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Transmittal of 2015 Annual Radiological Environmental Operating Report (AREOR)
	ML16109A273
Person / Time
Site:	Grand Gulf
Issue date:	04/19/2016
From:	Nadeau J; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GNRO-2016/00019
	Download: ML16109A273 (84)
	v • d • e

'"'P 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-2016/00019 April 19, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Grand Gulf Nuclear Station 2015 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 Unit 1 Technical Specification 5.6.2, attached is the Annual Radiological Environmental Operating Report (AREOR) for the time period of January 1, 2015 through December 31, 2015.

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.

Sincerely, JJN/tmc cI~A

Attachment:

Grand Gulf Nuclear Station 2015 Annual Radiological Environmental Operating Report (AREOR) cc: (see next page)

GNRO-2016/00019 Page 2 of 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Marc Dapas (w/2)

Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission ATTN: Mr. James Kim, NRR/DORL (w/2)

Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2738 Mr. B. J. Smith Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health P.O. Box 1700 Jackson, MS 39205 Dr. Mary Currier, M.D., M.P.H State Health Officer Mississippi Department of Health P.O. Box 1700 Jackson, MS 39205-1700

Attachment 1 to GNRO-2016/00019 Grand Gulf Nuclear Station 2015 Annual Radiological Environmental Operating Report (AREOR)

ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1, 2015 - December 31, 2015

~Ur Prepared By Reviewed By

/ L/_I'I_lb

. Approved By

TABLE OF CONTENTS

SUMMARY

6

1.0 INTRODUCTION

10 1.1 Radiological Environmental Monitoring Program 10 1.2 Pathways Monitored 10 1.3 Land Use Census 10 2.0 INTERPRETATION AND TRENDS OF RESULTS 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

LIST OF TABLES TABLE 1.1 AIR SAMPLING DEVIATIONS IN 2015 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

3

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 39

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, 2015, through December 31, 2015. 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 2015, 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 2015 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.

Radioactivity 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 2015, the GGNS REMP detected no radioactivity attributable to other sources.

Comparison to Federal and State Programs 6

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 2015 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 2015, 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 2015 were within the limits for all samples.

Thermoluminescent Dosimeters There were no deviations in 2015.

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.

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Table 1.1 Air Sampling Deviations in 2014 Run Time Out-of-Service Sample Location Date In Date Out (Hours) (Hours) Comments AS-7 UH 01/06/15 01/13/15 166.05 2.03 Power outage AS-7 UH 01/20/15 01/27/15 165.44 2.39 Power outage AS-7 UH 03/03/15 03/10/15 165.10 0.68 Power outage AS-7 UH 03/31/15 04/07/15 169.67 2.15 Power outage AS-7 UH 04/21/15 04/28/15 170.55 2.22 Power outage AS-7 UH 04/28/15 05/05/15 160.28 2.80 Power outage AS-361VA 06/09/15 06/16/15 130.46 37.31 Power outage AS-7 UH 06/09/15 06/16/15 164.20 3.45 Power outage AS-361VA 06/30/15 07/07/15 165.91 1.91 Power outage AS-7UH 06/30/15 07/07/15 166.66 1.17 Power outage AS-7 UH 07/07/15 07/14/15 166.97 1.18 Power outage AS-7 UH 07/28/15 08/04/15 166.10 1.22 Power outage AS-7 UH 09/01/15 09/08/15 159.97 0.98 Power outage AS-1 PG 09/08/15 09/15/15 166.80 0.62 Power outage AS-361VA 09/22/15 09/29/15 155.62 22.21 Equipment Malfunction AS-7 UH 10/20/15 10/27/15 165.38 2.47 Power outage AS-361VA 12/08/15 12/15/15 166.49 1.56 Power outage AS-7 UH 12/08/15 12/15/15 167.00 1.17 Power outage AS-7 UH 12/22/15 12/29/15 158.86 7.26 Power outage Based on the sample collection period reductions, air samples were collected the following percentages of the available time:

AS-1 PG 99.9%

AS-361VA 99.2%

AS-7 UH 99.6%

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 No REMP modifications took place during this sampling period.

During 2015, installation of an additional air monitoring station in the vicinity of a community located within the sector having the highest calculated XlQ was approved. Meteorological data indicates that Sector L is the sector with the highest calculated XlQ at the site boundary.

Implementation of the new air sampling location will be completed in 2016. The additional 8

monitoring location will enhance the site's radiological environmental monitoring program, and will demonstrate robust compliance with the Offsite Dose Calculation Manual requirements.

Discussion of the data collected from the new location will be included in the next Annual Radiological Environmental Operating Report.

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 R41diological 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 ODCM 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 ODCM 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 ODCM. The census identifies the nearest:

1) Occupied and unoccupied residences 2 2

2) Garden of greater than 50 square meters (m ) [500 square feet (ft )]

producing broadleaf vegetation

3) Animal milked for human consumption 10

GGNS personnel conduct the land use census by:

Conducting field surveys in each meteorological sector out to five miles in order to confirm:

Nearest occupied residence

Nearest unoccupied residence

Nearest garden and approximate size

Nearest milking animal

Identifying locations on maps and aerial photographs, measuring distances to GGNS and recording results on surveillance data sheets

Comparing current land use census results to previous results from the 2012 census

Contacting the Claiborne County Agent for verification of nearest dairy animals No significant changes between the biennial land use census performed in 2012 and the most recent census performed in 2014 were identified that would require modifications to the REMP or the ODCM.

11

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 0/0.

Radioiodine Canister Continuous sampler 131; 7 days Radioiodine and Particulates operation with sample Particulate Sampler -

Airborne AS-1 PG (Sector G, Radius 5.5 collection per 7 days or as Gross beta radioactivity 1 sample from the vicinity of a Miles) - Southeast of GGNS at the required by dust loading, following filter change, community having the highest Port Gibson City Barn. whichever is more composite (by location) calculated annual average frequent for gamma isotopic; 92 ground level 0/0.

days 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, Radfus 0.5 Miles)

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

Property line, North-northeast of HWSA.

12

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 0, 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 Miles) -

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.

13

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 M-95 (Sector F, Radius 0.5 mi) - Spoils Area, fence of old storage area, near entrance gate M-96 (Sector B, Radius 0.7 mi.) - North Gate Fence TLDs M-97 (Sector D, Radius 0.8 mi.) - Grand An inner ring of stations in the Gulf Road entrance gate to spoils area Direct general areas of the SITE 92 days Gamma dose; 92 days Radiation M-98 (Sector H, Radius 0.5 mi.) - Bald 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 TLDs 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.

14

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 D, Radius 5.0 Miles) -

Near Ingelside Karnac 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-Ol (Sector E, Radius 3.5 Miles)-

Across the road from Lake Claiborne 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 Barn.

serve as control stations. (Special Interest)

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

Warner Tully V-Camp. (Special Interest)

M-l0 (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, Radius 1.6 Miles) -

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

MRDOWN (Sector P, Radius 1.3 Miles) - 366 days Gamma isotopic and 1 sample downstream during a Downstream of the GGNS discharge point in tritium analyses; 366 Liquid Radwaste Discharge.

the Mississippi River near Radial Well No.5. days 1 sample from Outfall 007 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 the Groundwater five wells.

Gamma isotopic and Waterborne 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 well.

