GNRO-2017/00029, Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report

ML17117A685
Person / Time
Site:	Grand Gulf
Issue date:	04/27/2017
From:	Nadeau J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2017/00029
Download: ML17117A685 (86)

Text

~Entergy Entergy Operations, Inc.

P.o. Box 756 Port Gibson, MS 39150 James Nadeau Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103 GNRO-2017/00029 April 27, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Grand Gulf Nuclear Station Annual Radiological Environmental Operating Report (AREOR)

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

Dear Sir or Madam:

In accordance with the Grand Gulf Nuclear Station (GGNS) Unit 1 Technical Specification 5.6.2, attached is the Annual Radiological Environmental Operating Report (AREOR) for the time period of January 1, 2016 through December 31, 2016.

There are no new commitments contained in this submittal. If you have any questions or require any additional information, please contact Richard Sumrall at 601-437-2115.

JJN/sas

Attachment:

Grand Gulf Nuclear Station 2016 Annual Radioactive Release Report (AREOR) cc: (see next page)

GNRO-2017/00029 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission

_ATTN: Mr. Siva Lingham Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss M. Kennedy (w/2)

Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith (w/2)

Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150

Attachment to GNRO-2017/00029 Grand Gulf Nuclear Station 2016 Annual Radiological Environmental Operating Report (AREOR)

ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2016 - December 31, 2016

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TABLE OF CONTENTS

SUMMARY

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1.0 INTRODUCTION

10 1.1 Radiological Environmental Monitoring Program 10 1.2 Pathways Monitored 10 1.3 Land Use Census 10 2.0 INTERPRETATION AND TRENDS OF RESULTS 23 2.1 Air Particulate and Radioiodine Sample Results 23 2.2 Thermoluminescent Dosimetry (TLD) Sample Results 23 2.3 Water Sample Results 24 2.4 Sediment Sample Results 25 2.5 Milk Sample Results 25 2.6 Fish Sample Results 25 2.7 Food Product Sample Results 25 2.8 Land Use Census Results 25 2.9 Interlaboratory Comparison Results 32 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

33 3.1 Program Results Summary 33 2

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LIST OF TABLES TABLE 1.1 AIR SAMPLING DEVIATIONS IN 2016 8 TABLE 1.2 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM 12 TABLE 2.1 LAND USE CENSUS RESULTS 27 TABLE 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING 34 PROGRAM

SUMMARY

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LIST OF FIGURES FIGURE 1-1 EXPOSURE PATHWAYS 20 FIGURE 1-2 SAMPLE COllECTION SITES - NEAR FIELD 21 FIGURE 1-3 SAMPLE COllECTION SITES - FAR FIELD 22 FIGURE 2-1 TlD READINGS 24 4

LIST OF ATTACHMENTS ATTACHMENT 1 RADIOLOGICAL MONITORING REPORT 40

SUMMARY

OF MONITORING RESULTS 5

Summary The Annual Radiological Environmental Operating Report presents data obtained through analyses of environmental samples collected for Grand Gulf Nuclear Station's (GGNS)

Radiological Environmental Monitoring Program (REMP) for the period January 1, 2016, through December 31, 2016. This report fulfills the requirements of GGNS Technical Specification 5.6.2.

To supplement the REMP, GGNS personnel installed duplicate TLDs and collected duplicate samples during the reporting period.

Radiological Environmental Monitoring Program GGNS established the REMP in 1978 prior to the station becoming operational (1985) to provide data on background radiation and radioactivity normally present in the area. GGNS has continued to monitor the environment by sampling air, water, sediment, fish and food products, as well as measuring radiation directly. GGNS also samples milk, if commercial milk production occurs within five miles of the plant.

The REMP includes sampling indicator and control locations within an 18-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 naturally occurring background radioactivity. GGNS personnel compare indicator results with control and preoperational results to assess any impact GGNS operation might have on the surrounding environment.

In 2016, GGNS personnel collected environmental samples for radiological analysis. The monitoring results for indicator locations when compared to control locations and previous studies show that GGNS has no significant effect on the local environment. The review of 2016 monitoring data, in many cases, showed undetectable radiation levels in the environment and near background levels in potential exposure pathways associated with GGNS.

Harmful Effects or Irreversible Damage The REMP monitoring did not detect any harmful effects or evidence of irreversible damage in the current year.

Reporting Levels When averaged over any calendar quarter, no environmental samples equaled or exceeded reporting levels for radioactivity as outlined in Offsite Dose Calculation Manual (ODCM)

Specifications Table 6.12.1-2; the analytical results did not trigger any Radiological Monitoring Program Special Reports.

Radioactivitv Not Attributable to GGNS Over previous years, the GGNS REMP detected radioactivity attributable to other sources.

These sources included the Chinese nuclear test in 1980 and the accident at the Chernobyl Nuclear Power Plant in 1986. In 2011, the GGNS REMP detected radioactivity released from the Fukushima Dai-ichi Nuclear Power Plant following the March 11,2011, Tohoku earthquake. In 2016, the GGNS REMP detected no radioactivity attributable to other sources.

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Comparison to Federal and State Programs GGNS personnel compare REMP data to federal and state monitoring programs. Historically, the programs used for comparison included the U.S. Nuclear Regulatory Commission (NRC)

Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network and the Mississippi State Department of Health (MSDH), Division of Radiological Health monitoring program.

Although the NRC TLD Network Program was discontinued in 1998, these results compared favorably to those from the GGNS REMP.

The MSDH and the GGNS REMP have similar monitoring requirements. These programs include co-located air sampling and sharing sample media such as water, sediment, fish and food products. Both programs have obtained similar results. The 2016 results of the MSDH monitoring program compared favorably with the GGNS REMP results.

Sample Deviations

• Milk The GGNS aDCM requires collection of milk samples if there is a commercially available source within 5 miles (8 km) of the plant. In 2016*, the REMP did not include milk sampling because no commercial milk production occurred within 5 miles of GGNS. GGNS personnel instead collected vegetation samples to monitor the ingestion pathway, as specified in aDCM Specifications Table 6.12.1-1.

• Required Lower Limit of Detection (LLD) Values Analytical lower limit of detection (LLD) values required by the aDCM specifications achieved in 2016 were within the limits for all samples with the following exception:

Sample Type Location I Analysis Nuclides Date Air Particulate AS-3 VA 11-131 & Gross Beta lodine-131 05/10/16 - 05/17/17 Gross Beta Cause was attributed to unavoidable small sample size due to failure of the sampling equipment. All remaining LLDs were achieved and no plant related nuclides were detected in the 2016 samples. As described in aDCM Specification Table 6.12.1-3, footnote (b), LLDs may be unachievable due to unavoidable small sample size and other legitimate reasons.

Air particulate samples are collected weekly at indicator [AS-1 PG, AS-7 UH] and control [AS-3 VA] locations. In addition, a quarterly composite sample for each location is analyzed for gamma isotopic. For all remaining 2016 air particulate samples, LLDs were achieved and no plant related nuclides were detected.

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• Thermoluminescent Dosimeters TLD M-36 (Sector P, Radius 5.0 Miles), was unavailable during 2 nd quarter, 2016, due to the TLD was missing during sample collection. As described in aDCM Specification Table 6.12.1-1, footnote (a), deviations from the required sampling schedule are permitted due to malfunction of sampling equipment and other legitimate reasons.

• Air Samples The following air sample locations had reduced run times due to weather-related power outages or mechanical problems. As described in aDCM Specification Table 6.12.1-1, footnote (a), deviations from the required sampling schedule are permitted due to malfunction of sampling equipment and other legitimate reasons.

Table 1.1 Air Sampling Deviations in 2016 Run Time Out-of-Service Sample Location Date In Date Out (Hours) (Hours) Comments AS-7 UH 03/08/2016 03/15/2016 165.02 3.69 Power outage AS-7 UH 03/29/2016 04/05/2016 158.75 9.16 Power outaue AS-7 UH 04/12/2016 04/19/2016 165.90 1.86 Power outage AS-7 UH 04/19/2016 04/26/2016 167.98 0.82 Power outaoe AS-361VA 05/10/2016 05/17/2016 16.30 157.41 Equipment Failure AS-20 GR 07/1212016 07/19/2016 159.70 7.83 Power outage AS-7 UH 08/09/2016 08/16/2016 163.18 5.03,- Power outaoe AS-20 GR 08/09/2016 08/16/2016 162.37 5.84 Power outage AS-20 GR 09/13/2016 09/20/2016 90.42 77.68 Equipment Failure AS-7 UH 09/20/2016 09/27/2016 162.67 4.91 Power outage AS-20 GR 09/20/2016 09/27/2016 167.17 0.49 Power outage AS-20 GR 10/11/2016 10/18/2016 128.72 36.41 Equipment Failure AS-7 UH 10/18/2016 10/25/2016 166.95 3.03 Power outage AS-20 GR 10/18/2016 10/25/2016 166.55 3.10 Power outage AS-20 GR 11/08/2016 11/15/2016 167.21 0.74 Power outage AS-7 UH 11/15/2016 11/2212016 165.72 1.66 Power outage AS-20 GR 11/15/2016 11/22/2016 165.72 1.64 Power outage AS-7 UH 11/2212016 11/29/2016 160.38 7.92 Power outage AS-20 GR 11/2212016 11/29/2016 166.46 1.87 Power outage AS-7 UH 11/29/2016 12/06/2016 168.62 0.63 Power outage AS-20 GR 11/29/2016 12/06/2016 168.99 0.24 Power outace AS-20 GR 12106/2016 12113/2016 160.86 7.79 Power outage AS-7 UH 12127/2016 01/03/2017 162.00 5.61 Power outage Sample location AS-20 GR was placed in service on 06/14/16. Based on the sample collection period reductions, air samples were collected the following percentages of the available time:

AS-1 PG 100.0%

AS-361VA 98.2%

AS-7 UH 99.5%

AS-20 GR 97.0%

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• Missed Samples All required samples were collected in accordance with REMP requirements. There were no missed samples.

• Unavailable Results GGNS received analytical results in adequate time for inclusion in this report.

Program Modifications During 2016, one additional air monitoring station was installed in the vicinity of the nearest community located within Sector L. Meteorological data indicates that Sector L has the highest calculated X/Q at the site boundary. The new air sampling location was placed in service on 06/14/16. The additional monitoring location will enhance the site's radiological environmental monitoring program, and will demonstrate robust compliance with the Offsite Dose Calculation Manual requirements. Laboratory analytical data indicates 1-131 and Gross Beta activity levels are similar for samples collected from AS-20 and the existing control location AS-3.

Attachments contains results of TLD, air, water, sediment, fish, food products and special samples collected in the reporting period. TLDs were analyzed by Stanford Dosimetry of Sterling, MA. Other samples were analyzed by Teledyne Brown Engineering of Knoxville, TN.

Tables A 9.1 and A 9.2 includes results from Stanford Dosimetry's and Teledyne Brown Engineering's participation in interlaboratory comparison programs.

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1.0 Introduction 1.1 Radiological Environmental Monitoring Program GGNS established the REMP to ensure that plant operating controls properly function to minimize any radiation that could endanger human health or the environment. The REMP is designed to:

• Analyze important pathways for anticipated types and quantities of radionuclides released into the environment,

• Consider the possibility of a buildup of long-lived radionuclides in the environment and identify any physical and biological accumulations that may contribute to human exposures,

• Consider the potential radiation exposure to plant and animal life in the environment surrounding GGNS,

• Correlate levels of radiation and radioactivity in the environment with radioactive releases from the operation of GGNS.

1.2 Pathways Monitored The airborne, direct radiation, waterborne and ingestion pathways, as seen in Figure 1-1 are monitored as required by the GGNS aDCM Table 6.12.1-1. A description of the GGNS REMP utilized to monitor the exposure pathways is provided in Table 1.2 and shown in Figures 1-2 and 1-3. GGNS may supplement this program with additional sampling in order to provide a comprehensive and well-balanced program.

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

1.3 Land Use Census GGNS personnel conduct a biennial land use census, as required by aDCM Specification 6.12.2. The most recent land use census data are included in Table 2.1. The purpose of this census is to identify land use changes within each of the 16 meteorological sectors and within a 5-mile radius of GGNS that would require modifications to the REMP or the aDCM.

GGNS personnel conduct the land use census by:

• Conducting field surveys.

• Identifying locations on maps and aerial photographs and measuring distances to GGNS

• Comparing current land use census results to results from the previous census

• Contacting the Claiborne County Agent for verification of nearest dairy animals 10 2*

No significant changes were identified between the biennial land use census performed in 2014 and the most recent census performed in 2016 that would require modifications to the REMP or the ODeM.

