 < 53.60 < 52.70 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) 06/28/2016 < 53.00 < 26.40 < 25.10 Station 55 (Control) 06/28/2016 < 55.10 < 25.50 < 32.80 Station 13 (Indicator) 07/12/2016 < 33.10 < 28.00 < 28.90 Station 55 (Control) 07/12/2016 < 46.20 < 35.30 < 31.60 Station 13 (Indicator) 08/23/2016 < 54.60 < 46.70 < 55.90 Station 55 (Control) 08/23/2016 < 53.40 < 48.90 < 49.10

Enclosure to 0CAN101701 Page 38 of 43 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* 03/17/2016 < 2.37 < 4.29 < 3.74 < 8.12 < 3.32 < 9.51 < 5.03 < 6.99 < 10.50 < 3.88 < 5.10 < 24.00 < 7.53 62* 03/16/2016 < 3.48 < 2.92 < 2.93 < 6.97 < 3.11 < 7.70 < 3.21 < 6.04 < 7.21 < 3.20 < 3.57 < 17.10 < 4.97 63 03/17/2016 4.32 < 3.77 < 4.40 < 7.88 < 3.90 < 8.17 < 3.68 < 7.62 < 8.83 < 3.59 < 4.46 < 21.80 < 7.45 64 03/16/2016 < 2.66 < 4.04 < 3.82 < 9.07 < 3.82 < 9.18 < 4.88 < 8.12 < 9.23 < 4.15 < 4.58 < 22.80 < 7.66 58* 06/01/2016 < 2.21 < 5.88 < 7.41 < 16.30 < 8.70 < 13.60 < 8.12 <15.90 < 12.30 < 6.39 < 8.01 < 34.30 < 10.70 62* 06/01/2016 < 3.06 < 4.79 < 6.32 < 10.90 < 7.04 < 13.90 < 7.69 < 12.30 < 10.90 < 7.07 < 6.11 < 36.30 < 9.53 63 06/01/2016 < 3.19 < 6.19 < 5.97 < 11.90 < 6.08 < 9.51 < 8.51 < 12.20 < 12.10 < 7.33 < 7.59 < 34.10 < 4.70 64 06/02/2016 2.16 < 3.86 < 3.82 < 7.50 < 3.38 < 9.32 < 4.01 < 4.57 < 11.80 < 3.44 < 1.96 < 23.30 < 4.14 58* 09/13/2016 < 2.18 < 4.18 < 3.74 < 9.67 < 4.03 < 9.05 < 4.84 < 7.18 < 12.60 < 4.12 < 4.18 < 28.50 < 7.98 62* 09/13/2016 < 3.82 < 4.03 < 3.89 < 7.20 < 3.92 < 6.60 < 3.52 < 6.85 < 11.40 < 3.69 < 4.41 < 27.00 < 7.14 63 09/13/2016 < 3.95 < 3.76 < 4.02 < 9.58 < 5.19 < 8.16 < 4.48 < 6.81 < 14.80 < 3.87 < 4.53 < 31.30 < 9.65 64 09/14/2016 < 3.29 < 3.95 < 5.05 < 9.71 < 5.12 < 9.46 < 5.68 < 8.42 < 13.20 < 4.45 < 4.88 < 34.40 < 12.10 58* 12/14/2016 < 2.69 < 3.83 < 4.07 < 7.62 < 3.65 < 8.36 < 5.38 < 7.62 < 7.45 < 3.59 < 4.20 < 19.70 < 6.24 62* 12/14/2016 < 2.63 < 3.82 < 3.98 < 9.47 < 4.85 < 9.29 < 4.05 < 6.93 < 7.12 < 3.85 < 3.76 < 18.90 < 7.10 63 12/14/2016 3.87 < 4.28 < 4.53 < 9.83 < 4.04 < 9.37 < 5.00 < 9.16 < 8.25 < 4.23 < 4.65 < 23.10 < 6.86 64 12/15/2016 < 3.28 < 4.24 < 4.55 < 9.56 < 4.31 < 11.80 6.53 < 9.11 < 7.45 < 4.64 < 5.13 < 21.90 < 6.33