SEDHAM (Sector N, Radius 1.6 Sediment From Shoreline Miles) - Downstream of the GGNS 1 sample from downstream discharge 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 Currently, no available milking animals within 8 km (5 miles) animals within 8 km of GGNS.

if milk is available commercially. AlCONT (Sector K, Radius 10.5 Gamma isotopic and 1-131; Ingestion 92 days when required Miles) - Located South-southwest of 92 days 1 control sample (only if GGNS at Alcorn State University.

indicator exists) >8 km if milk is available.

18

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 Ingestion 1 sample of broadleaf 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 1-131; average ground level D/Q if 92 days when available Miles) - Alcorn State University 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 milk km distant.

sampling is not performed.

19

Figure 1-1 Exposure Pathways 20

FIGURE 1-2 SAMPLE COLLECTION SITES - NEAR FIELD FIGURE 3.0-1 Collection Site Locations Q-4 Mile Area Map LEGEND P FISh o MSampIer o Surface Watet 6 Ground water o Broad1eaf vegetation o Sediment OTlD

Ranney Wells

$-MiIk

~~

ENIERGY GRANO GUlF NUClEAR STA110N Q-4 Mile EnvIn:mJentaI

~ LacsIIon Map I .5 0 1

~ !

SCALE IN MILES Grand GLdf. IAlIt 1 3.0-7 Rm<Isian sa /11 21

FIGURE 1-3 SAMPLE COLLECTION SITES - FAR FIELD FIGURE 3.0-2 Q

~N) Collection Site Locations, General Area Map c~

4-10 Mile Area Map LEGEND o /ldr~ 0 aJltamWIilBr o A. 0n:Iutld Wits

SdnIrrI Ramey weIs

~

0 no BtoIdsiIf'IegetaIIan

."'1)(

E tij 18 MILES FROM BfWI) eutF 10

~ ~RPORT 8IlcIaIr (B)

G(5E)

EHTERGY GRAND GULF NlJQ.EAR STAllON

+-10 Mile Environmental L \ " t I/IjI

' , Samplng lJJca1Ion Map lSVt1 Qoand Gul. Unlt1 3.0-8 REWtslon 35 0007 22

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 Chernobyl 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 2015.

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.

23

Figure 2-1 2015 TLD Readings mRlqtr 20.0 16.0 2010-2014 Control Location x

Maximum

(+2 Stdev)

~ A o 0 ~ 2010-2014 o Control 8.0 Location Minimum

(-2 Stdev) 4.0 .0

+1Q15 o2Q15 63Q15 x4Q15 0.0 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 February (5280 +/- 961 pCi/L), April (950 +/- 554 pCi/L), October (607 +/- 339 pCi/L), and December (449 +/- 280 pCi/L) at the Outfall 007 (indicator) location. Duplicate samples from Outfall 007 during February (5090 +/- 950 pCi/L) and April (1200 +/- 586 pCi/L) showed similar tritium activity. Tritium was not observed in the remaining Outfall 007 samples collected during 2015.

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.

24

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.

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 or tritium 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 Results 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 2014 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 25

2) nearest location of dairy production

3) nearest location of gardens Changes from the previous Land Use Census were evaluated in accordance with GGNS surveillance "Land Use Census", 06-EN-SOOO-O-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 ODCM were determined 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 Although not procedurally required, it is recommended that the next ODCM revision include an update to Table 2.2-3 to reflect the latest Land Use Census results.

26

Table 2.1 2014 Land Use Census Parameter Sector A* Sector B Sector C* Sector 0*

I. Nearest Occupied a. Distance (mile) 1.76 1.51 0.70 2.60 Residence b. Degrees from true north 351.6 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 4.53 3.06 Garden b. Garden size (ft2) =400 = 4050 =25 = 1200

c. Degrees from true north 355.4 21.9 49.1 58.8 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 No Yes' No No garden in same location as last census?

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

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

Table 2.1 2014 land Use Census, continued.

Parameter Sector E Sector F* Sector G* Sector H I. Nearest Occupied a. Distance (miles) 0.89 2.25 3.72 1.10 Residence b. Degrees from true north 86.9 101.3 134.1 151.4 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 4.50 4.20 4.39 Garden b. Garden size (ft2) :::: 1000 ::::450 :::: 1600 ::::200

c. Degrees from true north 86.9 110.0 130.1 155.0 1

V. Census Comparison a. Is nearest occupied Yes Yes No 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 No Yes in same location as last census?

1 - Nearest occupied residence location is the same as last census. Location data revised due to new mapping method.

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

Table 2.1 2014 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 2014 Land Use Census, continued.

Parameter Sector N Sector P Sector Q Sector R I. Nearest Occupied a. Distance (miles) None None None 1.11 Residence b. Degrees from true north 346.1 II. Nearest Unoccupied a. Distance (miles) None None None None Residence (closer b. Degrees from true north 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 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 N/A N/A N/A N/A garden in same location as last census?

30

2014 Land Use Census Changes SECTOR PARAMETER Reason for Change Nearest occupied residence from 2012 census no longer occupied.

A Nearest Occupied Residence New nearest occupied residence identified in 2014.

No garden location identified in 2012 census. New garden location A Nearest Broadleaf Garden identified in 2014.

Garden location identified in 2012 census no longer planted. New C Nearest Broadleaf Garden nearest garden location identified in 2014.

0 Nearest Broadleaf Garden New nearest garden location identified in 2014.

Nearest occupied residence is the same as previous census.

E Nearest Occupied Residence Location data revised due to new mapping method.

F Nearest Broadleaf Garden New nearest garden location identified in 2014.

Nearest occupied residence from 2012 census no longer occupied.

G Nearest Occupied Residence New nearest occupied residence identified in 2014.

Nearest garden location from 2012 census no longer planted. New G Nearest Broadleaf Garden nearest garden location identified in 2014.

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

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.

33

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 2015 Sample Type Type & Number LLDb Indicator Locations Location with Highest Annual Mean Control Number of

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

[Range] Mean (F) c Results e

[ Range]

Mean (F) c Location d [Range]

Air Particulates GB 156 0.01 0.0172 (104/104) AS-1 PG 0.01779 (52/52) 0.0175 (52/52) 0

[0.00535 - 0.0280] (Sector G, 5.5 mi) [0.00535-0.0276] [0.0051-0.0273]

(pCilm3 )

GS 12 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 (pCilm 3)

~.

Inner Ring TLDs Gamma 56 f 9.6 (56/56) M-99 12.8 (4/4) N/A 0 (mRlQtr) [4.3 -14.2] (Sector J, 0.4 mi.) [11.9 -14.2]

Outer Ring TLDs Gamma 28 f 9.5 (28/28) M-57 11.8 ( 4/4) N/A 0 (mRlQtr) [4.5 - 12.2] (Sector F, 4.5 mi.) [11.4 - 12.1]

Special Interest Gamma 28 f 9.6 (28/28) M-01 11.8 (4/4) N/A 0 TLDs [8.1 - 12.2] (Sector E, 3.5 mi.) [11.4 - 12.2]

(mRlQtr)

Control TLDs Gamma 4 f N/A N/A N/A 10.8 (4/4) 0 (mRlQtr) [10.0 - 11.2]

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 2015 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 [ Range]

Surface Water H-3 32 3000 2263 (6/26) Outfall 007 2263 (6/18) <LLD 0

( pCill ) [449 - 5280] (Sector N, Radius 0.2 mi.) [449 - 5280]

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 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 0 Ba-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A 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 2015 Sample Type Type & LLOb Indicator Locations Location with Highest Annual Mean Control Locations Number of