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Table 1.2 Radiological Environmental Sampling Program Exposure Sample Point Description, Sampling and Type and Frequency Pathway Requirement Distance and Direction Collection Frequency Of Analyses Radioiodine and Particulates 1 sample close to the SITE AS-7 UH (Sector H, Radius 0.5 BOUNDARY having the highest Miles) - South-southeast of GGNS calculated annual average at the IBEW Union Hall.

ground level D/Q.

Radioiodine and Particulates 1 sample from the vicinity of a AS-20 GR (Sector l, Radius 0.9 Radioiodine Canister-community having the highest Miles) - Southwest of GGNS on Continuous sampler 1-131; 7 days calculated. annual average Bald Hill Road, at the Former operation with sample Particulate Sampler-Airborne ground level D/Q. Glodjo Residence. collection per 7 days or Gross beta radioactivity as required by dust following filter change, loading, whichever is composite (by location)

Radioiodine and Particulates more frequent for gamma isotopic; 92 1 sample from the vicinity of a AS-1 PG (Sector G, Radius 5.5 Miles) - Southeast of GGNS at the days community having the highest calculated annual average Port Gibson City Bam.

ground level D/Q.

AS-3 61VA (Sector B, Radius 18 Radioiodine and Particulates Miles) - North-northeast of GGNS 1 sample from a control location on Hwy 61, North of the Vicksburg 15 -30 km (10 - 20 miles)

Airport.

distance.

M-16 (Sector A, Radius 0.9 Miles)

TlDs - Meteorological Tower.

An inner ring of stations in the Direct general areas of the SITE M-19 (Sector E, Radius 0.5 Miles)

- Eastern SITE BOUNDARY 92 days Gamma dose; 92 days Radiation BOUNDARY.

Property line, North-northeast of HWSA.

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Table 1.2 Radiological Environmental Sampling Program Exposure Sample Point Description, Sampling and Type and Frequency Pathway Requirement Distance and Direction Collection Frequency Of Analyses M-21 (Sector J, Radius 0.4 Miles) -~,_

Near Former Training Center Building on Bald Hill Road.

M-22 (Sector G, Radius 0.5 Miles) -

Former RR Entrance Crossing On Bald Hill Road.

TLDs M-23 (Sector Q, Radius 0.5 Miles)-

An inner ring of stations in the Direct Gin Lake Road 50 Yards North of general areas of the SITE 92 days Gamma dose; 92 days Radiation Heavy Haul Road on Power Pole.

BOUNDARY.

M-25 (Sector N, Radius 1.6 Mfles) -

Radial Well Number 1.

M-28 (Sector L, Radius 0.9 Miles) -

Bald Hill Road.

M-94 (Sector R, Radius 0.8 Miles)-

Sector R Near Meteorological Tower.

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Table 1.2 Radiological Environmental Sampling Program Sampling and Exposure Sample Point Description, Collection Type and Frequency Pathway Requirement Distance and Direction Frequency Of Analvses M-95 (Sector F, Radius 0.5 mil - Spoils Area, fence of old storage area, near entrance gate M-96 (Sector S, Radius 0.7 mi.) - North Gate Fence TlOs M-97 (Sector 0, Radius 0.8 mi.) - Grand An inner ring of stations in the Gulf Road entrance gate to spoils area Direct 92 days Gamma dose; 92 days general areas of the SITE M-98 (Sector H, Radius 0.5 mi.) - Ba1d Radiation BOUNDARY. Hill Road, across from Union Hall, in curve M-99 (Sector K, Radius 0.4 mi.) - North Fence of old Ball Field near utility pole M-100 (Sector C, Radius 0.6 mi.)-

Grand Gulf Road TlOs M-36 (Sector P, Radius 5.0 Miles) -

Curve on HW 608. Point Nearest GGNS An outer ring approximately 3 to at Power Pole.

5 miles from the site.

M-40 (Sector M, Radius 2.3 Miles)-

Headly Drive. Near River Port Entrance.

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i Table 1.2 Radiological Environmental Sampling Program Exposure Sample Point Description, Sampling and Type and Frequency Pathway Requirement Distance and Direction Collection Frequency Of Analyses TLDs M-48 (Sector K, Radius 4.8 Miles)-

0.4 Miles South on Mont Gomer Road An outer ring approximately 3 on West Side.

to 5 miles from the site.

M-49 (Sector H, Radius 4.5 Miles) -

Fork in Bessie Weathers Road/Shaifer Road.

M-50 (Sector B, Radius 5.3 Miles)-

Panola Hunting Club Entrance.

M-55 (Sector 0, Radius 5.0 Miles)-

Near Ingelside Kamac Ferry Road/Ashland Road Intersection.

M-57 (Sector F, Radius 4.5 Miles)-

Direct Hwy 61 , Behind the Welcome to Port Radiation Gibson Sign at Glensdale Subdivision. 92 days Gamma dose; 92 days TLDs M-01 (Sector E, Radius 3.5 Miles)-

Across the road from Lake Claibome 8 stations in special interest Entry Gate. (Special Interest) areas such as population centers, nearby residences, M-07 (Sector G, Radius 5.5 Miles) -

schools, and in 1 or 2 areas to AS-1 PG. Port Gibson City Bam.

serve as control stations. (Special Interest)

M-09 (Sector 0, Radius 3.5 Miles) -

Warner Tully V-Camp. (Special Interest)

M-10 (Sector A, Radius 1.5 Miles)-

Grand Gulf Military Park. (Special Interest) 15

Table 1.2 Radiological Environmental Sampling Program Exposure Sample Point Description, Sampling and Type and Frequency Pathway Requirement Distance and Direction Collection Frequency Of Analyses M-14 (Sector B, Radius 18.0 Miles)

- AS-3-61 VA, Hwy 61, North of Vicksburg Airport. (Control)

M-33 (Sector P, Radius 12.5 Miles)

TLDs - Newellton, Louisiana Water Tower.

8 stations in special interest (Special Interest)

Direct areas such as population M-38 (Sector M, Radius 9.5 Miles)- 92 days Gamma dose; 92 days Radiation centers, nearby residences, Lake Bruin State Park, Entrance schools, and in 1 or 2 areas to Road. (Special Interest) serve as control stations M-39 (Sector M, Radius 13.0 Miles)

- S1. Joseph, Louisiana, Auxiliary Water Tank. (Special Interest) 16

Table 1.2 Radiological Environmental Sampling Program Sampling and Exposure Sample Point Description, Collection Type and Frequency Pathway Requirement Distance and Direction frequency Of Analyses Surface Water MRUP (Sector R, Radius 1.8 Miles) - At 92 days Gamma isotopic and least 4500 ft upstream of the GGNS tritium analyses; 92 1 sample upstream.

discharge point into the Mississippi River to days 1 sample downstream. allow adequate mixing of the Mississippi and Big Black Rivers.

MRDOWN (Sector -N, Radiusf B Miles) -

At least 5000 ft downstream of the GGNS discharge point in the Mississippi River near Radial Well NO.1.

Waterborne MRDOWN (Sector P, Radius 1.3 Miles)- 366 days Gamma isotopic and 1 sample downstream during a Downstream of the GGNS discharge point tritium analyses; 366 Liquid Radwaste Discharge. in the Mississippi River near Radial Well No. days 1 sample from Outfall 007 5.

OUTfALL 007 (Sector N, Radius 0.2 31 days Tritium; 31 days Miles) - Storm Drain System 17

Table 1.2 Radiological Environmental Sampling Program Exposure Sample Point Description, Sampling and Type and Frequency Pathway Requirement Distance and Direction Collection Frequency Of Analyses PGWELL (Sector G, Radius 5.0 Miles) - Port Gibson Wells - Taken from distribution system or one of Groundwater the five wells.

Gamma isotopic and Samples from 2 sources. CONSTWELL (Sector Q, Radius 366 days tritium analyses; 366 days 0.4 Miles) - GGNS Construction Water Well- Taken from distribution system or the wel/.

Waterborne SEDHAM (Sector N, Radius 1.6 Sediment From Shoreline Miles) - Downstream of the GGNS 1 sample from downstream discharqe point in the Mississippi area. River near Hamilton Lake outlet.

366 days Gamma isotopic; 366 days 1 sample from upstream area. SEDCONT (Minimum of 100 yds) -

Upstream of the GGNS discharge point in the Mississippi River.

Milk 1 sample from milking animals within 8 km (5 miles) if milk is available commercial/y. Currently, no available milking Gamma isotopic and 1-Ingestion 92 days when required animals within 8 km of GGNS. 131; 92 days 1 control sample (only if indicator exists) >8 km if milk is available.

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Table 1.2 Radiological Environmental Sampling Program Exposure Sample Point Description, Sampling and Type and Frequency Pathway Requirement Distance and Direction Collection Frequency Of Analyses FISHDOWN - Downstream of the Fish GGNS discharge point into the 1 sample in vicinity of GGNS Mississippi River discharge point. FISHUP - Upstream of the GGNS Gamma isotopic on edible 366 days 1 sample uninfluenced by discharge point into the Mississippi portion; 366 days GGNS discharge. River uninfluenced by plant operations.

Food Products _c Ingestion 1 sample of broad leaf VEG-J (Sector J, Radius 0.4 Miles) vegetation grown in one of two - South of GGNS near former different offsite locations with Training Center on Bald Hill Road.

highest anticipated annual VEG-CONT (Sector K, Radius 10.5 Gamma isotopic and 1-average ground level D/Q if 92 days when available Miles) - Alcorn State University 131; 92 days milk sampling is not performed.

south-southwest of GGNS when 1 sample of similar vegetation available, otherwise a location 15-30 grown 15 - 30 km distant if km distant.

milk sampling is not performed.

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2.0 Interpretation and Trends of Results 2.1 Air Particulate and Radioiodine Sample Results GGNS did not detect any plant related gamma emitting radionuclides in the quarterly air particulate composites .

. The REMP had previously detected airborne radioactivity attributable to other sources in this pathway. These sources include the Chinese nuclear test in 1980 and the accident at the Chemobyl Nuclear Power Plant in 1986. The GGNS REMP detected radioactivity released from the Fukushima Dai-ichi Nuclear Power Plant following the March 11, 2011, Tohoku earthquake. No radioiodine was detected in 2016.

Table 3.1, which also includes gross beta activity, provides a comparison of the indicator and control means and ranges, further emphasizing that the airborne pathway remains at background levels. In the absence of plant-related gamma radionuclides, gross beta activity is attributed to naturally occurring radionuclides. Similar trends are present for control and indicator locations, which support the presence of naturally occurring radioactivity.

2.2 Thermoluminescent Dosimetry Sample Results GGNS calculates dose by subtracting shield readings from control and indicator location readings and reports measured dose as net exposure, normalized to 92 days.

GGNS relies on the comparison of the indicator locations to the control location as an indication of plant impact. Gamma radiation dose in the reporting period is compared to control location readings for previous years as shown in Figure 2~ 1.

The comparison of the indicator results to the control, and to previous indicator results, as seen in Figure 2-1 and Table 3.1, indicates that plant operation has had no significant impact on ambient radiation levels during the reporting period.

In previous years, TLD locations M-21 (Sector J, 0.4 miles), M-98 (Sector H, 0.5 miles),

and M-99 (Sector K, 0.4 miles) were above background. The dose rates at these three locations were the result of Nitrogen-16 (N-16) associated with the injection of hydrogen and subsequent N-16 production. Hydrogen injection into the feedwater system provides protection against Intergranular Stress Corrosion of plant components.

Since November 2010, the hydrogen injection rate has been reduced and the dose rates at TLD locations M-21, M-98, and M-99 have returned to near background levels.

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2.3 Water Sample Results Surface water samples were collected from three indicator locations (Outfall 007, MRDOWN, and MRDOWN During Discharge) and one control location (MRUP) and analyzed for gamma emitting radionuclides and tritium. Plant related gamma emitting radionuclides and tritium remained undetectable in the upstream and downstream Mississippi River locations, which is consistent with preoperational and previous operational years. Storm waters contribute to Outfall 007 and can include tritium as a result of washout and entrainment of normal, previously monitored gaseous effluents.

As a result, tritium is occasionally observed. Tritium was measured during January (2100 +/- 537 pCi/L) and August (698 +/- 195 pCi/L) at the Outfall 007 (indicator) location.

Tritium was not observed in the remaining Outfall 007 samples collected during 2016.

