ML20108F575

From kanterella
Jump to navigation Jump to search
Annual Radiological Environmental Operating Report (AREOR)
ML20108F575
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/17/2020
From: Emily Larson
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2020/0012
Download: ML20108F575 (48)
v • d • e


Text

Entergy Operations, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 GNRO-2020/0012 April 17, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

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

Grand Gulf Nuclear Station, Unit 1 Docket Number 50-416 License Number NPF-29

Dear Sir or Madam:

In accordance with 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, 2019 through December 31, 2019.

This letter contains no new commitments. If you have any questions or require additional information, please contact Kevin Sanders at 601-6930.

Sincerely, C~ 1,,.___------

Eric A. Larson EAUsaw

Attachment:

Grand Gulf Nuclear Stations Annual Radiological Environmental Operating Report (AREOR) cc: NRC Region IV - Regional Administrator NRC Senior Resident Inspector, Grand Gulf Nuclear Station State Health Officer, Mississippi Department of Health NRC Project Manager

G N RO-2020/00012 Page 2 of 2 Attachment Grand Gulf Nuclear Station Annual Radiological Environmental Operating Report (AREOR)

Page 1 of 46 Plant: Grand Gulf Nuclear Station YEAR: 2019 Document Number: GNRO 2020-00012 Annual Radiological Environmental Operating Report

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 2 of 46 Annual Radiological Environmental Operating Report TABLE OF CONTENTS 1.0 EXECUTIVE

SUMMARY

.............................................................................................................3

2.0 INTRODUCTION

.........................................................................................................................5 3.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM REQUIREMENTS ...................... 6 4.0 INTERPRETATION AND TRENDS OF RESULTS .................................................................... 17 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

.......................... 22 ATTACHMENTS - Sample Deviations ........................................................................................................28 - Monitoring Results Tables ............................................................................................ 29 - lnterlaboratory Comparison Program Results .............................................................. .44

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 3 of 46 Annual Radiological Environmental Operating Report 1.0 EXECUTIVE

SUMMARY

1.1 Radiological Environmental Monitoring Program The Annual Radiological Environmental Operating Report presents data obtained through analyses of environmental samples collected for Grand Gulf Nuclear Station (GGNS) Radiological Environmental Monitoring Program (REMP) for the period January 1 through December 31, 2019. This report fulfills the requirements of Grand Gulf Nuclear Station Technical Specification 5.6.2.

All required lower limit of detection (LLD) capabilities were achieved in all sample analyses during 2019, as required by the GGNS Offsite Dose Calculation Manual (ODCM) Specifications Table 6.12.1-3. No measurable levels of radiation above baseline levels attributable to GGNS operation were detected in the vicinity of GGNS.

The 2019 Radiological Environmental Monitoring Program thus substantiated the adequacy of source control and effluent monitoring at GGNS with no observed impact of plant operations on the environment.

GGNS established the REMP in 1978 prior to the station's 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 direct radiation. GGNS also samples milk if milk-producing animals used for human consumption are present within five miles (8 km) of the plant.

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

In 2019, environmental samples were collected for radiological analysis. The results of indicator locations were compared with control locations and previous studies. It was concluded that no significant relationship exists between GGNS operation and effect on the area around the plant. The review of 2019 data showed radioactivity levels in the environment were undetectable in many locations and near background levels in significant pathways.

1.2 Reporting Levels When averaged over any calendar quarter, no environmental samples equaled or exceeded reporting levels for radioactivity as outlined in ODCM Specifications Table 6.12.1-2; the analytical results did not trigger any Radiological Monitoring Program Special Reports.

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 4 of 46 Annual Radiological Environmental Operating Report 1.3 Comparison to State and/or Federal Program GGNS personnel compared REMP data to state monitoring programs as results became available. Historically, the programs used for comparison have included the U.S. Nuclear Regulatory Commission (NRC) Thermoluminescent Dosimeter (TLD)

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

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

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

1.4 Sample Deviations During 2019, environmental sampling was performed for 5 media types addressed in the ODCM and for direct radiation. A total of 373 samples of the 379 scheduled were obtained. Of the scheduled samples, 98 percent were collected and analyzed in accordance with the requirements specified in the ODCM. Attachment 1 contains the listing of sample deviations and actions taken.