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

Groundwater H-3 5 2000 <LLD N/A N/A <LLD 0

( pCi/l )

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-50 15 <LLD N/A N/A <LLD 0 Zn-55 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 Ba-140 50 <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 2015 Sample Type Type & LLOb 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]

I Mean ( F) c Location d [ Range]

Fish GS 2

( pCilkg ) 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 N/A <LLD 0 Food 1-131 8 60 <LLD N/A N/A <LLD 0 ProductsNegetation

( pCilkg ) GS 8 Cs-134 60 <LLD N/A N/A <LLD 0 Cs-137 80 <LLD N/A N/A <LLD 0

-l 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 2015 Location with Highest Annual Mean Control Indicator Location Locations Number of Sample Type Type & Number Mean (F) c Mean (F) c Mean ( F) c Nonroutine

( Units) of Analyses a LLOb [ Range] Location d [Range] [Range] Results e Surface Water GS 4 (Special) Mn-54 15 <LLD N/A N/A <LLD 0

( pCill ) 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 0 Ba-140 60 <LLD N/A N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD 0 a GB = Gross beta; 1-131 = lodine-131; H-3 = Tritium; GS = Gamma scan.

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

38

Attachment 1 Radiological Monitoring Report Summary of Monitoring Results 39

TABLE OF CONTENTS TABLE A1.1 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-1 PG 41 TABLE A 1.2 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-3 61VA 43 TABLE A 1.3 AIR PARTICULATE FILTER GROSS BETA AND CHARCOAL CARTRIDGE AS-7 UH 45 TABLE A 1.4 AIR PARTICULATE FILTER GAMMA 47 TABLE A 2.1 THERMOLUMINESCENT DOSIMETERS 48 TABLE A2.2 THERMOLUMINESCENT DOSIMETERS 49 TABLE A2.3 THERMOLUMINESCENT DOSIMETERS 49 TABLE A 3.1 SURFACE WATER GAMMA 50 TABLE A3.2 SURFACE WATER TRITIUM 51 TABLE A 4.1 GROUNDWATER GAMMA 52 TABLE A4.2 GROUNDWATER TRITIUM 53 TABLE A4.3 GROUNDWATER IODINE-131 54 TABLE A 5.1 SEDIMENT 55 TABLE A 6.1 FISH 56 TABLE A 7.1 FOOD PRODUCTS 57 TABLE A 8.1 SPECIAL SAMPLES 58 TABLE A 9.1 INTERLABORATORY PROGRAM - TLDS (14 PAGES)

TABLE A9.2 INTERLABORATORY PROGRAMS - SAMPLES (7 PAGES) 40

Table Al.l Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCi/m3 AIR SAMPLE AS-l PG LLD (pCi/m3) 0.07 0.01 LABID START DATE END DATE 1-131 GROSS BETA L61599-1/4 12/30/14 01/06/15 <0.04997 0.01960 +/-0.00357 L61733-1/4 01/06/15 01/13/15 <0.04536 0.02190 +/-0.00391 L61809-1/4 01/13/15 01/20/15 <0.05241 0.02240 +/-0.00383 L61916-1/4 01/20/15 01/27/15 <0.05868 0.01810 +/-0.00341 L62010-1/4 01/27/15 02/03/15 <0.05293 0.01920 +/-0.00342 L62084-1/4 02/03/15 02/10/15 <0.05899 0.02760 +/-0.00417 L62140-1/4 02/10/15 02/16/15 <0.03465 0.02380 +/-0.0041 L62223-1/4 02/16/15 02/24/15 <0.05227 0.02010 +/-0.0033 L62301-1/4 02/24/15 03/03/15 <0.06146 0.02070 +/-0.00364 L62369-1/4 03/03/15 03/10/15 <0.03657 0.01470 +/-0.00317 L62445-1/4 03/10/15 03/17/15 <0.05801 0.00868 +/-0.00271 L62533-1/4 03/17/15 03/24/15 <0.0492 0.01760 +/-0.00343 L62626-1/4 03/24/15 03/31/15 <0.05153 0.01490 +/-0.00331 L62742-1/4 03/31/15 04/07/15 <0.0428 0.01770 +/-0.00346 L62826-1/4 04/07/15 04/14/15 <0.05923 0.01500 +/-0.00324 L62920-1/4 04/14/15 04/21/15 <0.03069 0.00766 +/-0.00262 L63084-1/4 04/21/15 04/28/15 <0.04648 0.01570 +/-0.00328 L63140-1/4 04/28/15 05/05/15 <0.05171 0.01950 +/-0.00336 L63240-1/4 05/05/15 05/12/15 <0.03923 0.01750 +/-0.00318 L63338-1/4 05/12/15 05/19/15 <0.04185 0.01280 +/-0.00319 L63432-1/4 05/19/15 OS/26/15 <0.01745 0.01410 +/-0.00321 L63525-1/4 OS/26/15 06/02/15 <0.03267 0.01150 +/-0.00319 L63626-1/4 06/02/15 06/09/15 <0.02177 0.02280 +/-0.00404 L63729-1/4 06/09/15 06/16/15 <0.05543 0.01380 +/-0.0031 L63867-1/4 06/16/15 06/23/15 <0.06472 0.02160 +/-0.00375 L63906-1/4 06/23/15 06/30/15 <0.06786 0.01330 +/-0.00307 L63992-1/4 06/30/15 07/07/15 <0.0477 0.01390 +/-0.00306 L64149-1/4 07/07/15 07/14/15 <0.05783 0.01880 +/-0.00333 L64283-1/4 07/14/15 07/21/15 <0.05458 0.01640 +/-0.00328 L64303-1/4 07/21/15 07/28/15 <0.06074 0.01980 +/-0.00357 L64409-1/4 07/28/15 08/04/15 <0.06292 0.02330 +/-0.00391 L64500-1/4 08/04/15 08/11/15 <0.04584 0.02400 +/-0.00382 L64614-1/4 08/11/15 08/18/15 <0.05042 0.01580 +/-0.00309 L64658-1/4 08/18/15 08/25/15 <0.04001 0.01180 +/-0.00313 L64770-1/4 08/25/15 09/01/15 <0.06471 0.02460 +/-0.00377 41

Table A1.1 Sample Type: Air Particulate Filter and Radioiodine Cartridge Analysis: Gross Beta and 1-131 Units: pCilm3 AIR SAMPLE AS-1 PG LLD (pCilm3) 0.07 0.01 LAB 10 START DATE END DATE 1-131 GROSS BETA L64856-1/4 09/01/15 . . 09/08/15 <0.05645 0.02710 +/-0.00411 L64946-1/4 09/08/15 09/15/15 <0.04999 0.02020 +/-0.00359 L65032-1/4 09/15/15 09/22/15 <0.05491 0.02390 +/-0.00393 L65136-1/4 09/22/15 09/29/15 <0.03989 0.01920 +/-0.00353 L65243-1/4 09/29/15 10/06/15 <0.02673 0.01230 +/-0.0029 L65340-1/4 10/06/15 10/13/15 <0.05476 0.02760 +/-0.00396 L65499-1/4 10/13/15 10/20/15 <0.06206 0.02270 +/-0.00398 L65551-1/4 10/20/15 10/27/15 <0.03386 0.01120 +/-0.00279 L65669-1/4 10/27/15 11/03/15 <0.03082 0.01600 +/-0.00385 L65765-1/4 11/03/15 11/10/15 <0.06763 0.01420 +/-0.00309 L65830-1/4 11/10/15 11/17/15 <0.05215 0.01580 +/-0.00336 L65909-1/4 11/17/15 11/24/15 <0.02428 0.02040 +/-0.00383 L65959-1/4 11/24/15 12/01/15 <0.04273 0.00766 +/-0.00285 L66076-1/4 12/01/15 12/08/15 <0.02887 0.02550 +/-0.00389 L66152-1/4 12/08/15 12/15/15 <0.02851 0.02220 +/-0.00368 L66241-1/4 12/15/15 12/22/15 <0.05834 0.01330 +/-0.00309 L66284-1/4 12/22/15 12/29/15 <0.06672 0.00535 +/-0.00255 Average: 0.01779 Maximum: 0.02760 Minimum: 0.00535 42