In addition to the tritium samples required by the REMP, four special surface water samples for gamma emitting radionuclides were collected at the Outfall 007 location (Table A 8.1). Plant related gamma emitting radionuclides remained undetectable in these samples.

Based on review of results and historical data, plant operations had no significant impact on this pathway during the reporting period.

Groundwater samples were collected from two locations (indicator and control) and analyzed for gamma emitting radionuclides and tritium (Tables A 4.1 and A 4.2). In addition to the samples required by the REMP, an extra sample from the locations was analyzed for lodine-131 (Table A 4.3). GGNS did not detect any plant related gamma emitting radionuclides or tritium in groundwater samples during the reporting period.

24 M"W

Based on review of results and historical data, plant operations had no significant impact on this pathway during the reporting period.

2.4 Sediment Sample Results Sediment samples were collected from two locations (indicator and control) and analyzed for gamma emitting radionuclides. GGNS did not detect any plant related gamma emitting radionuclides in sediment samples during the reporting period.

Based on review of results and historical data, plant operations had no significant impact on this pathway during the reporting period.

2.5 Milk Sample ResuIts Milk samples were not collected within five miles of the site in the reporting period due to the absence of milking animals. Since there are no dairies within five miles of GGNS, and based on non-detectable radioiodine and gamma radionuclides in air and vegetation samples, plant operations had no impact on this pathway during the reporting period.

2.6 Fish Sample Results Fish samples were collected from two locations (indicator and control) and analyzed for gamma emitting radionuclides. GGNS did not detect any plant related gamma emitting radionuclides in fish samples (edible portions) during the reporting period, as has been the case in preoperational and previous operational years. These results indicate that this pathway has not been affected by plant operations.

2.7 Food Product (Vegetation) Sample Results Food product samples were collected from two locations (indicator and control) and analyzed for lodine-131 and gamma emitting radionuclides. GGNS did not detect any plant related lodine-131 or gamma emitting radionuclides in vegetation samples during the reporting period. These results indicate that this pathway has not been affected by plant operations. .

2.8 Land Use Census Results Results from the most recent Land Use Census performed in 2016 are included in this report. Methods utilized to perform the Land Use Census include: visual surveys, door to door surveys, telephone interviews, Global Positioning System (GPS), Aerial Photography, and consultation with the local county agent concerning dairy production in Claiborne County.

During the survey the following information was obtained:

1) nearest location of occupied and unoccupied residences

2) nearest location of dairy production

3) nearest location of gardens 25

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Changes from the previous Land Use Census were evaluated in accordance with GGNS surveillance "Land Use Census", 06-EN-5000-0-0002. The differences were compared to the locations and assumptions used in calculations for compliance with the ODCM Limiting Condition for Operation 6.11.6 and 6.12.2. The locations and assumptions currently used in the ODCM were determined to be more conservative than any of the changes. Determinations from the most recent Land Use Census results are:

• Because of downwind location and/or distance from the site, in no case will the occupancy of an existing unoccupied residence cause any existing ODCM critical receptor calculation results to be less conservative.

• No additional sampling locations are required as the onsite vegetation sampling location (Sector J, 0.4 miles) is more conservative than changes identified in the land use census.

• Cattle are raised for human consumption (most notably in Sectors F, H, J, and K). GGNS uses the Grass/Cow/Meat pathway.

• The milk pathway does not need to be activated because no commercial dairy production is occurring within 5 miles, as referenced by ODCM Table 6.12.1-1.

• Sectors M, N, P, and Q are remote areas in which the primary use is hunting.

Areas were surveyed by vehicle, aerial photographs, and interviews.

• Gardens, regardless of size, were included in the census data 26

Table 2.1 2016 Land Use Census Parameter Sector A* Sector B Sector C* Sector D*

I. Nearest Occupied a. Distance (mile) 1.02 1.51 0.70 2.60 Residence b. Degrees from true north 355.4 23.7 42.3 60.8 II. Nearest Unoccupied a. Distance (mile) 0.94 0.83 None None Residence (closer b. Degrees from true north 8.0 15.1 than occupied residence)

III. Nearest Milk Animal a. Distance None None None None IV. Nearest Broadleaf a. Distance (mile) 1.02 1.52 4.14 4.50 Garden b. Garden size (ft2) ~ 400  :::::4050  ::::: 100  ::::: 2000

c. Degrees from true north 355.4 21.9 47.6 64.8 V. Census Comparison a. Is nearest occupied No Yes Yes Yes residence in same location as last census?

b. Is nearest milk animal in N/A N/A N/A N/A same location as last census?

c. Is nearest broadleaf Yes' Yes' No No garden in same location as last census?

1 Retained previous garden location. Located no other gardens in the sector.

• Change from tast census. See table of Land Use Census Changes 27

Table 2.1 2016 Land Use Census, continued.

Parameter Sector E* Sector F* Sector G Sector H*

I. Nearest Occupied a. Distance (miles) 0.83 2.25 3.72 1.10 Residence b. Degrees from true north 94.5 101.3 134.1 151.4 II. Nearest Unoccupied a. Distance (miles) None None 3.71 1.07 Residence (closer b. Degrees from true north 131.8 151.0 than occupied residence)

III. Nearest Milk Animal a. Distance None None None None IV. Nearest Broadleaf a. Distance (miles) 0.89 4.49 4.20 4.31 Garden b. Garden size (ft2)  ;::: 1000  :::::400  ;::: 1600  ;:::200

c. Degrees from true north 86.9 113.5 130.1 146.6 V. Census Comparison a. Is nearest occupied No Yes Yes Yes residence in same location as last census?

b. Is nearest milk animal in N/A N/A N/A N/A same location as last census?

c. Is nearest broadleaf garden Yes No Yes No in same location as last census?

• - Change from last census. See table of Land Use Census Changes 28

Table 2.1 2016 Land Use Census, continued.

Parameter Sector J Sector K Sector L Sector M I. Nearest Occupied a. Distance (miles) 3.14 2.20 0.89 None Residence b. Degrees from true north 174.2 197.0 219.7 II. Nearest Unoccupied a. Distance (miles) None 1.70 None None Residence (closer than b. Degrees from true north 203.3 occupied residence) (Hunting Lodge-Info Only)

III. Nearest Milk Animal a. Distance (miles) None None None None IV. Nearest Broadleaf a. Distance (miles) 3.16 2.18 0.89 None Garden b. Garden size (ft2) ~ 500 ~ 2500 ~400

c. Degrees from true north 174.0 196.3 219.5 V. Census Comparison a. Is nearest occupied Yes Yes Yes N/A residence in same location as last census?

b. Is nearest milk animal in N/A N/A N/A N/A same location as last census?

c. Is nearest broadleaf Yes Yes Yes N/A garden in same location as last census?

29

Table 2.1 2016 Land Use Census, continued.

Parameter Sector N Sector P Sector Q Sector R*

I. Nearest Occupied a. Distance (miles) None None None 1.44 Residence b. Degrees from true north 348.4 II. Nearest Unoccupied a. Distance (miles) None None None 1.11 Residence (closer b. Degrees from true north 346.1 than occupied residence)

III. Nearest Milk Animal a. Distance (miles) None None None None IV. Nearest Broadleaf a. Distance (miles) None None None None Garden b. Garden size (ft2)

c. Degrees from true north V. Census Comparison a. Is nearest occupied N/A N/A N/A No residence in same location as last census?

b. Is nearest milk animal in N/A N/A N/A N/A same location as last census?

c. Is nearest broadleaf N/A N/A N/A N/A garden in same location as last census?

• - Change from last census. See table of Land Use Census Changes 30

2016 land Use Census Changes SECTOR PARAMETER Reason for Change A Nearest Occupied Residence New nearest occupied residence identified in 2016.

C Nearest Broadleaf Garden New nearest garden location identified in 2016.

Garden location identified in 2014 census no longer active. New D Nearest Broadleaf Garden nearest garden location identified in 2016.

E Nearest Occupied Residence New nearest occupied residence identified in 2016.

F Nearest Broadleaf Garden New nearest garden location identified in 2016.

H Nearest Broadleaf Garden New nearest garden location identified in 2016.

Nearest occupied residence from 2014 census no longer occupied.

R Nearest Occupied Residence New nearest occupied residence identified in 2016.

31

2.9 Interlaboratory Comparison Results Stanford Dosimetry Company analyzed interlaboratory comparison thermoluminescent dosimeters to fulfill the requirements of aDCM Specification 6.12.1. The results are shown in Table A.9.1.

GEL Laboratories analyzed interlaboratory comparison samples to fulfill the requirements of aDCM Specification 6.12.1. The results are shown in Table A.9.2.

32 k$'IO@¥iiA** #B¥Wi -$-¥**46*++iHi%#-'¥§-- ¥ij -- '7'"' ffii&4H¥d- .$$ Pb4##-***,ffi - 49 . ¥ M *"~ *w .,. d -4 '". *P.*EJ(..*:* "JoWit

3.0 Radiological Environmental Monitoring Program Summary 3.1 Program Results Summary Table 3.1 summarizes the REMP results. Values reported as less than the lower limit of detection <<LLD) were not used when determining ranges and means for indicator and control locations.

I 33 ie§?¥¥i§!i4f¥-¥"k -¥¥A -- ih-f,,!,U ... ¥i¥#&¥#*;i¥*bP¥%#: dt§iM-¥ ¥§ ~ .. ,#; -f* &¥§

TABLE 3.1 Radiological Environmental Monitoring Program Summary Name of Facility: Grand Gulf Nuclear Station Docket No: 50-416 Location of Facility: Claiborne County, Mississippi Reporting Period: January - December 2016 Sample Type Type & Number LLD b Indicator Locations Location with Highest Annual Control Number of

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

[ Range] Mean (F) c Results e

[Range]

Mean (F) c Location d [Range]

Air Particulates GB 184 0.01 0.01742 (132/132) AS-20 GR 0.01839 (28/28) 0.01850 (52/52) 0

[0.00505 - 0.03690] (Sector L, 0.9 mi) [0.00674-0.03580] [0.00818-0.03530]

(pCi/m 3 )

GS 15 Cs-134 0.05 <LLD N/A N/A <LLD 0 Cs-137 0.06 <LLD N/A N/A <LLD 0 Airborne Iodine 1-131 156 0.07 <LLD N/A N/A <LLD 0 (pCi/m 3 )

Inner Ring TLDs Gamma 56 f 9.3 (56/56) M-99 11.5 (4/4) NlA 0 (mRlQtr) [2.2 -12.6] (Sector J, 0.4 mi.) [10.2 - 12.5]

Outer Ring TLDs Gamma 27 f 9.3 (27/27) M-57 11.4 ( 4/4) N/A 0 (mRlQtr) [3.5 -13.0] (Sector F, 4.5 mi.) [9.9 -12.5]

Special Interest Gamma 28 f 9.4 (28/28) M-01 11.3 (4/4) N/A 0 TLDs [7.1 - 13.2] (Sector E, 3.5 [9.6 -13.2]

( mRlQtr) mi.)