1.5 Program Modifications There were no program modifications during the reporting period.

Plant: Grand Gulf Nuclear Station I Year:2019 I Page 5 of 46 Annual Radiological Environmental Operating Report

2.0 INTRODUCTION

2.1 Radiological Environmental Monitoring Program GGNS established the REM P to ensure that plant operating controls properly function to minimize any associated radiation endangerment to human health or the environment. The REMP is designed for:

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

  • Considering the possibility of a buildup of long-lived radionuclides in the environment and identifying physical and biological accumulations that may contribute to human exposures.
  • Considering the potential radiation exposure to plant and animal life in the environment surrounding GGNS.
  • Correlating levels of radiation and radioactivity in the environment with radioactive releases from station operation.

2.2 Pathways Monitored The airborne, direct radiation, waterborne and ingestion pathways are monitored as required by GGNS ODCM Table 6.12.1-1. A description of the REMP utilized to monitor the exposure pathways is described in the attached Tables and Figures.

Section 4.0 of this report provides a discussion of 2019 sampling results with Section 5.0 providing a summary of results for the monitored exposure pathways.

2.3 Land Use Census GGNS conducts a land use census biennially, as required by Section 6.12.2 of the ODCM. The purpose of this census is to identify changes in uses of land within five miles of GGNS that would require modifications to the REMP and the ODCM. The most important criteria during this census are to determine the location in each sector of the nearest occupied residence, unoccupied residence, garden, and milking animal.

Plant: Grand Gulf Nuclear Station l Year: 2019 1 Page 6 of 46 Annual Radiological Environmental Operating Report 3.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM REQUIREMENTS Table 1, Exposure Pathway - Airborne Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency RADIOIODINE AND PARTICULATES AS-7 (Sector H, 0.5 miles) -

South-southeast of GGNS at 1 sample close to the SITE BOUNDARY the IBEW Union Hall having the highest calculated annual average ground level D/Q.

RADIOIODINE AND PARTICULATES AS-1 (Sector G, 5.5 miles) -

Southeast of GGNS at the

  • Radioiodine Canisters 131 analysis every 7 days 1 sample from the vicinity of a community having the highest calculated annual average Port Gibson City Barn
  • Air Particulate - Gross beta radioactivity analysis 7 days, or more frequently if following filter change ground level D/Q.

required by dust loading.

  • Air Particulate - Gamma Isotopic composite (by RADIOIODINE AND PARTICULATES AS-20 (Sector L, 0.9 miles) - location) every 92 days South-southeast of GGNS at 1 sample from the vicinity of a community the former Glodjo residence having the highest calculated annual average ground level D/Q.

RADIOIODINE AND PARTICULATES AS-3 (Sector B, 18 miles) -

North of the Vicksburg Airport 1 sample from a control location 15 - 30 km distance.

Plant: Grand Gulf Nuclear Station I Year: 2019 l Page 7 of 46 Annual Radiological Environmental Operating Report Table 2, Exposure Pathway - Direct Radiation Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency TLDS

  • M-16 (Sector A, Radius 0.9 Miles) - Meteorological Tower.

An inner ring of stations in the general areas 92 days Gamma dose; 92 days of the SITE BOUNDARY.

  • M-19 (Sector E, Radius 0.5 Miles) - Eastern SITE BOUNDARY Property line, North-northeast of HWSA.
  • 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.
  • M-23 (Sector Q, Radius 0.5 Miles) - Gin Lake Road 50 Yards North of Heavy Haul Road on Power Pole.
  • 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.
  • M-95 (Sector F, Radius 0.5 mi) -

Spoils Area, fence of old storage area, near entrance gate

Plant: Grand Gulf Nuclear Station T Year: 2019 l Page 8 of 46 Annual Radiological Environmental Operating ~eport Table 2, Exposure Pathway - Direct Radiation Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency TLDS

  • M-96 (Sector B, Radius 0.7 mi.)-

North Gate Fence An inner ring of stations in the general areas 92 days Gamma dose; 92 days of the SITE BOUNDARY.

  • M-97 (Sector D, Radius 0.8 mi.) -

Grand Gulf Road entrance gate to spoils area

  • M-98 (Sector H, Radius 0.5 mi.) -

Bald Hill Road, across from Union Hall, in curve

  • M-99 (Sector K, Radius 0.4 mi.) -

North Fence ofold Ball Field near utility pole

  • M-100 (Sector C, Radius 0.6 mi.)