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 L61599-2/5 12/30/14 01/06/15 <0.05007 0.0191 +/-0.0036 L61733-2/5 01/06/15 01/13/15 <0.04543 0.0211 +/-0.0039 L61809-2/5 01/13/15 01/20/15 <0.05258 0.0239 +/-0.0039 L61916-2/5 01/20/15 01/27/15 <0.05879 0.0175 +/-0.0034 L62010-2/5 01/27/15 02/03/15 <0.05298 0.0187 +/-0.0034 L62084-2/5 02/03/15 02/10/15 <0.0591 0.0258 +/-0.0041 L62140-2/5 02/10/15 02/16/15 <0.03438 0.0223 +/-0.0040 L62223-2/5 02/16/15 02/24/15 <0.05264 0.0213 +/-0.0034 L62301-2/5 02/24/15 03/03/15 <0.02729 0.0216 +/-0.0037 L62369-2/5 03/03/15 03/10/15 <0.03664 0.0124 +/-0.0030 L62445-2/5 03/10/15 03/17/15 <0.02439 0.0087 +/-0.0027 L62533-2/5 03/17/15 03/24/15 <0.04929 0.0134 +/-0.0031 L62626-2/5 03/24/15 03/31/15 <0.05172 0.0118 +/-0.0031 L62742-2/5 03/31/15 04/07/15 <0.04317 0.0170 +/-0.0034 L62826-2/5 04/07/15 04/14/15 <0.05911 0.0100 +/-0.0028 L62920-2/5 04/14/15 04/21/15 <0.03075 0.0085 +/-0.0027 L63084-2/5 04/21/15 04/28/15 <0.04839 0.0152 +/-0.0033 L63140-2/5 04/28/15 05/05/15 <0.05074 0.0170 +/-0.0031 L63240-2/5 05/05/15 05/12/15 <0.03942 0.0159 +/-0.0031 L63338-2/5 05/12/15 05/19/15 <0.04182 0.0103 +/-0.0030 L63432-2/5 05/19/15 OS/26/15 <0.04963 0.0094 +/-0.0029 L63525-2/5 OS/26/15 06/02/15 <0.03319 0.0103 +/-0.0031 L63626-2/5 06/02/15 06/09/15 <0.008403 0.0219 +/-0.0040 L63729-2/5 06/09/15 06/16/15 <0.06907 0.0201 +/-0.0042 L63867-2/5 06/16/15 06/23/15 <0.06487 0.0178 +/-0.0035 L63906-2/5 06/23/15 06/30/15 <0.06799 0.0145 +/-0.0032 L63992-2/5 06/30/15 07/07/15 <0.04834 0.0127 +/-0.0030 L64149-2/5 07/07/15 07/14/15 <0.05795 0.0170 +/-0.0032 L64283-2/5 07/14/15 07/21/15 <0.05468 0.0194 +/-0.0035 L64303-2/5 07/21/15 07/28/15 <0.06108 0.0196 +/-0.0036 L64409-2/5 07/28/15 08/04/15 <0.02639 0.0230 +/-0.0039 L64500-2/5 08/04/15 08/11/15 <0.04588 0.0211 +/-0.0036 L64614-2/5 08/11/15 08/18/15 <0.04804 0.0159 +/-0.0030 L64658-2/5 08/18/15 08/25/15 <0.04198 0.0100 +/-0.0031 43

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 LASID START DATE END DATE 1*131 GROSS BETA L64770-2/5 08/25/15 09/01/15 <0.06832 0.0252 +/-0.0039 L64856-2/5 09/01/15 09/08/15 <0.05467 0.0272 +/-0.0040 L64946-2/5 09/08/15 09/15/15 <0.04985 0.0184 +/-0.0035 L65032-2/5 09/15/15 09/22/15 <0.05515 0.0246 +/-0.0040 L65136-2/5 09/22/15 09/29/15 <0.04228 0.0205 +/-0.0038 L65243-2/5 09/29/15 10/06/15 <0.02796 0.0224 +/-0.0038 L65340-2/5 10/06/15 10/13/15 <0.05547 0.0271 +/-0.0040 L65499-2/5 10/13/15 10/20/15 <0.0613 0.0206 +/-0.0038 L65551-2/5 10/20/15 10/27/15 <0.03455 0.0117 +/-0.0029 L65669-2/5 10/27/15 11/03/15 <0.03101 0.0167 +/-0.0039 L65765-2/5 11/03/15 11/10/15 <0.06728 0.0158 +/-0.0032 L65830-2/5 11/10/15 11/17/15 <0.05224 0.0178 +/-0.0035 L65909-2/5 11/17/15 11/24/15 <0.06365 0.0178 +/-0.0037 L65959-2/5 11/24/15 12/01/15 <0.04241 0.0094 +/-0.0030 L66076-2/5 12/01/15 12/08/15 <0.02893 0.0273 +/-0.0040 L66152-2/5 12/08/15 12/15/15 <0.06884 0.0218 +/-0.0037 L66241-2/5 12/15/15 12/22/15 <0.05836 0.0161 +/-0.0033 L66284-2/5 12/22/15 12/29/15 <0.06696 0.0051 +/-0.0025 Average: 0.0175 Maximum: 0.0273 Minimum: 0.0051 44

