View source for GNRO-2016/00019, Transmittal of 2015 Annual Radiological Environmental Operating Report (AREOR)

{{Adams
| number = ML16109A273
| issue date = 04/19/2016
| title = Transmittal of 2015 Annual Radiological Environmental Operating Report (AREOR)
| author name = Nadeau J
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000416
| license number = NPF-029
| contact person = 
| case reference number = GNRO-2016/00019
| document type = Annual Operating Report, Environmental Monitoring Report, Letter type:GNRO
| page count = 84
}}

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'"'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.
7

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.
9

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
                                             -ii-

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
                                         -iii-

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.
                                                -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 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.
2 of 6

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.
3 of 6

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.
4of6

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

'"'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.
7

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.
9

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
                                             -ii-

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
                                         -iii-

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.
                                                -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 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.
2 of 6

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.
3 of 6

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.
4of6

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}}