- Grand Gulf Road

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 9 of 46 Annual Radiological Environmental Operating Report Table 2, Exposure Pathway - Direct Radiation Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency TLDS

  • M-36 (Sector P, Radius 5.0 Miles) - Curve on HW 608, Point An outer ring of stations approximately 3 to 5 92 days Gamma dose; 92 days Nearest GGNS at Power Pole.

miles from the site.

  • M-40 (Sector M, Radius 2.3 Miles) - Headly Drive, Near River Port Entrance.
  • M-48 (Sector K, Radius 4.8 Miles) - 0.4 Miles South on Mont Gomer Road on West Side.
  • 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 lngelside Karnac Ferry Road/Ashland Road Intersection.
  • M-57 (Sector F, Radius 4.5 Miles) - Hwy 61, Behind the Welcome to Port Gibson Sign at Glensdale Subdivision.

P!ant: Grand Gulf Nuclear Station l Year: 2019 I Page 10 of 46 Annual Radiological Environmental Operating Report Table 2, Exposure Pathway - Direct Radiation Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency TLDS

  • M-01 (Sector E, Radius 3.5 Miles) - Across the road from Additional stations in special interest areas 92 days Gamma dose; 92 days Lake Claiborne Entry Gate.

such as population centers, nearby (Special) residences, schools, and in 1 or 2 areas to serve as control locations.

  • M-07 (Sector G, Radius 5.5 Miles) - AS-1 PG, Port Gibson City Barn. (Special)
  • M-09 (Sector D, Radius 3.5 Miles) - Warner Tully Y-Camp.

(Special)

  • M-10 (Sector A, Radius 1.5 Miles) - Grand Gulf Military Park.

(Special)

  • 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) - Newellton, Louisiana Water Tower. (Control)
  • M-38 (Sector M, Radius 9.5 Miles) - Lake Bruin State Park, Entrance Road. (Special)
  • M-39 (Sector M, Radius 13.0 Miles) - St. Joseph, Louisiana, Auxiliary Water Tank. (Special)

Plant: Grand Gulf Nuclear Station I Year: 2019 l Page 11 of 46 Annual Radiological Environmental Operating Report Table 3, Exposure Pathway-Waterborne Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency

  • MRUP (Sector R, Radius 1.8 Miles) - At least 4500 ft upstream 92 days Gamma isotopic and tritium analysis; 92 days of the GGNS discharge point into SURFACE WATER the Mississippi River to allow adequate mixing of the Mississippi 1 sample upstream and 1 sample and Big Black Rivers.

downstream.

  • MRDOWN (Sector N, Radius 1.6 Miles) - At least 5000 ft downstream of the GGNS discharge point in the Mississippi River near Radial Well No. 1.
  • MRDOWN (Sector P, Radius 1.3 Miles) - Downstream of the 1 sample downstream during a Liquid GGNS discharge point in the 366 days Gamma isotopic and tritium analysis; 366 days Radwaste Discharge.

Mississippi River near Radial Well No. 5.

1 sample from Outfall 007

  • OUTFALL 007 (Sector N, Radius 31 days Tritium; 31 days 0.2 Miles)- Storm Drain System
  • PGWELL (Sector G, Radius 5.0 Miles) - Port Gibson Wells -

366 days Gamma isotopic and tritium analysis; 366 days Taken from distribution system or GROUNDWATER one of the five wells.

Samples from 2 sources

  • CONSTWELL (Sector Q, Radius 0.4 Miles)- GGNS Construction Water Well - Taken from distribution system or the well.

Plant: Grand Gulf Nuclear Station T Year: 2019 I Page 12 of 46 Annual Radiological Environmental Operating Report Table 3, Exposure Pathway - Waterborne Sample Point Description Sampling and Collection Requirement Type and Frequency Of Analyses Distance and Direction Frequency SEDIMENT FROM SHORELINE

  • SEDHAM (Sector N, Radius 1.6 Miles) - Downstream of the 1 sample from downstream area and 1 366 days Gamma isotopic; 366 days GGNS discharge point in the sample from upstream area Mississippi River near Hamilton Lake outlet.
  • SEDCONT (Minimum of 100 yds)

- Upstream of the GGNS discharge point in the Mississippi River.