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 LASID START DATE END DATE 1-131 GROSS BETA L61599-3/6 12/30/14 01/06/15 <0.04989 0.0228 +/-0.0038 L61733-3/6 01/06/15 01/13/15 <0.04588 0.0204 +/-0.0038 L61809-3/6 01/13/15 01/20/15 <0.05232 0.0218 +/-0.0038 L61916-3/6 01/20/15 01/27/15 <0.05948 0.0202 +/-0.0036 L62010-3/6 01/27/15 02/03/15 <0.05291 0.0176 +/-0.0033 L62084-3/6 02/03/15 02/10/15 <0.05893 0.0240 +/-0.0040 L62140-3/6 02/10/15 02/16/15 <0.03463 0.0224 +/-0.0040 L62223-3/6 02/16/15 02/24/15 <0.05218 0.0188 +/-0.0032 L62301-3/6 02/24/15 03/03/15 <0.06145 0.0199 +/-0.0036 L62369-3/6 03/03/15 03/10/15 <0.03669 0.0138 +/-0.0031 L62445-3/6 03/10/15 03/17/15 <0.05793 0.0071 +/-0.0026 L62533-3/6 03/17/15 03/24/15 <0.04914 0.0113 +/-0.0030 L62626-3/6 03/24/15 03/31/15 <0.02161 0.0143 +/-0.0033 L62742-3/6 03/31/15 04/07/15 <0.04321 0.0158 +/-0.0034 L62826-3/6 04/07/15 04/14/15 <0.05927 0.0093 +/-0.0028 L62920-3/6 04/14/15 04/21/15 <0.03065 0.0086 +/-0.0027 L63084-3/6 04/21/15 04/28/15 <0.04704 0.0140 +/-0.0032 L63140-3/6 04/28/15 05/05/15 <0.05257 0.0179 +/-0.0033 L63240-3/6 05/05/15 05/12/15 <0.03919 0.0143 +/-0.0029 L63338-3/6 05/12/15 05/19/15 <0.04178 0.0125 +/-0.0032 L63432-3/6 05/19/15 OS/26/15 <0.04948 0.0085 +/-0.0028 L63525-3/6 OS/26/15 06/02/15 <0.03258 0.0101 +/-0.0031 L63626-3/6 06/02/15 06/09/15 <0.02177 0.0184 +/-0.0038 L63729-3/6 06/09/15 06/16/15 <0.05656 0.0191 +/-0.0036 L63867-3/6 06/16/15 06/23/15 <0.06463 0.0185 +/-0.0035 L63906-3/6 06/23/15 06/30/15 <0.06782 0.0098 +/-0.0028 L63992-3/6 06/30/15 07/07/15 <0.015 0.0129 +/-0.0030 L64149-3/6 07/07/15 07/14/15 <0.05819 0.0137 +/-0.0030 L64283-3/6 07/14/15 07/21/15 <0.05452 0.0166 +/-0.0033 L64303-3/6 07/21/15 07/28/15 <0.06046 0.0167 +/-0.0034 L64409-3/6 07/28/15 08/04/15 <0.06344 0.0240 +/-0.0040 L64500-3/6 08/04/15 08/11/15 <0.01776 0.0221 +/-0.0037 L64614-3/6 08/11/15 08/18/15 <0.05066 0.0165 +/-0.0032 L64658-3/6 08/18/15 08/25/15 <0.04008 0.0132 +/-0.0032 L64770-3/6 08/25/15 09/01/15" <0.02504 0.0280 +/-0.0040 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 L64856-3/6 09/01/15 09/08/15 <0.05673 0.0228 +/-0.0038 L64946-3/6 09/08/15 09/15/15 <0.04977 0.0186 +/-0.0035 L65032-3/6 09/15/15 09/22/15 <0.05486 0.0245 +/-0.0040 L65136-3/6 09/22/15 09/29/15 <0.0398 0.0197 +/-0.0036 L65243-3/6 09/29/15 10/06/15 <0.02672 0.0124 +/-0.0029 L65340-3/6 10/06/15 10/13/15 <0.02304 0.0279 +/-0.0040 L65499-3/6 10/13/15 10/20/15 <0.0623 0.0213 +/-0.0039 L65551-3/6 10/20/15 10/27/15 <0.03444 0.0098 +/-0.0027 L65669-3/6 10/27/15 11/03/15 <0.03054 0.0126 +/-0.0036 L65765-3/6 11/03/15 11/10/15 <0.06777 0.0158 +/-0.0032 L65830-3/6 11/10/15 11/17/15 <0.05212 0.0174 +/-0.0035 L65909-3/6 11/17/15 11/24/15 <0.06299 0.0143 +/-0.0034 L65959-3/6 11/24/15 12/01/15 <0.04247 0.0071 +/-0.0028 L66076-3/6 12/01/15 12/08/15 <0.02886 0.0235 +/-0.0038 L66152-3/6 12/08/15 12/15/15 <0.06843 0.0203 +/-0.0036 L66241-3/6 12/15/15 12/22/15 <0.0583 0.0154 +/-0.0033 L66284-3/6 12/22/15 12/29/15 <0.06972 0.0060 +/-0.0027 Average: 0.0166 Maximum: 0.0280 Minimum: 0.0060 46

Table A1.4 Sample Type: Air Particulate Filter Analysis: Gamma Isotopic Units: pCi/m3 AIR PARTICULATE FILTER SAMPLES (GAMMA)

LLD (pCi/m3) 0.05 0.06 LASlO LOCATION DATE CS-134 CS-137 L62771-1 AS-1 PG 02/13/15 <0.002665 <0.002108 L62771-2 AS-361VA 02/13/15 <0.002512 <0.002137 L62771-3 AS-7 UH 02/13/15 <0.002694 <0.002222 L64087-1 AS-1 PG 05/15/15 <0.003325 <0.002582 L64087-2 AS-361VA 05/15/15 <0.001724 <0.002033 L64087-3 AS-7 UH 05/15/15 <0.003231 <0.002898 L65183-1 AS-1 PG 08/14/15 <0.002141 <0.002077 L65183-2 AS-361VA 08/15/15 <0.001331 <0.001341 L65183-3 AS-7 UH 08/14/15 <0.001891 <0.002219 L66362-1 AS-1 PG 11/13/15 <0.002132 <0.001742 L66362-2 AS-361VA 11/13/15 <0.003417 <0.003152 L66362-3 AS-7 UH 11/13/15 <0.002692 <0.001344 47

Table A 2.1 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose Units: mrem/Qtr Inner Ring - Within General Area of Site Boundary Station 1st atr 2nd atr 3rd atr 4th atr Annual Mean M-16 10.3 10.3 11.2 11.0 10.7 M-19 9.1 9.2 9.9 10.1 9.6

.., **************",***1-****** ,........... . <. . ... .. . .. . .. . . .. .. ~

M-21

~~"~~,.~".~ ..,,, ,'"", . 11.4 _ --t ~_ _~. ~:. ~ -- w.~"L .. 11.8

....y *** " ** "~' " w.' ,*., ,, .. " *.* *.,.*.. :-. .* w .. ~ * **** " "

13.4

.,.... ~ " *. , _. '.* .. **.o>.*.*., **..** d '.

11.9 M-22 7.6 7.6 8.8 9.6 8.4 M-23 7.3 7.2 5.8 9.0 7.4 M-25 7.6 4.3 8.1 8.6 7.2 M-28 10.3 10.4 11.2 11.8 10.9

.* ~, .*. ,.~'M"~"Y .**.,.. ~, *.. ,~ ... ,~,. "'~,~~"~, .* ~.~.,~~~,.~~~,~w.~,~,, .. ~ " .., ~".~.~ '~.~ *.~" ~ ,.".-. , , " ,. .' .....' ... " ...*." .*...

' ~

M-94 10.7 9.2 10.7 11.0 10.4

.. . ~ .-} . ._ ; .

M-95 6.3 i 7.0 6.2 7.5 6.8 M-96 7.4 7.3 7.6 8.3 7.6 M-97 7.8 7.7 7.1 7.6 7.6 M-98 11.8 11.4 12.0 11.9 11.8 M-99* 12.6 11.9 14.2 12.7 12.8 M-100 11.0 I 10.1 11.3 11.8 11.1

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 Annual Mean

!......, ._ .. ~~,~~... . .... ~ .. w . . .__

__. . . . . . . . . ?:.~_._. . ...~." = ~ "

8.2 8.3

.........*.** ,.*

w .* ~ ,,~ .".w "~ ~ ,,

8.4

. .~ "

8.2

.. w .. * ..

M-40 4.9 4.5 4.8 5.4 4.9 M-48 9.1 9.3 9.9 10.6 9.7 M-49 10.2 10.8 11.3 12.2 11.1 M-50 9.2 9.3 9.9 9.8 9.6

,." .. " , , ."., y "~ , . " .. ".,.~"." " " " ** ~ ................................... ~... , , . . . . . .*~ ........w.w..... " . , , ,............*.,, ....., , .". ., ...,* .... *.w.. y... ...