Control TLDs Gamma 4 f N/A N/A N/A 10.7 (4/4) 0 (mRlQtr) [9.0 -12.3]

34

TABLE 3.1 Radiological Environmental Monitoring Program Summary Name of Facility: Grand Gulf Nuclear Station Docket No: 50-416 location of Facility: Claiborne County, Mississippi Reporting Period: January - December 2016 Sample Type Type & Number LLOb Indicator Location Location with Highest Annual Mean Control Number of

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

[Range] Mean (F) c Results e

[Range]

Mean (F) c Location d [RanQe]

Surface Water H-3 32 3000 1399(2/26) Outfall 007 1399 (2126) <LLD 0

( pCill ) [698 - 2100] (Sector N, Radius 0.2 mi.) [698 - 2100]

GS 14 Mn-54 15 <LLD N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Fe-59 30 <LLD N/A N/A <LLD 0 Co-60 15 <LLD N/A N/A <LLD 0 Zn-65 30 <LLD NJA N/A <LLD 0 Nb-95 15 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 1-131 15 <LLD NJA N/A <LLD 0 Cs-134 15 <LLD N/A N/A <LLD 0 Cs-137 18 <LLD N/A N/A <LLD 0 8a-140 60 <LLD N/A N/A <LLD 0 La-140 15 I <LLD NJA N/A <LLD 0 35

TABLE 3.1 Radiological Environmental Monitoring Program Summary Name of Facility: Grand Gulf Nuclear Station Docket No: 50-416 Location of Facility: Claiborne County, Mississippi Reporting Period: January - December 2016 Sample Type Type & LLOb Indicator Locations Location with Highest Annual Mean Control Number of

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

[Range]

Mean (F) c Location d [Range]

Groundwater H-3 6 2000 <LLD N/A N/A <LLD 0

( pCi/1 )

1-131 3 1 <LLD N/A N/A <LLD 0 GS 3 Mn-54 15 <LLD N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Fe-59 30 <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 Nb-95 15 <LLD N/A N/A <LLD 0 Zr-95 30 <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 8a-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD 0 Sediment GS 4 (pCi/kg) Cs-134 150 <LLD N/A N/A <LLD 0 Cs-137 180 <LLD N/A N/A <LLD 0 36

TABLE 3.1 Radiological Environmental Monitoring Program Summary Name of Facility: Grand Gulf Nuclear Station Docket No: 50-416 Location of Facility: Claiborne County, Mississippi Reporting Period: January - December 2016 Sample Type Type & LLD b Indicator Location Location with Highest Annual Control Number of

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

[Range]

Mean (F) c Location d [Range]

Fish GS 2

( pCi/kg ) Mn-54 130 <LLD N/A N/A <LLD 0 Co-58 130 <LLD N/A N/A <LLD 0 Fe-59 260 <LLD N/A N/A <LLD 0 Co-60 130 <LLD N/A N/A <LLD 0 Zn-65 260 <LLD N/A N/A <LLD 0 Cs-134 130 <LLD N/A N/A <LLD 0 Cs-137 150 <LLD N/A NJA <LLD 0 Food 1-131 8 60 <LLD N/A N/A <LLD 0 ProductsNegetation

( pCi/kg ) GS 8 Cs-134 60 <LLD N/A N/A <LLD a Cs-137 80 <LLD N/A N/A <LLD 0 37

TABLE 3.1 Radiological Environmental Monitoring Program Summary Name of Facility: Grand Gulf Nuclear Station Docket No: 50-416 Location of Facility: Claiborne County. Mississippi Reporting Period: January - December 2016 Sample Type Type & Number LLDb Indicator Location Location with Highest Annual Control Number of

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

[Range] Mean (F) c Results e Mean (F) c [ Range 1 Location d [Range]

Surface Water GS 5 (Special) Mn-54 15 <LLD N/A N/A <LLD 0

( pCi/1 ) Co-58 15 <LLD N/A N/A <LLD 0 Fe-59 30 <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 Nb-95 15 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 1-131 15 <LLD N/A N/A <LLD 0 Cs-134 15 <LLD N/A N/A <LLD 0 Cs-137 18 <LLD N/A N/A <LLD a 8a-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD a Meat GS 2 (Special) Mn-54 130 <LLD N/A N/A <LLD 0

( pCi/kg ) Co-58 130 <LLD N/A N/A <LLD a Fe-59 260 <LLD N/A N/A <LLD a 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 38

= =

a GB Gross beta; 1-131 lodine-131; H-3 Tritium; GS Gamma scan.

=

b LLD Required lower limit of detection based on aDeM Table 6.12.1-3.

c Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis (F).

d Where applicable, locations are specified by name, distance from reactor site and meteorological sector.

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 oocu Table 6.12.1-3.

39

Attachment 1 Radiological Monitoring Report Summary of Monitoring Results 40

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TABLE OF CONTENTS TABLE A1.1 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-1 PG 42 TABLEA1.2 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-3 61VA 44 TABLEA1.3 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-7 UH 46 TABLEA1.4 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-20 GR 48 TABLEA1.5 AIR PARTICULATE FILTER GAMMA 49 TABLEA2.1 THERMOLUMINESCENT DOSIMETERS 50 TABLEA2.2 THERMOLUMINESCENT DOSIMETERS 51 TABLEA2.3 THERMOLUMINESCENT DOSIMETERS 51 TABLEA3.1 SURFACE WATER GAMMA 52 TABLE A3.2 SURFACE WATER TRITIUM 53 TABLEA4.1 GROUNDWATER GAMMA 54 TABLEA4.2 GROUNDWATER TRITIUM 55 TABLE A4.3 GROUNDWATER IODINE-131 56 TABLEA5.1 SEDIMENT 57 TABLEA6.1 FISH 58 TABLEA7.1 FOOD PRODUCTS 59 TABLEA8.1 SPECIAL SAMPLES 60 TABLEA9.1 INTERLABORATORY PROGRAM - TLDS (14 PAGES)

TABLEA9.2 INTERLABORATORY PROGRAMS - SAMPLES (7 PAGES) 41

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Table A1.1 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-1 PG LLD (pCi/m3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L66432-1/4 12129/15 01105/16 <0.04632 0.02550 +/-0.00396 L66463-1/4 01/05/16 01112116 <0.04171 0.01340 +0.00307 L66587-1/4 01/12116 01/19/16 <0.05486 0.03120 +/-0.00440 L66635-1/4 01/19/16 01/26/16 <0.03432 0.01510 +/-0.00326 L66726-1/4 01/26/16 02102116 <0.04757 0.02080 +/-0.00364 L66829-1/4 02/02116 02109/16 <0.04666 0.01240 +/-0.00317 L66915-1/4 02/09/16 02116116 <0.04686 0.01720 +/-0.00335 L66990-1/4 02116/16 02/23/16 <0.02744 0.01290 +/-0.00315 L67081-1/4 02123/16 03/01/16 <0.06706 0.01420 +0.00322 L67163-1/4 03/01/16 03108/16 <0.04461 0.01700 +/-0.00336 L67243-1 14 03/08/16 03/15/16 <0.03015 0.00639 +/-0.00248 L67320-1/4 03/15/16 03/22116 <0.05916 0.01140 +/-0.00313 L67366-1/4 03/22116 03/29/16 <0.05953 0.01290 +/-0.00314 L6748Q-1/4 03/29/16 04/05/16 <0.05518 0.01790 +/-0.00348 L67589-1/4 04/05/16 04/12116 <0.06881 0.01370 +/-0.00305 L67683-1/4 04/12116 04/19/16 <0.04587 0.00975 +/-0.00277 L67804-1/4 04/19/16 04/26/16 <0.04239 0.01200 +/-0.00310 L67933-1/4 04/26/16 05103/16 <0.03376 0.01430 +/-0.00330 L68039-1/4 05103/16 05/10/16 <0.05523 0.01460 +/-0.00322 L68137-1/4 05/10/16 05/17/16 <0.01381 0.01820 +/-0.00325 L68240-1/4 05/17/16 OS/24/16 <0.05851 0.02030 +/-0.00360 L68307-1/4 OS/24/16 05/31/16 <0.06813 0.01500 +/-0.00324 L68396-1/4 05/31/16 06/07/16 <0.06309 0.01170 +/-0.00312 L68496-1/5 06/07/16 06/14/16 <0.04911 0.01270 +/-0.00313 L68572-1/5 06/14/16 06/21/16 <0.03603 0.01800 +/-0.00331 L68711-1/5 06/21/16 06/28/16 <0.04312 0.01610 +/-0.00339 L68749-1/5 06/28/16 07/05/16 <0.06806 0.01770 +/-0.00352 L68844-1/5 07/05/16 07/12116 <0.05053 0.01200 +/-0.00285 L68942-1/5 07/12116 07/19/16 <0.05381 0.01460 +/-0.00317 L69076-1/5 07/19/16 07/26/16 <0.05179 0.01280 +/-0.00307 L69194-1/5 07/26/16 08/02116 <0.04554 0.01030 +/-0.00292 L69272-1/5 08/02116 08/09/16 <0.04339 0.01420 +/-0.00319 L69363-1/5 08/09/16 08/16/16 <0.04136 0.00826 +/-0.00276 L69443-1/5 08/16/16 08/23/16 <0.04012 0.00902 +/-0.00268 L69544-1/5 08/23/16 08/30/16 <0.06753 0.01610 +/-0.00333 42

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Table A1.1 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-1 PO LLD (pCi/m3) 0.07 0.01 LABID START DATE END DATE 1-131 GROSS BETA L69615-1/5 08/30/16 09/06/16 <0.01821 0.02030 +/-0.00364 L69726-1/5 09/06/16 09/13/16 <0.05677 0.01080 +/-0.00285 L69883-1/5 09/13/16 09/20/16 <0.03610 0.00793 +/-0.00268 L69934-1/5 09/20/16 09/27/16 <0.04949 0.02190 +/-0.00387 L70048-1/5 09/27/16 10/04/16 <0.03904 0.02180 +/-0.00360 L70178-1/5 10/04/16 10/11116 <0.04483 0.02030 +/-0.00348 L70282-1/5 10/11/16 10/18/16 <0.03147 0.02000 +/-0.00369 L70393-1/5 10/18/16 10/25/16 <0.06442 0.01380 +/-0.00319 L70536-1/5 10/25/16 11/01/16 <0.05197 0.03690 +/-0.00456 L70560-1/5 11/01/16 11/08/16 <0.03599 0.02740 +/-0.00403 L70676-1/5 11/08/16 11/15/16 <0.05512 0.03570 +/-0.00467 L70742-1/5 11115/16 11/22116 <0.02909 0.03500 +/-0.00464 L70806-1/5 11/22116 11/29/16 <0.05501 0.02810 +/-0.00403 L70869-1/6 11/29/16 12106/16 <0.03559 0.01950 +/-0.00370 L70951-1/5 12106/16 12/13/16 <0.02608 0.02160 +/-0.00355 L71048-1/5 12113/16 12120/16 <0.06460 0.02210 +/-0.00358 L71091-1/5 12/20/16 12/27/16 <0.05707 0.01810 +/-0.00348 Average: 0.01732 Maximum: 0.03690 Minimum: 0.00639 43

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Table A1.2 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-3 61VA LLD (pCi/m3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L66432-2/5 12129/15 01/05/16 <0.04636 0.02960 +/-0.00420 L66463-2/5 01/05/16 01/12116 <0.04176 0.01450 +/-0.00316 L66587-215 01/12116 01/19/16 <0.05500 0.03110 +/-0.00439 L66635-215 01/19/16 01/26/16 <0.01334 0.01800 +/-0.00346 L66726-2/5 01/26/16 02102116 <0.04763 0.01970 +/-0.00357 L66829-2/5 02/02116 02109/16 <0.04679 0.01330 +/-0.00324 L66915-2/5 02/09/16 02116116 <0.04699 0.01660 +/-0.00330 L66990-215 02/16/16 02/23/16 <0.03123 0.01480 +/-0.00330 L67081-2/5 02/23/16 03/01/16 <0.06796 0.01630 +/-0.00339 L67163-2/5 03/01/16 03/08/16 <0.04460 0.01550 +/-0.00324 L67243-215 03/08/16 03/15/16 <0.03079 0.01050 +/-0.00287 L67320-215 03/15/16 03/22/16 <0.02468 0.01480 +/-0.00336 L67366-2/5 03/22116 03/29/16 <0.05954 0.01310 +/-0.00315 L67480-2/5 03/29/16 04/05/16 <0.05523 0.01760 +/-0.00346 L67589-2/5 04/05/16 04/12116 <0.06889 0.01580 +/-0.00322 L67683:..2/5 04/12116 04/19/16 <0.04597 0.00987 +/-0.00278 L67804-2/5 04/19/16 04/26/16 <0.04244 0.01760 +/-0.00350 L67933-2/5 04/26/16 05/03/16 <0.03383 0.01530 +/-0.00337 L68039-2/5 05/03/16 05/10/16 <0.05534 0.01840 +/-0.00350 L68137-2/5 05/10/16 05/17/16 <0.146* 0.04820* +/-0.02170 L68240-215 05/17/16 05/24/16 <0.05899 0.02140 +/-0.00369 L68307-215 OS/24/16 05/31/16 <0.06829 0.01950 +/-0.00355 L68396-215 05/31/16 06/07/16 <0.06313 0.01460 +/-0.00335 L68496-2/5 06/07/16 06/14/16 <0.05114 0.01160 +/-0.00312 L68572-2/6 06/14/16 06/21116 <0.03546 '0.01720 +/-0.00320 L68711-216 06/21/16 06/28/16 <0.01809 0.01760 +/-0.00349 L68749-2/6 06/28/16 07/05/16 <0.06456 0.02050 +/-0.00361 L68844-2/6 07/05/16 07/12116 <0.05222 0.01680 +/-0.00331 L68942-2/6 07/12116 07/19/16 <0.05391 0.01470 +/-0.00318 L69076-2/6 07/19/16 07/26/16 <0.05191 0.01180 +/-0.00300 L69194-2/6 07/26/16 08102116 <0.04559 0.01020 +/-0.00290 L69272-216 08/02116 08/09/16 <0.01822 0.01590 +/-0.00332 L69363-216 08/09/16 08/16/16 <0.04151 0.00922 +/-0.00284 L69443-216 08/16/16 08/23/16 <0.04014 0.00818 +/-0.00261 44