Plant: Grand Gulf Nuclear Station I Year:2019 I Page 13 of 46 Annual Radiological Environmental Operating Report Table 4, Exposure Pathway - Ingestion Sample Point Description Distance Sampling and Collection Requirement Type and Frequency Of Analyses and Direction Frequency MILK

  • If commercially available, 1 sample from
  • Currently, no available milking animals 92 days when required Gamma isotopic and 1-131 ; 92 days milking animals within 8 km distant within 8 km of GGNS.
  • 1 sample from milking animals at a
  • ALCONT (Sector K, Radius 10.5 control location >8 km distant when an Miles) - Located South-southwest of indicator location exists. GGNS at Alcorn State University.

(Control)

FISH AND INVERTEBRATES

  • FISH DOWN - Downstream of the GGNS discharge point into the
  • 1 sample in vicinity of GGNS discharge 366 days Gamma isotopic on edible portions; 366 days Mississippi River point.
  • 1 sample uninfluenced by GGNS
  • FISH UP - Upstream of the GGNS discharge point into the Mississippi discharge. River uninfluenced by plant operations.

FOOD PRODUCTS

  • VEG-J (Sector J, Radius 0.4 Miles) -

South of GGNS near former Training

  • 1 sample of broadleaf vegetation grown in 92 days when available Gamma isotopic and 1-131 ; 92 days Center on Bald Hill Road.

one of two different offsite locations with highest anticipated annual average

  • VEG-CONT (Sector K, Radius 10.5 ground level D/Q if milk sampling is not Miles) - Alcorn State University south-performed. southwest of GGNS when available, otherwise a location 15-30 km distant.
  • 1 sample of similar vegetation grown 15 -

(Control) 30 km distant if milk sampling is not performed.

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 14 of 46 Annual Radiological Environmental Operating Report Figure 1, Exposure Pathway NUCLEAR POWER PLANT i

\.

l; I

0t> ~!-..

0 I

'O Q i' / Otrtct N'l\,_\o-, -

J

.~ \. ,,;ldi,uion _.

,,i- ,,,. -~,~.~

e , ~

, ; : : L TRANSPORT

  • Id"'~._ ~~,,.'* to

~,.,i.,,.!"1

"~f#l/.,.,ln, (iP

e . . ____

Shot.rint E~Posc,,*

~

,,,it",...,.. * ~ e>e a,o~AflP"' 9\.....

'°"

~::.$ (~~ ----

..*,;on ~

~ 1

~~

Jt

\

I

-~

'""°" -- i

.t'

~*

~

Exposure pathways to man

Plant: Grand Gulf Nuclear Station I Year:2019 J Page 15 of 46 Annual Radiological Environmental Operating Report Figure 2, Sample Collection Sites -Near Field

~

i I! ul 1 i 1)1 Cit! I I * ! i iuI -

i I i1h111~1. ~ I ..

I l

'-O<J 00*$

~*

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 16 of 46 Annual Radiological Environmental Operating Report Figure 3, Sample Collection Sites - Far Field i

I ,1

~;; ~- a

  • i C') 1J I ic1*

11:u 1000*

~ ......-Ju*

e,lilH a: oj~

~~

1*11

.JI DIii** 1 i"""I I

C:,11 I

-,~

dSu:('t)

...JI

Plant: Grand Gulf Nuclear Station Year:2019 I Page 17 of 46 Annual Radiological Environmental Operating Report 4.0 INTERPRETATION AND TRENDS OF RESULTS 4.1 Air Particulate and Radioiodine Sam(!le 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.

In 2019 there were no samples above the LLD for 1-131. Indicator gross beta air particulate results for 2019 were comparable to results obtained from 2009-2018 of the operational REMP. Also, the 2019 gross beta annual average was less than the average for preoperational levels. Results are reported as annual average picocuries per cubic meter (pCi/m 3).

Monitoring Period Result 2009- 2018 (Minimum Value) 0.009 2019 Average Value 0.017 2009 - 2018 (Maximum Value) 0.043 Preoperational 0.032 In the absence of plant-related gamma radionuclides, gross beta activity is attributed to naturally occurring radionuclides. Table 3.1, which include gross beta concentrations and provide a comparison of the indicator and control means and ranges emphasizes the consistent trends seen in this pathway to support the presence of naturally occurring activity. Therefore, it can be concluded that the airborne pathway continues to be unaffected by Grand Gulf Nuclear Station operations.