  • Identifies Control Locations

Enclosure to 0CAN101701 Page 39 of 43 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 < 365 Station 62 (Control) 03/17/2016 < 369 Station 63 (Indicator) 03/16/2016 < 374 Station 64 (Indicator) 03/16/2016 < 364 Station 58 (Control) 06/01/2016 < 307 Station 62 (Control) 06/01/2016 < 312 Station 63 (Indicator) 06/01/2016 < 318 Station 64 (Indicator) 06/02/2016 < 298 Station 58 (Control) 09/13/0216 < 316 Station 62 (Control) 09/13/0216 < 312 Station 63 (Indicator) 09/13/0216 < 303 Station 64 (Indicator) 09/14/2016 < 312 Station 58 (Control) 12/14/2016 < 278 Station 62 (Control) 12/14/2016 < 285 Station 63 (Indicator) 12/14/2016 < 285 Station 64 (Indicator) 12/15/2016 < 285

Enclosure to 0CAN101701 Page 40 of 43 ATTACHMENT 2 INTERLABORATORY COMPARISON PROGRAM

Enclosure to 0CAN101701 Page 41 of 43 Interlaboratory Comparison Report provided by Teledyne Brown Engineering For the Teledyne Brown Engineering (TBE) laboratory, 156 out of 160 analyses performed met the specified acceptance criteria. Four analyses (Milk - Sr-90, Vegetation - Sr-90, and Water -

H-3 samples) did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program.

Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

1. Teledyne Brown Engineerings MAPEP March 2016 air particulate cross check sample is now being provided to TBE by Analytics. MAPEPs policy is to evaluate as failed non-reported nuclides that were reported in the previous study. Non-Conformance Report (NCR) 16-14 1a. Since the Sr-90 was reported in the previous MAPEP study but not in this study, MAPEP evaluated the Sr-90 for Soil as failed. NCR 16-14 1b. The MAPEP March 2016 Sr-90 in vegetation was evaluated as failing a false positive test. In reviewing the data that was reported vs. the data in LIMS (TBEs work management database), it was found that the error was incorrectly reported as 0.023 rather than the correct value of 0.230. If the value had been reported with the activity with the correct uncertainty of 0.301 +/- 0.230, MAPEP would have evaluated the result as acceptable. NCR 16-14
2. Teledyne Brown Engineerings Analytics March 2016 milk Sr-90 result of 15 +/- 0.125 pCi/L was higher than the known value of 11.4 pCi/L with a ratio of 1.32. The upper ratio of 1.30 (acceptable with warning) was exceeded. After an extensive review of the data it is believed the technician did not rinse the filtering apparatus properly and some cross contamination from one of the internal laboratory spike samples may have been transferred to the analytics sample. We feel the issue is specific to the March 2016 Analytics sample.

NCR 16-26

3. Teledyne Brown Engineerings Environmental Resource Associates (ERA) November 2016 sample for H-3 in water was evaluated as failing. A result of 918 pCi/L was reported incorrectly due to a data entry issue. If the correct value of 9180 had been reported, ERA would have evaluated the result as acceptable. NCR 16-34
4. Teledyne Brown Engineerings Analytics December 2016 milk Sr-90 sample result of 14.7 +/- .26 pCi/L was higher than the known value of 10 pCi/L with a ratio of 1.47. The upper ratio of 1.30 (acceptable with warning) was exceeded. The technician entered the wrong aliquot into the LIMS system. To achieve a lower error term, TBE uses a larger aliquot of 1.2 L (normally we use .6 L for client samples). If the technician had entered an aliquot of 1.2 L into the LIMS system, the result would have been 12.2 pCi/L, which would have been considered acceptable. NCR 16-35

Enclosure to 0CAN101701 Page 42 of 43 ATTACHMENT 3 SEDIMENT DOSE CALCULATIONS

Enclosure to 0CAN101701 Page 43 of 43 Sediment Sample Results Sediment samples were collected from two locations in 2016 and analyzed for gamma radionuclides. Although Cesium-137 has been detected in previous years prior to 2016, all gamma radionuclides from 2016 samples were below detectable limits. These results are consistent with 2015 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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