Table A1.2 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-3 61VA LLD (pCi/m3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L69544-2/6 08/23116 08/30/16 <0.06764 0.01250 +/-0.00305 L69615-2/6 08/30/16 09/06/16 <0.04350 0.02000 +/-0.00362 L69726-2/6 09/06/16 09/13/16 <0.05686 0.00879 +/-0.00267 L69883-216 09/13/16 09/20/16 <0.03618 0.00913 +/-0.00278 L69934-2/6 09/20/16 09/27/16 <0.02078 0.02540 +/-0.00408 L70048*2/6 09/27/16 10/04/16 <0.03910 0.03030 +/-0.00412 L70178-2/6 10/04/16 10/11/16 <0.04661 0.02280 +/-0.00371 L70282-216 10/11116 10/18/16 <0.03089 0.01790 +/-0.00347 L70393-2/6 10/18/16 10/25/16 <0.06474 0.01660 +/-0.00341 L70536-216 10/25/16 11/01/16 <0.05198 0.03390 +/-0.00440 L70560-216 11/01/16 11/08/16 <0.03641 0.02810 +/-0.00409 L70676*216 11/08/16 11/15/16 <0.05490 0.03530 +/-0.00463 L70742-2/6 11/15/16 11/22116 <0.06568 0.03130 +/-0.00444 L70806-2/6 11/22116 11/29/16 <0.05510 0.03020 +/-0.00416 L70869-216 11/29/16 12106/16 <0.03564 0.02180 +/-0.00385 L70951-217 12106/16 12113/16 <0.02613 0.01890 +/-0.00335 L71048*216 12113/16 12120/16 <0.06470 0.02790 +/-0.00395 L71091-2/6 12120/16 12/27/16 <0.05720 0.02110 +/-0.00368 Average: 0.01850 Maximum: 0.03530 Minimum: 0.00818

• LLD not met due to small sample size. Data not included in avg/maxlmin calculations.

45

Table A1.3 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-7 UH LLD (pCi/m3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L66432-3/6 12129/15 01/05/16 <0.04628 0.02830 +/-0.00412 L66463-3/6 01/05/16 01/12116 <0.04169 0.00966 +/-0.00276 L66587-3/6 01/12116 01/19/16 <0.05480 0.02880 +/-0.00426 L66635-3/6 01/19/16 01/26/16 <0.03429 0.01430 +/-0.00319 L66726-3/6 01/26/16 02/02116 <0.04753 0.01990 +/-0.00359 L66829-3/6 02102116 02/09/16 <0.04661 0.01040 +/-0.00301 L66915-3/6 02/09/16 02/16/16 <0.02074 0.01560 +/-0.00323 L66990-3/6 02116/16 02123/16 <0.03110 0.01320 +/-0.00318 L67081-3/6 02/23/16 03/01/16 <0.06688 0.01540 +/-0.00331 L67163-3/6 03/01/16 03/08/16 <0.04462 0.01710 +/-0.00337 L67243-3/6 03/08/16 03/15/16 <0.03080 0.00724 +/-0.00260 L67320-3/6 03/15/16 03/22116 <0.05944 0.01260 +/-0.00323 L67366-3/6 03/22116 03/29/16 <0.02490 0.01150 +/-0.00303 L67480-3/6 03/29/16 04/05/16 <0.05832 0.01860 +/-0.00366 L67589-3/6 04/05/16 04/12/16 <0.06874 0.01340 +/-O.00303 L67683-3/6 04/12116 04/19/16 <0.04635 0.01220 +/-0.00300 L67804-3/6 04/19/16 04/26/16 <0.04255 0.01570 +/-0.00339 L67933-3/6 04/26/16 05/03/16 <0.01414 0.01570 +/-0.00340 L68039-3/6 05/03/16 05/10/16 <0.05517 0.01650 +/-0.00337 L68137-3/6 05/10/16 05/17/16 <0.01381 0.01470 +/-0.00299 L68240-3/6 05/17/16 OS/24/16 <0.05847 0.01870 +/-0.00348 L68307-3/6 OS/24/16 05/31/16 <0.06811 0.01580 +/-0.00330 L68396-3/6 05/31/16 06/07/16 <0.06303 0.01230 +/-0.00317 L68496-3/6 06/07/16 06/14/16 <0.05111 0.01430 +/-0.00332 L68572-3/7 06/14/16 06/21/16 <0.03444 0.01750 +/-0.00318 L68711-3/7 06/21/16 06/28/16 <0.04354 0.01530 +/-0.00337 L68749-3/7 06/28/16 07/05/16 <0.06804 0.01990 +/-0.00366 L68844-3/7 07/05/16 07/12/16 <0.05047 0.01350 +/-0.00297_

L68942-3/7 07/12116 07/19/16 <0.05373 0.00956 +/-0.00275 L69076-3/7 07/19/16 07/26/16 <0.05165 0.01360 +/-0.00313 L69194-3/7 07/26/16 08/02/16 <0.04548 0.01090 +/-0.00297 L69272-3/7 08/02116 08/09/16 <0.04336 0.01480 +/-0.00324 L69363-3/7 08/09/16 08/16/16 <0.04259 0.00899 +/-0.00288 L69443-3/7 08/16/16 08/23/16 <0.04007 0.01010 +/-0.00278 L69544-3/7 08/23/16 08/30/16 <0.06745 0.01330 +/-0.00311 46

Table A1.3 Sample Type: Air Particulate Filter and Radiolcdine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-7 UH LLD (pCi/m3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L69615-3J7 08/30/16 09/06/16 <0.04037 0.01800 +/-O.00349 L69726-3/7 09/06/16 09/13/16 <0.05669 0.00770 +/-0.00257 L69883-3/7 09/13/16 09/20/16 <0.03599 0.00505 +/-0.00240 L69934-3/7 09/20/16 09/27/16 <0.05093 0.02460 +/-0.00411 L70048-3/7 09/27/16 10/04/16 <0.03902 0.01990 +/-0.00347 L70178-3/7 10/04/16 10/11/16 <0.04542 0.02100 +/-0.00355 L70282-3/7 10/11/16 10/18/16 <0.03120 0.01900 +/-0.00359 L70393-3/7 10/18/16 10/25/16 <0.06550 0.01550 +/-O.00336 L70536-3/7 10/25/16 11/01/16 <0.05187 0.03280 +/-0.00434 L70560-3/7 11/01/16 11/08/16 <0.03594 0.02440 +/-0.00384 L70676-3/7 11/08/16 11/15/16 <0.05508 0.03600 +/-0.00468 L70742-3/7 11/15/16 11/22116 <0.06611 0.03000 +/-O.00439 L70806-3/7 11/22116 11/29/16 <0.05734 0.02730 +/-O.00409 L70869-3/7 11/29/16 12/06/16 <0.03580 0.02160 +/-0.00386 L70951-3/8 12106/16 12/13/16 <0.02603 0.02050 +/-0.00346 L71048-3/7 12113/16 12120/16 <0.06454 0.02280 +/-0.00362 L71091-3/7 12120/16 12127/16 <0.05685 0.01790 +/-0.00346 Average: 0.01699 Maximum: 0.03600 Minimum: 0.00505 47

Table A1.4 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-20 GR LLO (pCi/m3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L68572-4/8 06/14/16 06/21/16 <0.03546 0.01710 +/-O.00321 L68711-4/8 06/21/16 06/28/16 <0.04307 0.01460 +/-O.00329 L68749-4/8 06/28/16 07105/16 <0.06790 0.01900 +/-O.00361 L68844-4/8 07/05/16 07/12116 <0.05047 0.01370 +/-0.00299 L68942-4/8 07/12/16 07/19/16 <0.05639 0.01430 +/-0.00325 L69076-4/8 07/19/16 07/26/16 <0.05167 0.01250 +/-O.00305 L69194-4/8 07/26/16 08/02116 <0.04547 0.01010 +/-0.00290 L69272-4/8 08/02116 08/09/16 <0.04337 0.01240 +/-O.00305 L69363-4/8 08/09/16 08/16/16 <0.04281 0.00904 +0.00290 L69443-4/8 08/16/16 08/23/16 <0.04009 0.00830 +/-O.00262 L69544-4/8 08/23/16 08/30/16 <0.06747 0.01430 +/-O.00319 L69615-418 08/30/16 09/06/16 <0.01568 0.02040 +/-0.00364 L69726-4/8 09/06/16 09/13/16 <0.05670 0.00674 +/-0.00248 L69883-4/8 09/13/16 09/20/16 <0.06700 0.01180 +/-0.00471 L69934-4/8 09/20/16 09/27/16 <0.05096 0.02960 +/-O.00441 L70048-4/8 09/27/16 10/04/16 <0.03903 0.01970 +/-0.00346 L70178-4/8 10104/16 10/11/16 <0.04530 0.01870 +/-O.00339 L70282-4/8 10/11/16 10/18/16 <0.03117 0.01420 +/-0.00324 L70393-4/8 10/18/16 10/25/16 <0.06563 0.01780 +/-O.00353 L70536-4/8 10/25/16 11/01/16 <0.05190 0.03580 +/-0.00450 L70560-4/8 11/01/16 11/08/16 <0.03595 0.02820 +/-O.00408 L70676-4/8 11/08/16 11/15/16 <0.05509 0.03050 +/-0.00438 L70742-4/8 11/15/16 11/22/16 <0.06613 0.03180 +/-O.00449 L70806-4/8 11/22/16 11/29/16 <0.05526 0.02310 +/-0.00373 L70869-4/8 11/29/16 12106116 <0.03574 0.01590 +/-0.00346 L70951-5/10 12106/16 12113/16 <0.02915 0.02210 +/-0.00391 L71048-4/8 12113/16 12120/16 <0.06454 0.02350 +/-0.00367 L71091-4/8 12/20/16 12/27/16 <0.05685 0.01970 +/-O.00358 Average: 0.01839 Maximum: 0.03580 Minimum: 0.00674 48

Table A1.5 Sample Type: Air Particulate Filter Analysis: Gamma Isotopic Units: pCi/m3 AIR PARTICULATE FILTER SAMPLES (GAMMA)

LLD (pCilm3) 0.05 0.06 LAB 10 LOCATION DATE CS-134 CS-137 L67692-1 AS-1 PG 02112116 <0.001861 <0.002114 L67692-2 AS-361VA 02112116 <0.002451 <0.001763 L67692-3 AS-7 UH 02112116 <0.003138 <0.002981 L68987-1 AS-1 PG 05/13/16 <0.001597 <0.00161 L68987-2 AS-361VA 05/13/16 <0.001931 <0.001599 L68987-3 AS-7 UH 05/13/16 <0.001755 <0.001427 L68987-4 AS-20 GR 06/21/16 <0.01107* <0.008607*

L70077-1 AS-1 PG 08/16/16 <0.001622 <0.001359 L70077-2 AS-361VA 08/16/16 <0.002109 <0.001509 L70077-3 AS-7 UH 08/16/16 <0.001899 <0.001399 L70077-4 AS-20 GR 08/16/16 <0.002201 <0.001654 L71344-1 AS-1 PG 11/18/16 <0.001483 <0.001579 L71344-2 AS-361VA 11/18/16 <0.001711 <0.001805 L71344-3 AS-7 UH 11/18/16 <0.002363 <0.001571 L71344-4 AS-20 GR 11/18/16 <0.002707 <0.002552

• New monitoring location AS-20 was activated on 06/14/16 with only two weeks left in the quarterly monitoring period. Due to the activation date, only two weekly samples were included in the quarterly composite analysis (06/21/16) for AS-20, as compared to 13 samples for each of the remaining (05/13/16) monitoring locations. The difference in activity between the (06/21/16) AS-20 sample and the remaining locations is attributed to the non-comparable sample volumes and sampling intervals. Weekly gross beta and 1-131 activity, as well as the remaining 2016 quarterly composite gamma analyses were comparable for all monitoring locations.