~ "~.~,,,.y.y.,* ... w., .. w ...*.*., .. "y ...." ....

".*.*M~.~.*~" ...." .. ,... ,.,

M-55 11.4 10.4 11.8 11.5 11.3 M-57* 11.5 11.4 12.1 12.1 11.8

Location with highest annual mean 48

Table A 2.2 Sample Type: Thermoluminescent Dosimeters Analysis: Gamma Dose

. Units: mrem/Qtr Special Interest Areas - Population Centers & Schools Station 1st atr 2nd atr 3rd Otr 4th atr Annual Mean M-01* 11.5 11.4 11.9 12.2 11.8 M-07 10.3 9.5 10.3 10.8 10.2 M-09 9.7 9.0 9.7 10.8 9.8

... ", ..... ~ ............

M-10 9.0 8.4 8.7 9.4 8.9 M-33 8.1 8.3 8.7 8.5 8.4 M-38 9.0 8.3 9.9 10.0 9.3 M-39 8.5 8.7 9.1 9.6 9.0

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 10.9 10.0 10.9 11.2 10.8 49

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

LLD (pCilL) 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 L62109-1 MRDOWN 02/10/15 <5.768 <6.045 <13.38 <6.275 <11.82 <6.44 <9.982 <14.74 <4.895 <5.919 <40.61 <12.8 L62109-3 MRUP 02/10/15 <3.257 <3.935 <8.441 <4.424 <8.312 <4.402 <8 <13.29 <3.738 <3.456 <28.03 <8.488 L63181-1 MRDOWN 05/07/15 <3.695 <4.034 <8.489 <4.172 <8.4 <3.804 <7.878 <11.76 <3.713 <4.078 <26.27 <8.839 L63181-3 MRUP 05/07/15 <4 <3.468 <8.245 <4.244 <8.519 <3.9 <7.461 <11.65 <4.195 <4.049 <25.76 <9.071 L63181-5 MRDOWN GG 05/07/15 <4.52 <4.657 <10.16 <5.387 <8.821 <5.095 <8.773 <11.36 <4.273 <4.682 <30.02 <9.097 L63181-7 MRUP GG 05/07/15 <3.397 <4.017 <7.492 <3.623 <7.885 <3.901 <7.325 <10.14 <3.36 <3.898 <23.16 <6.94 L64668-1 MRDOWN 08/26/15 <5.967 <7.661 <17.18 <8.563 <15.01 <8.014 <13.39 <13.2 <8.182 <8.487 <39.24 <11.72 L64668-3 MRUP 08/26/15 <11 <8.877 <22.01 <8.56 <16.7 <9.379 <17.75 <12.28 <9.56 <9.681 <38.45 <14.92 L65733-1 MRDOWN 11/05/15 <4.001 <4.88 <8.607 <3.616 <9.81 <5.419 <7.589 <12.1 <4.891 <4.665 <28.63 <8.372 L65733-2 MRDOWN GG 11/05/15 <3.958 <3.421 <8.705 <3.373 <7.235 <4.362 <7.398 <9.519 <3.021 <3.794 <24.17 <5.049 L65733-5 MRUP 11/05/15 <4.707 <4.18 <10.49 <5.469 <10.8 <4.893 <5.719 <12.56 <4.693 <5.339 <31.4 <8.028 L65733-6 MRUP GG 11/05/15 <5.369 <5.081 <12.32 <6.356 <10.7 <6.405 <7.882 <14.48 <5.655 <5.253 <32.5 <11 L65734-1 MRDOWN

11/06/15 <6.792 <7.568 <13.75 <7.562 <15.05 <7.409 <14.34 <10.84 <6.716 <7.91 <31.64 <10.28 L65734-3 MRDOWN GG

11/06/15 <6.149 <5.967 <12.61 <6.481 <14.5 <5.616 <11.2 <10.71 <5.374 <6.062 <26.73 <7.142 "GG" - indicates duplicate sample

Annual Sample collected during liquid discharge 50

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 L61841-1 OUTFALL 007 01/21/15 <393 L62109-2 MRDOWN 02/10/15 <577 L62109-4 MRUP 02/10/15 <573 L62141-1C1 OUTFALL 007 02/16/15 5280 +/-961 L62141-2C1 OUTFALL 007 GG 02/16/15 5090 +/-950 L62468-1 OUTFALL 007 03/17/15 <527 L62864-1 OUTFALL 007 04/15/15 950 +/-554 L62864-2 OUTFALL 007 GG 04/15/15 1200 +/-586 L63181-2 MRDOWN 05/07/15 <539 L63181-4 MRUP 05/07/15 <539 L63181-6 MRDOWN GG 05/07/15 <557 L63181-8 MRUP GG 05/07/15 <542 L63339-1 OUTFALL 007 05/19/15 <576 L63655-1 OUTFALL 007 06/10/15 <581 L63655-2 OUTFALL 007 GG 06/10/15 <585 L64010-1C1 OUTFALL 007 07/08/15 <570 L64440-1 OUTFALL 007 08/06/15 <554 L64668-2 MRDOWN 08/26/15 <598 L64668-4 MRUP 08/26/15 <598 L64790-1 OUTFALL 007 09/02/15 <382 L64790-2 OUTFALL 007 GG 09/02/15 <392 L65170-1 OUTFALL 007 09/30/15 <437 L65600-1 OUTFALL 007 10/29/15 607 +/-339 L65733-3 MRDOWN 11/05/15 <512 L65733-4 MRDOWN GG 11/05/15 <505 L65733-7 MRUP 11/05/15 <511 L65733-8 MRUP GG 11/05/15 <508 L65734-2 MRDOWN

11/06/15 <512 L65734-4 MRDOWN GG

11/06/15 <506 L65912-1 OUTFALL 007 11/24/15 <477 L65912-2 OUTFALL 007 GG 11/24/15 <475 L66227-1 OUTFALL 007 12/22/15 449 +/-280

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

51

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

LLD (pCilL) 15 15 30 15 30 15 30 15 18 60 15 LAB 10 LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 L65815-1 PGWELL 11/16/15 <8.964 <5.698 <10.43 <4.605 <15.79 <7.858 <12.46 <7.007 <8.887 <27.88 <6.487 L65815-5 CONSTWELL3 11/16/15 <5.389 <5.646 <9.286 <5.125 <10.68 <5.533 <12.89 <5.873 <6.424 <23.3 <6.182 L65815-9 CONSTWELL4 11/16/15 <5.369 <5.325 <10.35 <6.158 <15.13 <6.665 <11.89 <5.243 <5.927 <39.01 <13.12 52

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

LLD (pCi/L) 2000 LASlO LOCATION DATE H-3 L65815-3 PGWELL 11/16/15 <461 L65815-4 PGWELL GG 11/16/15 <458 L65815-7 CONSTWELL3 11/16/15 <465 L65815-8 CONSTWELL 3 GG 11/16/15 <466 L65815-11 CONSTWELL4 11/16/15 <462 L65815-12 CONSTW ELL 4 GG 11/16/15 <463 "GG" - indicates duplicate sample.