Plant: Grand Gulf Nuclear Station I Year:2()19~-----r Page 18 of 46 Annual Radiological Environmental Operating Report 4.2 Thermoluminescent Dosimetry (TLD) Sample Results Grand Gulf Nuclear Station reports measured dose as net exposure (field reading less transit reading) normalized to 92 days and relies on comparison of the indicator locations to the control as a measure of plant impact. Grand Gulf Nuclear Station's comparison of the inner ring and special interest area TLD results to the control, as seen in Table 7, identified no noticeable trend that would indicate that the ambient radiation levels are being affected by plant operations. In addition, the inner ring value of 10.0 millirem/quarter (mR/Qtr) shown in Table 7 for 2019 is within the historical bounds of 2009 - 2018 annual average results, which have ranged from 9.3 to 10.9 mrem. Overall, Grand Gulf Nuclear Station concluded that the ambient radiation levels are not being affected by plant operations.

Table 5, Direct Radiation Annual Summary Year Inner Ring (mR/Qtr) Outer Ring (mR/Qtr) Control Location lm0/0tr\

2009 10.9 10.2 11.3 2010 10.8 10.5 12.1 2011 10.0 10.2 11.4 2012 9.5 9.7 11.0 2013 9.8 9.7 10.8 2014 10.0 9.9 11.0 2015 9.6 9.5 10.8 2016 9.3 9.3 10.7 2017 9.9 9.9 11.3 2018 9.7 9.8 10.6 2019 10.0 9.7 10.7 4.3 Waterborne Samale Results Analytical results for 2019 surface water and drinking water samples were similar to those reported in previous years. Gamma radionuclides analytical results for 2019 surface water samples were similar to those reported in previous years. Tritium in Grand Gulf Nuclear Station surface water indicator samples continues to be detected, but is attributed to washout and entrainment of normal, previously monitored gaseous effluents. These results are further explained below.

4.3.1 Surface Water Samples were collected from two indicator locations (Outfall 007, MRDOWN) 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 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

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 19 of 46 Annual Radiological Environmental Operating Report occasionally observed. Tritium was measured at during June (1850 pCi/L), July (1700 pCi/L),

and December (1660 pCi/L) at the Outfall 007 location. Tritium was also measured in the duplicate samples collected during June (2020 pCi/L) and December (1570 pCi/L). Tritium was not observed in the remaining Outfall 007 samples collected during 2019. Results are reported as annual average pCi/1.

Monitoring Period Result 2009 - 2018 (Minimum Value) 729 2019 Value 1760 2009 - 2018 (Maximum Value) 2020 Preoperational 2739 In addition to the tritium samples required by the REMP, five special surface water samples for gamma emitting radionuclides were collected at the Outfall 007 location.

Plant related gamma emitting radionuclides remained undetectable in these samples.

Grand Gulf Nuclear Station personnel have noted no definable increasing trends associated with the tritium levels at the discharge location. Levels detected during 2019 and previous operational years have been well below regulatory reporting limits.

Therefore, the operation of Grand Gulf Nuclear Station had no definable impact on this waterborne pathway during 2019 and levels of radionuclides remain similar to those obtained in previous operational years.

4.3.2 Drinking Water Drinking water samples were collected from two locations, CONSTWELL (indicator) and PGWELL (control). Drinking water samples were analyzed for 1-131, gamma radionuclides and tritium. During 2019, gamma radionuclides, 1-131, and tritium concentrations were below the LLD limits at the indicator and control locations, which is consistent with previous operational years. Results are reported as annual average pCi/L.

Radionuclide 2019 2009 - 2018* Preo~erational Gross Beta < LLD < LLD <LLD lodine-131 < LLD < LLD < LLD Gamma < LLD < LLD < LLD Tritium < LLD < LLD <LLD Grand Gulf Nuclear Station personnel have noted no definable trends associated with drinking water results at the indicator location. Therefore, the operation of Grand Gulf Nu clear Station had no definable impact on this waterborne pathway during 2019 and levels of radionuclides remain similar to those obtained in previous operational years.

Results from 2019 are summarized in Table 7.

Plant: Grand Gulf Nuclear Station I Year: 2019 1 Page 20 of 46 Annual Radiological Environmental Operating Report 4.3.3 Groundwater Groundwater monitoring data collected during administration of the Groundwater Protection Initiative (GPI) site program are included in the Annual Radioactive Effluent Release Report.