49

&.i&:'.. ll!LiJJlOii:i:JOlIDii ...,.-

Table A 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring - Within General Area of Site Boundary I

Station 1st atr I 2nd atr 3rd atr 14th atr Annual Mean

(_._ M-16

_._. *__  : 9.6 I

• ---:**~**_*_***_*_*_*_-_***_-t-*_-_***_*",---,,-,

9.6 I 12.5  !

-'-.t----.---*..*."..-,,* *..~"**r----*-*

11.8

. -*-*-***-*-"*  ! 10.8_ -_

'--T.,_._-_._-_._.. _,j I

...._.. "_.~~.!.~ . . _".. _L".._.. .,_.. . , .. ~.:.4 .__._, _. J" ....."".",,, _.~_:!t ......"."L..._.".. _..!Q:Q,_",.." ""...i....._"..."..~9:L.,,, _ L__..",_. .~:.~. ..,_ ,.".,_. .:

M-21  : 10.6 l 10.51 12.2 I 12.3 j 11.4  ;

M-22 6.8 I 1

7.5  !

I 8.8 1

I 9.2 ,1... 8.1 M-23 5.1 L 7.61 9.9! 10.0 L 8.?

M-25 2.2 II 6.0 1

'1 I

7.8 1

I 9.1 6.3 M-28  ; 9.7 I, 10.3 I 11.6 ".".l 12.6j 11.0 M 94 i l l

- 8.9 I 9.3  ! 10.4 I 11.3  !! 10.0 "Location with highest annual mean Outer Ring - Approximately Three (3) to Five (5) Miles from the Site Station 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr i Annual Mean M-36 Not Available 7.2 7.7 8.3 M-40 Ij M-48 M-49 M-50 "Location with highest annual mean 50 eee A .. ¥.. s* -w!: 5* .

Table A 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - Population Centers & Schools Station 1st Qtr 2nd etr 3rd etr 4th etr Annual Mean M-011' 9.6 10.4\ 12.0 13~2, 11.3 . j

. .,_",. _..,~~.~?., _.._.:.__._._ _..,1..Q.:-?..._., _._"..: "..., ~.~~._,,, . _.,_ i_ _., _.._1..~. :Q_...,., ,_._.,I..__._ _ .. _.l!:~_ __.. . Lm._ ,....1Q;~,_ ,.._.j

...... M 10 M-09!

1 9.1 i

t ,

8.1 i 10.3 I 11.3 i 9.7 i[

) - - _****.* _ " " _ . _ , .* _ - - . _ . _ _ .~

~ " .. " " _ . - - ~_

7.5

"'..-..- _" _ - _(

i ,.,. A 8.0 ' _** _ _.A_ _

---+-_ ~ _ 8.9 -.. . . .*, . ,--_*.. 1__..***,,*_*_-_*

~*

9.3*

• _ _****-**f,*_*

~~

- , * - 8.4 .....*......""_ _.--_.'1!

M-33 i

~

7.1  :

7.5 i 9.0

! 9.1

_..\ -_ _ _--'_._ \_ ,._" ,..,

! 8.2 ,*...._ _ "'.'.j I

M-38 8.2' 9.2 9.7! 10.8 i 9.5  !

M-39 7.3 7.4 8.3 I 10.0 8.2 I

• Location with highest annual mean Table A 2.3 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Special Interest Areas - Control Station 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Mean M-14 9.0 9.6 11.7 12.3 10.7 51 I

. pUd iii Sb

Table A3.1 Sample Type: Surface Water Analysis: Gamma Isotopic Units: pCi/L SURFACE WATER SAMPLES (GAMMA)

LLD (pCi/L) 15 15 30 15 30 15 30 15 15 18 60 15 LAB 10 LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 L66700-1 MRDOWN 01/28/16 <4.04 <4.181 <9.821 <4.665 <9.369 <5.258 <10.36 <8.202 <3.522 <4.709 <22.22 <6.429 L66700-2 MRDOWNGG 01/28/16 <5.028 <5.203 <13.54 <5.518 <11.54 <4.863 <10.71 <9.498 <5.244 <6.982 <31.15 <9.123 L66700-5 MRUP 01/28/16 <5.812 <5.276 <12.77 <5.717 <14.56 <5.293 <9.876 <7.603 <5.776 <6.815 <27 <7.967 L66700-6 MRUPGG 01/28/16 <7.004 <8.457 <12.73 <6.747 <13.78 <6.367 <16.48 <13.58 <8.282 <8.363 <38.64 <7.868 L67955-1 MRDOWN 05/04/16 <4.725 <4.656 <10.64 <9.226 <9.971 <7.216 <10.75 <11.83 <5.182 <6.947 <35.76 <12.04 L67955-3 MRUP 05/04/16 <6.193 <7.182 <16.14 <8.43 <17.72 <7.421 <12.41 <11.62 <6.709 <8.409 <35.51 <8.197 L69273-1 MRDOWN 08/04/16 <8.043 <7.064 <11.06 <8.658 <10.11 <6.514 <13.48 <13.33 <7.706 <7.855 <40.98 <9.544 L69273-3 MRUP 08/04/16 <8 <7.778 <15.71 <6.538 <16.7 <5.643 <15.17 <14.8 <7.029 <5.497 <41.63 <13.12 L70558-1R1 MRDOWN 11/03/16 <2.074 <2.542 <5.822 <2.381 <4.726 <2.712 <4.557 <11.64 <2.035 <2.381 <22.41 <7.768 L70558-3R1 MRUP 11/03/16 <2.171 <2.082 <5.373 <2.172 <4.639 <2.638 <4.308 <9.784 <1.831 <2.168 <19.05 <6.132 L70558-5R1 MRDOWN GG 11/03/16 <2.316 <2.563 <5.503 <2.514 <4.816 <2.834 <4.436 <11.17 <2.256 <2.378 <20.72 <6.749 L70558-7R1 MRUPGG 11/03/16 <2.661 <3.077 <7.257 <2.595 <5.853 <3.247 <5.26 <12.32 <2.554 <2.878 <25.13 <7.458 L70609-1R1 MRDOWN* 11/09/16 <1.772 <1.795 <4.152 <1.698 <3.693 <2.094 <3.463 <4.957 <1.705 <2.051 <12.17 <3.548 L70609-3R1 MRDOWN GG* 11/09/16 <2.351 <2.527 <5.134 <2.186 <4.74 <2.591 <4.77 <7.842 <2.819 <2.581 <16.44 <4.402 "GG" - indicates duplicate sample

• Annual Sample collected during liquid discharge 52

Table A3.2 Sample Type: Surface Water Analysis: Tritium Units: pCi/L SURFACE WATER SAMPLES (TRITIUM)

LLD (pCi/L) 3000 LASlO LOCATION DATE H-3 L66597-1 OUTFALL 007 01/20/16 2020 +/-399 L66597-1C1 OUTFALL 007 01/20/16 2100 +/-537 L66597-1R1 OUTFALL 007 01/20/16 2050 +/-539 L66700-3 MRDOWN 01/28/16 <589 L66700-4 MRDOWN GG 01/28/16 <590 L66700-7 MRUP 01/28/16 <592 L66700-8 MRUP GG 01128/16 <594 L66916-1C1 OUTFALL 007 02117/16 <533 L66916-2C1 OUTFALL 007 GG 02117/16 <528 L67281-1 OUTFALL 007 03/17/16 <441 L67637-1 OUTFALL 007 04/14/16 <542 L67955-2 MRDOWN 05104/16 <443 L67955-4 MRUP 05/04/16 <449 L68136-1C1 OUTFALL 007 05/18/16 <572 L68136-2 OUTFALL 007 GG 05/18/16 <496 L68475-1 OUTFALL 007 06/08/16 <500 L68982-1 OUTFALL 007 07/20/16 <502 L69273-2 MRDOWN 08/04/16 <491 L69273-4 MRUP 08/04/16 <482 L69405-1 OUTFALL 007 08/17/16 698 +/-195 L69663-1C1 OUTFALL 007 09/07/16 <458 L69663-2C1 OUTFALL 007 GG 09/07/16 <468 L70179-1 OUTFALL 007 10/12116 <370 L70558-2 MRDOWN 11/03/16 <597 L70558-4 MRUP 11103/16 <588 L70558-6 MRDOWN GG 11/03/16 <597 L70558-8 MRUPGG 11/03/16 <599 L70609-2 MRDOWN* 11/09/16 <525 L70609-4 MRDOWN GG* 11/09/16 <515 L70677-1 OUTFALL 007 11/15/16 <577 L70956-1 OUTFALL 007 12114/16 <509 L70956-2 OUTFALL 007 GG 12114/16 <497

.. Annual Sample collected during liquid discharge "GG" - indicates duplicate sample 53

Table A4.1 Sample Type: Ground Water Analysis: Gamma Isotopic Units: pCi/L GROUND WATER SAMPLES (GAMMA)

LLD (pCi/L) 15 15 30 15 30 15 30 15 18 60 15 LASlO LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 L70675-1 PGWELL 11/16/16 <7.819 <8.921 <15.99 <8.332 <17.72 <11.9 <15.54 <11.51 <9.43 <36.87 <7.972 L70675-5 CONSTWELL 3 11/16/16 <10.96 <10.11 <18.33 <8.68 <20.51 <8.684 <15.54 <9.291 <9.564 <31.52 <11.8 L70675-9 CONSTWELL4 11/16/16 <8.531 <8.158 <13.67 <7.554 <15.32 <9.443 <12.09 <9.681 <8.422 <30.48 <10.31 54

Table A4.2 Sample Type: Ground Water Analysis: Tritium Units: pCi/L GROUND WATER SAMPLES (TRITIUM)

LLO (pCilL) 2000 LAB 10 LOCATION DATE H-3 L70675-3 PGWELL 11/16/16 <564 L70675-4 PGWELLGG 11/16/16 <571 L70675-7 CONSTWELL3 11/16/16 <575 L70675-8 CONSTWELL 3 GG 11/16/16 <572 L70675-11 CONSTWELL4 11/16/16 <574 I

L70675-12 CONSTWELL 4 GG 11/16/16 <575 "GG" - indicates duplicate sample.

55 db+- -.. g'b",*4;;'* ~¥.

Table A4.3 Sample Type: Ground Water Analysis: lodine-131 Units: pCilL GROUND WATER SAMPLES (IODINE-131)

LLD (pCilL) 1 LAB 10 LOCATION DATE 1-131 L70675-2 PGWELL 11/16/16 <0.654 L70675-6 CONSTWELL 3 11/16/16 <0.874 L70675-10 CONSTWELL4 11/16/16 <0.978 56

Table A5.1 Sample Type: Sediment Analysis: Gamma Isotopic Units: pCi/kg SEDIMENT SAMPLES (GAMMA)

LLD (pCi/kg) 150 180 LASlO LOCATION DATE CS-134 CS-137 L69790-1 SEDHAM 09/15/16 <47.07 <44.08 L69790-2 SEDCONT 09/15/16 <55.30 <44.28 L69790-3 SEDHAM GG 09/15/16 <42.23 <43.63 L69790-4 SEDCONT GG 09/15/16 <65.25 <44.80 "GG" - indicates duplicate sample.