53

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

LLD (pCi/L) 1 LASID LOCATION DATE 1-131 L65815-2 PGWELL 11/16/15 <0.293 L65815-6 CONSTWELL 3 11/16/15 <0.28 L65815-10 CONSTWELL4 11/16/15 <0.3 54

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 L65751-1 SEDHAM 11/05/15 <34.47 <41.29 L65751-2 SEDCONT 11/05/15 <74.66 <78.88 L65751-3 SEDHAM GG 11/05/15 <67.28 <84.58 L65751-4 SEDCONT GG 11/05/15 <45.2 <43.31 "GG" - indicates duplicate sample.

55

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

LLD (pCilkg) 130 130 260 130 260 130 150 LASlO LOCATION DATE MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 L65167-1 FISHUP 09/24/15 <56.01 <43.59 <89.19 <42.55 <116.5 <47.55 <48.26 L65167-2 FISHDOWN 09/24/15 <63.65 <64.9 <78.64 <78.44 <150.2 <41.3 <86.93 56

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

LLD (pCilkg) 60 60 80 LASlO LOCATION DATE 1-131 CS-134 CS-137 L62519-1 VEG-CONT 03/19/15 <13.26 <6.718 <7.887 L62519-2 VEG-J 03/17/15 <49.25 <19.4 <22.02 L63651-1 VEG-CONT 06/05/15 <52.83 <20.66 <21.94 L63651-2 VEG-J 06/08/15 <49.69 <21.06 <21.98 L65137-1 VEG-CONT 09/28/15 <59.6 <25.41 <31.27 L65137-2 VEG-J 09/28/15 <49.91 <27.81 <42.83 L66045-1 VEG-CONT 12/04/15 <57.38 <29.45 <27.2 L66045-2 VEG-J 12/03/15 <54.23 <29.73 <27.87 57

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

LLD 15 15 30 15 30 15 30 15 15 18 50 15 LAB 10 LOCATION DATE MN-54 CO-58 FE-59 CO-50 ZN-55 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 L62512-1 OUTFALL 007 03/17/15 <4.157 <3.6 <8.896 <3.594 <8.021 <4.836 <6.36 <8.263 <3.716 <3.95 <19.66 <6.244 L64009-1 OUTFALL 007 06/19/15 <1.574 <1.824 <4.251 <1.679 <3.388 <1.933 <3.44 <11.84 <1.518 <1.605 <18.99 <6.489 L65134-1 OUTFALL 007 09/29/15 <6.343 <6.113 <11 <6.801 <14.54 <5.951 <12.49 <10.7 <5.015 <5.767 <29.93 <11.13 L66341-1 OUTFALL 007 12/29/15 <5.139 <5.233 <11.69 <5.215 <10.03 <5.007 <8.626 <11.73 <4.718 <5.708 <25.77 <8.199 58

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

ENVIRONMENTAL DOSIMETRY COMPANY ANNUAL QUALITY ASSURANCE STATUS REPORT January - December 2015 Prepared By:

~-~Q~-- Date: :J...@.2(16

\

Approved By:

Date: &[ffCL{ in Environme~tal Dosimetry Company 10 Ashton Lane St~rling, -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 2015 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 2015 4 VII. CONCLUSION AND RECOMMENDATIONS 4 VIII. REFERENCES 4 APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS

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LIST OF TABLES

1. Percentage of Individual Analyses Which Passed EDC Internal Criteria, January - December 2015 5

2. Mean Dosimeter Analyses (n=6), January - December 2015 5

3. Summary of Independent QC Results for 2015 5

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EXECUTIVE

SUMMARY

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

During this annual period, 100 % (72/72) of the individual dosimeters, evaluated against the EDC internal performance acceptance criteria (high-energy photons only), met the criterion for accuracy and 100% (72/72) met the criterion for precision (Table 1). In addition, 100% (12/12) of the dosimeter sets 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 assessment was performed in 2015. There were no findings.

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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 l" dosimeter (i.e., the reported exposure)

Hi = the exposure delivered to the l" 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 (i.e., the reported exposure)

Hi = the exposure delivered to the l" irradiated test dosimeter (i.e., the delivered exposure) n = the number of 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 exposure for the ith dosimeter (i.e., the reported exposure)

R = the mean reported exposure; i.e., R= IH:(~)

n = the number of dosimeters in the test group

4. EDC Internal Tolerance Limits All evaluation criteria are taken from the "EDC Quality System 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. QC Investigation 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 mean of 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 2015 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 Figures 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 co-located station results.

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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 2015. There were no findings identified.

B. External None.

VI. PROCEDURES AND MANUALS REVISED DURING JANUARY - DECEMBER 2015 Procedure 1052 was revised on December 23, 2015. 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, 2015.

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

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TABLE 1 PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2015(1), (2)

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

(2)Environmental dosimeter results are free in air.

TABLE 2 MEAN DOSIMETER ANALYSES (N=6)

JANUARY - DECEMBER 2015(1), (2) 4/16/2015 55 4.5 1.1 Pass 4/28/2015 91 2.7 1.6 Pass 05/07/2015 48 0.3 1.3 Pass 7/22/2015 28 1.5 1.4 Pass 7/24/2015 106 2.9 1.8 Pass 8/06/2015 77 -3.3 1.3 Pass 10/30/2015 28 3.7 2.2 Pass 11/04/2015 63 2.5 1.0 Pass 11/22/2015 85 -2.9 1.7 Pass 1/27/2016 61 3.1 0.9 Pass 1/31/2016 112 2.2 1.3 Pass 2/05/2016 36 3.2 1.4 Pass (1)This table summarizes results of tests conducted by EDC for TLDs issued in 2015.

(2)Environmental dosimeter results are free in air.

TABLE 3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2015(1), (2) 1$ Qtr. 2015 Millstone 2" Qtr.2015 Millstone 2" Qtr.2015 Seabrook 3r Qtr. 2015 Millstone 4 Qtr.2015 Millstone 4t Qtr.2015 Seabrook (1)Performance criteria are +/- 30%.

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

APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS ISSUE PERIOD JANAURY - DECEMBER 2015 6 of 6

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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

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 2)

Identification Reported Known Ratio (c)

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

March 2015 E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 W E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A E11184 AP Ce-141 pCi 107 85.0 1.26 W Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 Water Fe-55 pCi/L 1950 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 W Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143.0 125 1.14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 W Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1)

Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 W Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pC; 93.9 80 1.17 A

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 2)

Identification Reported Known Ratio (c)

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

June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCilL 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A E11357 AP Ce-141 pCi 89.9 84.0 1.07 A Cr-51 pCi 215 184 1.17 A Cs-134 pCi 103 105 0.98 A Cs-137 pCi 76.6 74.8 1.02 A Co-58 pCi 76.2 71.9 1.06 A Mn-54 pCi 91.4 94.4 0.97 A Fe-59 pCi 78.6 70.3 1.12 A Zn-65 pCi 173 162 1.07 A Co-60 pCi 138 139 0.99 A E11422 AP Sr-89 pCi 98.0 96.9 1.01 A Sr-90 pCi 10.0 14.0 0.71 W E11356 Charcoal 1-131 pCi 74.9 75.2 1.00 A E11358 Water Fe-55 pCi/L 2160 1710 1.26 W E11353 Soil Ce-141 pCi/kg 252 222 1.14 A Cr-51 pCi/kg 485 485 1.00 A Cs-134 pCi/kg 319 277 1.15 A Cs-137 pCi/kg 292 276 1.06 A Co-58 pCi/kg 193 190 1.02 A Mn-54 pCi/kg 258 250 1.03 A Fe-59 pCi/kg 218 186 1.17 A Zn-65 pCi/kg 457 429 1.07 A Co-60 pCi/kg 381 368 1.04 A (1) AP Cr Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error; the lowest value would be 119% of the reference value, which would be considered acceptable. NCR 15-18 (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 and/or volumetric measurements made during standard preparation.