57

s ;; 'n: 1

Table A6.1 Sample Type: Fish Analysis: Gamma Isotopic Units: pCi/kg FISH SAMPLES (GAMMA)

LLD (pCi/kg) 130 130 260 130 260 130 150 LASlO LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 L69764-1 FISH UP 09/12116 <50.47 <50.98 <90.56 <50.57 <112.5 <57.99 <46.59 L69764-2 FISHDOWN 09/12116 <48.35 <48.92 <91.05 <40.76 <100.7 <56.13 <51.91 58

Table A7.1 Sample Type: Vegetation Analysis: Gamma Isotopic Units: pCi/kg VEGETATION SAMPLES (GAMMA)

LLD (pCi/kg) 60 60 80 LASlO LOCATION DATE 1-131 CS-134 CS-137 L66964-1 VEG-CONT 02118/16 <28.74 <13.43 <17.25 L66964-2 VEG-J 02118/16 <45.11 <29.37 <29.45 L68361-1 VEG-CONT 06/02116 <48.2 <20.7 <22.69 L68361-2 VEG-J 06/02116 <46.85 <17.81 <18.17 L69404-1 VEG-CONT 08/18/16 <54.45 <21.9 <26.98 L69404-2 VEG-J 08/18/16 <45.23 <29.69 <35.95

" L70740-1 VEG-CONT 11/18/16 <58.7 <20.66 <18.66 L70740-2 VEG-J 11/18/16 <59.61 <20.33 <23.33 59

Table A 8.1 Sample Type: Special Samples Analysis: Gamma Isotopic Units: pCi/L, pCi/kg SPECIAL SURFACE WATER SAMPLES GAMMA)

LLD (pCi/L) 15 15 30 15 30 15 30 15 15 18 60 15 LAB 10 LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 L67282-1 OUTFALL 007 03/17/16 <3.783 <3.87 <8.073 <3.557 <8.171 <3.945 <6.315 <6.05 <3.859 <3.866 <18.8 <5.547 L68475-1 OUTFALL 007 06/08/16 <4.924 <5.452 <12.45 <6.23 <12.96 <6.685 <10.34 <14.64 <5.737 <7.146 <38.73 <14.44 L69765-1 OUTFALL 007 09/14/16 <8.508 <7.587 <15.47 <7.912 <15.95 <7.996 <10.39 <12.12 <6.151 <6.289 <30.35 <13.53 OUTFALL 007 L69765-2 GG 09/14/16 <5.875 <6.712 <12.02 <6.12 <11.76 <6.045 <9.541 <9.667 <6.041 <5.803 <28.09 <8.569 L71173-1 OUTFALL 007 12120/16 <2.237 <2.315 <5.641 <2.236 <5.15 <2.611 <4.158 <11.39 <2.103 <2.129 <22.68 <7.422 LLD (pCi/kg) 130 130 260 130 260 130 150 LASlO LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 L70071-1 Meat 1 10103/16 <31.21 <34.33 <61.04 <25.55 <86.28 <37.86 <43.9 L70071-2 Meat 2 10103/16 <41.5 <43.19 <88.9 <31.8 <55.13 <46.3 <47.66 60

Table A 9.1 Sample Type: Quality Assurance Report Analysis: Environmental Dosimeters STANFORD DOSIMETRY

ENVIRONMENTAL DOSIMETRY COMPANY ANNUAL QUALITY ASSURANCE STATUS REPORT January - December 2016 Prepared By: Date:

I ,

Approved By: Date: ~ i ~'

/ t '=1--

r Environmental Dosimetry Company 10 Ashton Lane Sterling, MA 01564

TABLE OF CONTENTS Page LIST OF TABLES '" '" iii EXECUTIVE SUMMARy iv I. INTRODUCTION 1 A. QC Program 1 B. QA Program 1 II. PERFORMANCE EVALUATION CRITERIA , 1 A. Acceptance Criteria for Internal Evaluations 1 B. QC Investigation Criteria and Result Reporting 3 C. Reporting of Environmental Dosimetry Results to EDC Customers 3 III. DATA

SUMMARY

FOR ISSUANCE PERIOD JANUARY-DECEMBER 2016 3 A. General Discussion  ; 3 B. Result Trending 4 IV. STATUS OF EDC CONDITION REPORTS (CR) 4 V. STATUS OF AUDITS/ASSESSMENTS 4 A. InternaL 4 B. External 4 VI. PROCEDURES AND MANUALS REVISED DURING JANUARY - DECEMBER 2016 4 VII. CONCLUSION AND RECOMMENDATIONS 4 VIII. REFERENCES 4 APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS

-ii-

.. 81:'

LIST OF TABLES

1. Percentage of Individual Analyses Which Passed EDC Internal Criteria, January- December 2016 5

2. Mean Dosimeter Analyses (n=6), January - December 2016 5

3. Summary of Independent QC Results for 2016 5

• iii-

EXECUTIVE

SUMMARY

Routine quality control (QC) testing was performed for dosimeters issued by the Environmental Dosimetry Company (EDC) .

During this annual period, 1000/0 (72172) of the individual dosimeters, evaluated against the EDC internal performance acceptance criteria (high-energy photons only), met the criterion for accuracyand 1000/0 (72/72) met the criterion for precision (Table 1). In addition, 100% (12/12) of the dosimetersets evaluated against the internal tolerance limits met EDC acceptance criteria (Table 2) and 100% (6/6) of independent testing passed the performance criteria (Table 3). Trending graphs, which evaluate performance statistic for high-energy photon irradiations and co-located stations are given in Appendix A.

One internal assessmentwas performed in 2016. There were no findings.

-iv-

I. INTRODUCTION The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in-house performance testing and independent performance testing by EDC clients, and both internal and client directed program assessments.

The purpose of the dosimetry quality assurance program is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes. Two programs are used:

A. QC Program Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in-house testing program coordinated by the EDC QA Officer and (2) independent test perform by EDC clients. In-house test are performed using six pairs of 814 dosimeters, a pair is reported as an individual result and six pairs are reported as the mean result.

Results of these tests are described in this report.

Excluded from this report are instrumentation checks. Although instrumentation checks represent an important aspect of the quality assurance program , they are not included as process checks in this report. Instrumentation checks represent between 5-10% of the TLDs processed.

B. QA Program An internal assessment of dosimetry activities is conducted annually by the Quality Assurance Officer (Reference 1). The purpose of the assessment is to review procedures, results, materials or components to identify opportunities to improve or enhance processes and/or services.

II. PERFORMANCE EVALUATION CRITERIA A. Acceptance Criteria for Internal Evaluations

1. Bias For each dosimeter tested, the measure of bias is the percent deviation of the reported result relative to the delivered exposure. The percent deviation relative to the delivered exposure is calculated as follows:

where:

H; = the corresponding reported exposure for the jlh dosimeter (Le., the reported exposure)

HI = the exposure delivered to the ith irradiated dosimeter (i.e., the delivered exposure) 1 of 6

2. Mean Bias For each group of test dosimeters, the mean bias is the average percent deviation of the reported result relative to the delivered exposure. The mean percent deviation relative to the delivered exposure is calculated as follows:

where:

H; = the corresponding reported exposure for the ith dosimeter (Le., the reported exposure)

Hi = the exposure delivered to the i1h irradiated test dosimeter (Le., the delivered exposure) n = the numberof dosimeters in the test group

3. Precision For a group of test dosimeters irradiated to a given exposure, the measure of precision is the percent deviation of individual results relative to the mean reported exposure. At least two values are required for the determination of precision. The measure of precision for the ith dosimeter is:

where:

H; = the reported exposurefor the ith dosimeter(Le., the reported exposure)

R = the mean reported exposure; i.e., R=L H:( *J n = the number of dosimeters in the test group

4. EDC Internal Tolerance Limits All evaluation criteria are taken from the "EDC QualitySystem Manual,"

(Reference 2). These criteria are only applied to individual test dosimeters irradiated with high-energy photons (Cs-137) and are as follows for Panasonic Environmental dosimeters: +/- 15%for bias and +/-

12.8% for precision.

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B. aClnvestigation Criteria and Result Reporting EDC Quality System Manual (Reference 2) specifies when an investigation is required due to a QC analysis that has failed the EDC bias criteria. The criteria are as follows:

1. No investigation is necessary when an individual QC result falls outside the QC performance criteria for accuracy.

2. Investigations are initiated when the meanof a QC processing batch is outside the performance criterion for bias.

C. Reporting of Environmental Dosimetry Results to EDC Customers

1. All results are to be reported in a timely fashion.

2. If the QA Officer determines that an investigation is required for a process, the results shall be issued as normal. If the QC results, prompting the investigation, have a mean bias from the known of greater than +/-20%, the results shall be issued with a note indicating that they may be updated in the future, pending resolution of a QA issue.

3. Environmental dosimetry results do not require updating if the investigation has shown that the mean bias between the original results and the corrected results, based on applicable correction factors from the investigation, does not exceed +/-20%.

III. DATA

SUMMARY

FOR ISSUANCE PERIOD JANUARY-DECEMBER 2016 A. General Discussion Results of performance tests conducted are summarized and discussed in the following sections. Summaries of the performance.tests for the reporting period are given in Tables 1 through 3 and Figures 1 through 4.

Table 1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons only. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (72/72) met the criterion for precision.

A graphical interpretation is provided in Figures 1 and 2.

Table 2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall,100%

(12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria. A graphical interpretation is provided in Figure 3.

Table 3 presents the independent blind spike results for dosimeters processed during this annual period. All results passed the performance acceptance criterion. Figure 4 is a graphical interpretation of Seabrook Station blind 00-located station results.

3 of 6

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B. Result Trending One of the main benefits of performing quality control tests on a routine basis is to identify trends or performance changes. The results of the Panasonic environmental dosimeter performance tests are presented in Appendix A. The results are evaluated against each of the performance criteria listed in Section II, namely: individual dosimeter accuracy, individual dosimeter precision, and mean bias.

All of the results presented in Appendix A are plotted sequentially by processing date.

IV. STATUS OF EDC CONDITION REPORTS (CR)

No condition reports were issued during this annual period.

V. STATUS OF AUDITS/ASSESSMENTS A. Internal EDC Internal Quality Assurance Assessment was conducted during the fourth quarter 2016. There were no findings identified.

B. External None.

VI. PROCEDURES AND MANUALS REVISED DURING JANUARY - DECEMBER 2016 Several procedures were reissued with no changes as part of the 5 year review cycle.

VII. CONCLUSION AND RECOMMENDATIONS The quality control evaluations continue to indicate the dosimetry processing programs at the EDC satisfy the criteria specified in the Quality System Manual. The EDC demonstrated the ability to meet all applicable acceptance criteria.

VIII. REFERENCES

1. EDC Quality Control and Audit Assessment Schedule, 2016.

2. EDC Manual 1, Quality System Manual, Rev. 3, August 1, 2012.

40f6

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TABLE 1 PERCENTAGE OF INDIVIDUAL DOSIMETERSTHAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2016(1};-(2)

(1)-rhis table summarizes results of tests conducted by EDC.

(2)Environmental dosimeter results are free in air.

TABLE 2 MEAN DOSIMETERANALYSES (N=6)

JANUARY - DECEMBER 2016(1), (2) 4/22/2016 40 3.5 0.7 I Pass 4/29/2016 80 1.8 0.7 Pass 5/10/2016 70 1.8 1.8 Pass 7/25/2016 33 2.4 1.5 Pass 8/212016 56 2.4 1.6 Pass 8/2/2016 123 0.7 1.4 Pass 10125/2016 28 2.9 1.0 Pass 10/29/2016 93 3.2 1.8 Pass 11/612016 61 0.0 1.6 Pass 1/30/2017 39 1.4 2.5 Pass 1/31/2017 76 2.2 1.3 Pass 1/31/2017 101 -1.7 1.5 Pass (1)This table summarizes results of tests conducted by EDC for TLDs issued in 2016.

(2)Environmental dosimeter results are free in air.

TABLE 3

SUMMARY

OF INDEPENDENT DOSIMETERTESTING JANUARY - DECEMBER 2016(1), (2) 1S Qtr.2016 Millstone Pass 'I 2n Qtr.2016 Millstone Pass 2n Qtr.2016 Seabrook Pass 3r Qtr. 2016 Millstone Pass 4 Qtr.2016 Millstone Pass 4 Qtr.2016 Seabrook Pass (1)Performance criteria are +/- 30%.

(2)Slind spike irradiations using Cs-137 5 of 6

APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS ISSUE PERIOD JAf\:JAURY - DECEMBER 2016 6of6

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Table A.9.2 Sample Type: Quality Assurance Report Matrix: Milk, Soil, Liquid, Vegetation, Air Charcoal, Air Particulate, Water TELEDYNE BROWN ENGINEERING

For the 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 Engineering's MAPEP March 2016 air particulate cross check sample is now being provided to TBE by Analytics. MAPEP's policy is to evaluate as failed non-reported nuclides that were reported in the previous study. 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 lb. 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, 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 and correct uncertainty of 0.301 +/- 0.230, MAPEP would have evaluated the result as acceptable. NCR 16-14

2. Teledyne Brown Engineering's Analytics' March 2016 milk Sr-90 result of 15 +/- . 125 pCiIL was higher than the known value of 11.4 pCiIL 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 Engineering's ERA November 2016 sample for H-3 in water was evaluated as failing. A result of 918 pCiIL 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

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4. Teledyne Brown Engineering's Analytics' December 2016 milk Sr-90 sample result of 14.7 +/- .26 pCi/L was higher than the known value of 10 pCiIL 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 1.2L (Normally we use. 6L for client samples). If the technician had entered an aliquot of 1.2L into the LIMS system, the result would have been 12.2 pCiIL, which would have been considered acceptable. NCR 16-35

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ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF3)

Identification Reported Known Ratio (c)

MonthNear Number Matrix Nuclide Units Value (a) Value (b) TBEJAnalytics Evaluation (d)

March 2016 E11476 Milk Sr-89 pCilL 97 86.7 1.12 A Sr-90 pCilL 15 11.4 1.32 N(2)

E11477 Milk 1-131 pCi/L 85.9 82.2 1.05 A Ce-141 pCi/L 106 98.4 1.08 A Cr-51 pCi/L 255 243 1.05 A Cs-134 pCi/L 134 130 1.03 A Cs-137 pCi/L 174 161 1.08 A Co-58 pCi/L 123 117 1.05 A Mn':54 pCilL 141 117 1.21 W Fe-59 pCi/L 152 131 1.16 A Zn-G5 pCi/L 193 179 1.08 A Co-60 pCi/L 259 244 1.06 A E11479 AP Ce-141 pCi 69 81.1 0.85 A Cr-51 pCi 242 201 1.20 W Cs-134 pCi 98.1 107.0 0.92 A Cs-137 pCi 136 133 1.02 A Co-58 pCi 91.9 97 0.95 A Mn-54 pCi 98.6 96.2 1.02 A Fe-59 pCi 98.8 108 0.91 A Zn-G5 pCi 131 147 0.89 A Co-GO pCi 209 201 1.04 A E11478 Charcoal 1-131 pCi 85.3 88.3 0.97 A E11480 Water Fe-55 pCi/L 1800 1666 1.08 A June 2016 E11537 Milk Sr-89 pCilL 94.4 94.4 1.00 A Sr-90 pCi/L 13.4 15.4 0.87 A E11538 Milk 1-131 pCilL 96.8 94.5 1.02 A Ce-141 pCi/L 129 139 0.93 A Cr-51 pCi/L 240 276 0.87 A Cs-134 pCi/L 157 174 0.90 A Cs-137 . pCi/L 117 120 0.98 A Co-58 pCi/L 131 142 0.92 A Mn-54 pCi/L 128 125 1.02 A Fe-59 pCi/L 132 122 1.08 A Zn-65 pCilL 235 235 1.00 A Co-60 pCi/L 169 173 0.98 A (a) Teledyne Brown Engineering reported result.

(b) The Analytics known value Is equal to 100% of the parameter present in the standard as determined by gravimetric ancVor volumetric measurements made during standard preparation.

(c) Ratio of Teledyne Brown Engineering to Analytlcs results.

(d) Analytlcs evaluation based on TBE Internal QC limits: A = Acceptable, reported result faits 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.

(2) NCR 16-26 was initiated

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ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE20F3)

Identification Reported Known Ratio (c)

MonthNear Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

June 2016 E11539 Charcoal 1-131 pCi 86.1 89.4 0.96 A E11540 AP Ce-141 pCi 105 99.8 1.05 A Cr-51 pCi 216 198.0 1.09 A Cs-134 pCi 113 125 0.90 A Cs-137 pCi 94.5 86.6 1.09 A Co-58 pCi 101 102 0.99 A Mn-54 pCi 88.8 90.2 0.98 A Fe-59 pCi 82 87.5 0.94 A Zn~5 pCi 174 169 1.03 A Co-60 pCi 143 124 1.15 A E11541 Water Fe-55 pCi/L 164 186 0.88 A September 2016 E11609 Milk Sr-89 pCi/L 90 90.9 0.99 A Sr-90 pCi/L 13.3 13.7 0.97 A E11610 Milk 1-131 pCi/L 80.4 71.9 1.12 A Ce-141 pCi/L 81.3 93 0.87 A Cr-51 pCi/L 198 236 0.84 A Cs-134 pCi/L 122 136 0.90 A Cs-137 pCi/L 119 119 1.00 A Co-58 pCi/L 92.2 97.4 0.95 A Mn-54 pCi/L 156 152 1.03 A Fe-59 pCi/L 97.5 90.6 1.08 A Zn~5 pCi/L 189 179 1.06 A Co-60 pCi/L 131 135 0.97 A E11611 Charcoal 1-131 pCi 52.4 59.9 0.87 A E11612 AP Ce-141 pCi 67.5 63.6 1.06 A Cr-51 pCi 192 161.0 1.19 A Cs-134 pCi 91.4 92.6 0.99 A Cs-137 pCi 93.9 80.8 1.16 A Co-58 pCi 66 66.4 0.99 A Mn-54 pCi 104 104 1.00 A Fe-59 pCi 60.5 61.8 0.98 A Zn-65 pCi 140 122 1.15 A Co-60 pCi 119 91.9 1.29 W (a) Telecfyne Brown Engineering reported result.

(b) The Analytlcs known value ;s equal to 100% of the parameter present In the standarrf as determined by gravimetric andlor volumetric measurements made during standarrf preparation.

(c) Ratio of Teledyne Brown Engineering to Analytlcs results.

=

(d) Analyt/cs evaluation based on TBE Internal QC limits: A Acceptable, reported result falls within ratio limits of O. 80-1.20.

W-Acceptable vJth warning, reported result falls wffhln 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.

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ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE30F3)

Identification Reported Known Ratio (c)

MonthlYear Number Matrix Nuclide Units Value (a) Value (b) TBEIAnalytics Evaluation (d)

September 2016 E11613 Water Fe-55 pCi/L 1990 1670 1.19 A E11614 Soil Ce-141 pCi/g 0.153 0.175 0.87 A Cr-51 pCi/g 0.482 0.441 1.09 A Cs-134 pCi/g 0.270 0.254 1.06 A Cs-137 pCi/g 0.313 0.299 1.05 A Co-58 pCi/g 0.177 0.182 0.97 A Mn-54 pCi/g 0.340 0.285 1.19 A Fe-59 pCi/g 0.206 0.17 1.21 W Zn-G5 pCi/g 0.388 0.335 1.16 A Co-GO pCi/g 0.284 0.252 1.13 A December 2016 E11699 Milk Sr-89 pCilL 95 74.2 1.28 W Sr-90 pCi/L 14.7 10 1.47 N(3)

E11700 Milk 1-131 pCi/L 97.5 97.4 1.00 A Ce-141 pCi/L 136 143 0.95 A Cr-51 pCi/L 247 280 0.88 A Cs-134 pCi/L 164 178 0.92 A Cs-137 pCilL 120 126 0.95 A Co-58 pCi/L 139 146 .0.95 A Mn-54 pCi/L 126 129 0.98 A Fe-59 pCi/L 114 125 0.91 A Zn-65 pCi/L 237 244 0.97 A Co-60 pCi/L 168 178 0.94 A E11701 Charcoal 1-131 pCi 95.6 98 0.98 A E11702 AP Ce-141 pCi 91.7 97.7 0.94 A Cr-51 pCi 210 192.0 1.09 A Cs-134 pCi 122 122 1.00 A Cs-137 pCi 93.9 86.4 1.09 A Co-58 pCi 92 100 0.92 A Mn-54 pCi 93.7 88.5 1.06 A Fe-59 pCi 84.9 84.5 1.00 A Zn-65 pCi 176 167 1.05 A Co-GO pCi 151 122 1.24 W E11702 AP Sr-89 pCi 79.1 92 0.86 A Sr-90 pCi 10 12.5 0.80 A E11703 Water Fe-55 pCi/L 2180 1800 1.21 W (a) Teledyne Brown Engineering reported result.

(b) The Analytlcs known value is equal to 100% of the parameter present in the standard as determined by gravimetric ancVor volumetric measurements made during standanJ preparation.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytlcs evaluation based on rBE Internal QC limits: A= Acceptable, reported result faJJs within ratio limits of 0.8CJ..1.20.

W-Acceptable ...nth warning, reported result falls within 0.70-0.80 or 1.2CJ..1.30. N =Not Acceptable, reported result falls outside the ratio limits of < 0.70 and> 1.30.

(3) NCR 16-35 was Initiated

-- ,.Ii

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Acceptance MonthNear Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

March 2016 16-MaW34 Water Am-241 Bq/L 0.008 (1) A Ni-63 Bq/L 12.4 12.3 8.6-16.0 A Pu-238 Bq/L 1.4900 1.2440 0.871-1.617 A Pu-239/240 Bq/L 0.729 0.641 0.449-0.833 A 16-MaS34 Soil Ni-63 Bq/kg 1140 1250.0 875-1625 A Sr-90 Bq/kg 8.15 (1) A 16-RdF34 AP U-234/233 Bq/sample 0.1620 0.1650 0.116-0.215 A U-238 Bq/sample 0.163 0.172 0.120-0.224 A 16-GrF34 AP Gr-A Bq/sample 0.608 1.20 0.36-2.04 A Gr-B Bq/sample 0.8060 0.79 0.40-1.19 A 16-RdV34 Vegetation Cs-134 Bq/sample 10.10 10.62 7.43-13.81 A Cs-137 Bq/sample 6.0 5.62 3.93-7.31 A Co-57 Bq/sample 13.3000 11.8 8.3-15.3 A Co-60 Bq/sample 0.013 (1) A Mn-54 Bq/sample 0.0150 (1) A Sr-90 'Bq/sample 0.301 (1) N(4)

Zn-65 Bq/sample 10.500 9.6 6.7-12.5 A September 2016 16-MaW35 Water Am-241 Bq/L 0.626 0.814 .570-1058 W Ni-63 Bq/L 12.4 17.2 12.0-22.4 A Pu-238 Bq/L 1.23 1.13 0.79-1.47 W Pu-239/240 Bq/L 0.0318 0.013 (1) A 16-MaS35 Soil Ni-63 Bq/kg 724 990 693-1287 A Sr-90 Bq/kg 747 894 626-1162 A 16-RdF35 AP U-234/233 Bq/sample 0.160 0.15 0.105-0.195 A U-238 Bq/sample 0.157 0.156 0.109-0.203 A 16-RdV35 Vegetation Cs-134 Bq/sample -0.103 (1) A Cs-137 Bq/sample 5.64 5.54 3.88-7.20 A Co-57 Bq/sample 7.38 6.81 4.77-8.85 A Co-60 Bq/sample 4.81 4.86 3.40-6.32 A Mn-54 Bq/sample 7.4 7.27 5.09-9.45 A Sr-90 Bq/sample 0.774 0.80 0.56-1.04 A Zn-65 Bq/sample 5.46 5.4 3.78-7.02 A (1) False positive test.

(a) Teledyne Brown Engineering reported result (b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric ancVor volumetric measurements made during standard preparation.

(c) DOEIMAPEP evaluation: A=acceptable, W--acceptable wffh warning, N=not acceptable.

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ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF1)

Identification Reported Known Acceptance MonthNear Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)

May 2016 RAD-105 Water Sr-89 pCi/L 48.9 48.2 37.8 - 55.6 A Sr-90 pCi/L 25.0 28.5 20.7 - 33.1 A Ba-133 pCi/L 53.1 58.8 48.7 - 64.9 A Cs-134 pCi/L 40.9 43.3 34.6 - 47.6 A Cs-137 pCi/L 84.8 78.4 70.6 - 88.9 A Co-60 pCi/L 108 102 91.8 -114 A Zn-65 pCi/L 226 214 193 - 251 A Gr-A pCi/L 38.9 62.7 32.9 - 77.8 A Gr-B pCi/L 41.9 39.2 26.0 - 46.7 A 1-131 pCi/L 24.1 26.6 22.1 - 31.3 A U-Nat pCi/L 4.68 4.64 3.39 - 5.68 A H-3 pCi/L 7720 7840 6790 - 8620 A November 2016 RAD-107 Water Sr-89 pCi/L 43.0 43.3 33.4-50.5 A Sr-90 pCi/L 30.0 33.6 24.6-38.8 A 8a-133 pCi/L 47.8 54.9 45.4-60.7 A Cs-134 pCi/L 72.9 81.8 67.0-90.0 A Cs-137 pCi/L 189 210 189-233 A Co-60 pCi/L 58.4 64.5 58.0-73.4 A Zn-65 pCilL 243 245 220-287 A Gr-A pCi/L 37.2 68.4 35.9-84.5 A Gr-B pCi/L 35.1 33.9 22.1-41.6 A 1-131 pCi/L 23.5 26.3 21.9-31.0 A U-Nat pCi/L 49.2 51.2 41.6-56.9 A H-3 pCi/L 918 9820 8540-10800 N(5)

MRAD-25 AP Gr-A pCi/Filter 56.8 71.2 23.9-111 A (a) Teledyne Brown Engineering reported result.

(b) The ERA known value Is equal to 100% of the parameter present In the standard as determined by gravimetric ancVor

...-olumetric measurements made during standard preparation.

(c) ERA evaluation: A=acceptabIe. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.

(5) NCR 16-34 was initiated 4 ?-Y* Sd "~h