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

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.

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

DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Acceptance Month/Year Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c)

March 2015 15-MaW32 Water Am-241 Bq/L 0.632 0.654 0.458 - 0.850 A Ni-63 Bq/L 2.5 (1) A Pu-238 Bq/L 0.0204 0.0089 (2) A Pu-239/240 Bq/L 0.9 0.8 0.582 - 1.082 A 15-MaS32 Soil Ni-63 Bq/kg 392 448.0 314 - 582 A Sr-90 Bq/kg 286 653 487 - 849 N (3) 15-RdF32 AP Sr-90 Bq/sample -0.0991 (1) A U-234/233 Bq/sample 0.0211 0.0155 0.0109 - 0.0202 N (3)

U-238 Bq/sample 0.095 0.099 0.069 - 0.129 A 15-GrF32 AP Gr-A Bq/sample 0.448 1.77 0.53 - 3.01 N (3)

Gr-B Bq/sample 0.7580 0.75 0.38 - 1.13 A 15-RdV32 Vegetation Cs-134 Bq/sample 8.08 7.32 5.12 - 9.52 A Cs-137 Bq/sample 11.6 9.18 6.43 - 11.93 W Co-57 Bq/sample -0.0096 (1) A Co-60 Bq/sample 6.53 5.55 3.89 - 7.22 A Mn-54 Bq/sample 0.0058 (1) A Sr-90 Bq/sample 0.999 1.08 0.76 - 1.40 A Zn-65 Bq/sample -0.108 (1) A September 2015 15-MaW33 Water Am-241 Bq/L 1.012 1.055 0.739 - 1.372 A Ni-63 Bq/L 11.8 8.55 5.99-11.12 N (4)

Pu-238 Bq/L 0.727 0.681 0.477 - 0.885 A Pu-239/240 Bq/L 0.830 0.900 0.630 - 1.170 A 15-MaS33 Soil Ni-63 Bq/kg 635 682 477 - 887 A Sr-90 Bq/kg 429 425 298 - 553 A 15-RdF33 AP Sr-90 Bq/sample 1.48 2.18 1.53 - 2.83 N (4)

U-234/233 Bq/sample 0.143 0.143 0.100 - 0.186 A U-238 Bq/sample 0.149 0.148 0.104 - 0.192 A 15-GrF33 AP Gr-A Bq/sample 0.497 0.90 0.27 - 1.53 A Gr-B Bq/sample 1.34 1.56 0.78 - 2.34 A 15-RdV33 Vegetation Cs-134 Bq/sample 6.10 5.80 4.06 - 7.54 A Cs-137 Bq/sample 0.0002 (1) A Co-57 Bq/sample 8.01 6.62 4.63 - 8.61 W Co-60 Bq/sample 4.97 4.56 3.19 - 5.93 A Mn-54 Bq/sample 8.33 7.68 5.38 - 9.98 A Sr-90 Bq/sample 0.386 1.30 0.91 - 1.69 N (4)

(1) False positive test. Zn-65 Bq/sample 6.07 5.46 3.82 - 7.10 A (2) Sensitivity evaluation.

(3) Soil Sr incomplete digestion of the sample resulted in low results; AP U-234/233 - extremely low activity was difficult to quantify AP Gr-A - the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21.

(a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter presem in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) DOE/MAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

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

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

May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 - 71.2 N(1)

Sr-90 pCi/L 28.0 41.9 30.8 - 48.1 N (1)

Sa-133 pCi/L 80.6 82.5 63.9 - 90.8 A Cs-134 pCi/L 71.7 75.7 61.8 - 83.3 A Cs-137 pCi/L 187 189 170 - 210 A Co-60 pCi/L 85.7 84.5 76.0 - 95.3 A Zn-65 pCi/L 197 203 183 - 238 A Gr-A pCi/L 26.1 42.6 22.1 - 54.0 A Gr-S pCi/L 28.8 32.9 21.3 - 40.6 A 1-131 pCi/L 23.5 23.8 19.7 - 28.3 A U-Nat pCi/L 6.19 6.59 4.99 - 7.83 A H-3 pCi/L 3145 3280 2770 - 3620 A MRAD-22 Filter Gr-A pCi/filter 28.3 62.2 20.8 - 96.6 A 011/01/2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 - 42.5 A Sr-90 pCi/L 29.3 31.1 22.7 - 36.1 A Sa-133 pCi/L 31.5 32.5 25.9 - 36.7 A Cs-134 pCi/L 59.65 62.3 50.6 - 68.5 A Cs-137 pCi/L 156 157 141 - 175 A Co-60 pCi/L 70.6 71.1 64.0 - 80.7 A Zn-65 pCi/L 145 126 113 - 149 A Gr-A pCi/L 38.2 51.6 26.9 - 64.7 A Gr-S' pCi/L 42.0 36.6 24.1 - 44.2 A 1-131 pCi/L 24.8 26.3 21.9 - 31.0 A U-Nat pCi/L 146.90 56.2 45.7 - 62.4 N(2)

H-3 pCi/L 21100 21300 18700 - 23400 A MRAD-23 Filter Gr-A pCi/filter Lost during processing (1) Yield on the high side of our acceptance range indicates possibility of calcium interference. NCR 15-09 (2) Technician failed to dilute original sample. If dilulted, the result would have been 57.1, which fell within the acceptance limits. NCR 15-19 (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 and/or VOlumetricmeasurements made during standard preparation.

(c) ERA evaluation: A=acceptable. 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.

For the TBE laboratory, 131 out of 139 analyses performed met the specified acceptance criteria. Eight analyses (AP - Cr-51 , U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni-3 and U natural; Vegetation Sr-90 samples) did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.20 was exceeded.

The air particulate sample is counted on a shelf (above the detector), which is the ideal geometry for this sample. But due to the fact that Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, this geometry produces a larger error for the Cr-51. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would be considered acceptable. NCR 15-18

2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. NCR 15-13

3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 Bq/sample was higher than the known value of 0.0155 Bq/sample, exceeding the upper acceptance range of 0.0202 Bq/sample. Due to the extremely low activity, it was difficult to quantify the U-234/233. Taking into consideration the uncertainty, the activity of U-234/233 overlaps with the known value, which is statistically considered the same value. NCR 15-13

4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Bq/sample was lower than the known value of 1.77 Bq/sample, exceeding the lower acceptance range of 0.53 Bq/sample. The efficiency used for gross alpha is made from a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters. NCR 15-13

5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/L was higher than the known value of 8.55 Bq/L, exceeding the upper acceptance range of 11.12 Bq/L. The original sample was run with a 10 mL aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 mL produced an acceptable result of 8.81 Bq/L. NCR 15-21

6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Bq/sample was lower than the known value of 2.18 Bq/sample, exceeding the lower acceptance range of 1.53

Bq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. We feel that this is possibly the case with this sample. NCR 15-21

7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Bq/sample was lower than the known value of 1.30 Bq/sample, exceeding the lower acceptance range of 0.91 Bq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. We feel that this is possibly the case with this sample. NCR 15-21

8. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L.

The technician failed to dilute the original sample, but used the entire 12 mL sample. When recalculated using the 12 mL aliquot, the result of 57.16 agreed with the assigned value of 56.2. NCR 15-19