4.4 Soil Samale Results Sediment samples were collected from two locations in 2019 and analyzed for gamma radionuclides. Listed below is a comparison of 2019 indicator results to the 2009 - 2018 operational years. Grand Gulf Nuclear Station operations had no significant impact on the environment or public by this waterborne pathway. Results are reported as pCi/kg.

Monitoring Period Result 2009 - 2018 (Minimum Value) <LLD 2019 Value < LLD 2009 - 2018 (Maximum Value) 40.3 Preoperational 295.0 4.5 Ingestion Sample Results 4.5.1 Milk SamQle Results Milk samples were not collected during 2019 due to the unavailability of indicator locations within five miles of Grand Gulf Nuclear Station.

4.5.2 Fish Sam12le Results Fish samples were collected from two locations and analyzed for gamma radionuclides. In 2019, gamma radionuclides were below detectable limits which are consistent with preoperational and operational years. Therefore, based on these measurements, Grand Gulf Nuclear Station operations had no significant radiological impact upon the environment or public by this ingestion pathway.

4.5.3 Food Product SamQle Results The REMP has detected radionuclides prior to 1990 that are attributable to other sources. These include the radioactive plume release due to reactor core degradation at Chernobyl Nuclear Power Plant in 1986 and atmospheric weapons testing.

In 2019, food product samples were collected from two locations and analyzed for plant related lodine-131 and gamma radionuclides. The 2019 levels remained undetectable, as has been the case in previous years. Therefore, based on these measurements, Grand Gulf Nuclear Station operations had no significant radiological impact upon the environment or public by this ingestion pathway.

Plant: Grand Gulf Nuclear Station Year: 2019 Page 21 of 46 Annual Radiological Environmental Operating Report 4.6 Land Use Census Results The latest land use census, performed in 2018, did not identify any new locations that yielded a calculated dose or dose commitment greater than those currently calculated.

The land use census identified no milk-producing animals within a five-mile radius of the plant site. In accordance with ODCM Section 6.12.1, Grand Gulf Nuclear Station personnel sampled broadleaf vegetation.

Table 6, Land Use Census - 2019 Nearest Residence Within Five Miles Sector Direction Nearest Residence (miles) Nearest Garden (miles)

A N 1.02 1.02 B NNE 1.51 1.52 C NE 0.70 4.14 D ENE 2.60 4.50 E E 0.83 0.91 F ESE 2.25 4.51 G SE 3.72 4.20 H SSE 1.10 4.31 J s 3.14 3.16 K SSW 2.20 2.18 L SW 0.89 0.89 M WSW none within 5 miles none within 5 miles N w none within 5 miles none within 5 miles p WNW none within 5 miles none within 5 miles Q NW none within 5 miles none within 5 miles R NNW 1.44 none within 5 miles A land use census was not conducted for the year 2019. The next land use census is scheduled to be conducted in 2020.

4.7 lnterlaboratory Comparison Results Attachment 3 contains result summary for lnterlaboratory Comparison program for Teledyne Brown Engineering.

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

1. Table 7, Radiological Environmental Monitoring Program Summary, summarizes data for the 2019 REMP program.

Pla'!t: Grand Gulf Nuclear Station 1 Year: 2019 I Page 22 of 46 Annual Radiological Environmental Operating Report Table 7, Radiological Environmental Monitoring Program Summary Location with the Highest Annual Control Type/ Number Indicator Locations Mean Number of Sample Type LLD [Note 2) Mean (f)[Note 3) Locations of Analyses Mean (f)[Note 3) Non-Routine (Units) [Note 1) Mean (f)[Note 3) Results [Note SJ

[Range] Location [Note 41 [Range]

[Range]

GB/ 212 0.01 0.0172 (159 / 159) AS-1 PG 0.0179 (53 I 53) 0.0175 (52 I 52) 0

[0.0085 - 0.0387] (Sector G, 5.5 mi) [0.0086 - 0.0394] [0.0085 - 0.0387]

Air Particulates GS I 16 (pCi/m 3 ) Cs-134 0.05 <LLD N/A N/A <LLD 0 CS-137 0.06 <LLD N/A N/A <LLD 0 Airborne 1-131/212 0.07 < LLD N/A N/A < LLD 0 Iodine (pCi/ m 3 )

Inner Ring [Note6]

Gamma I 50 10.12 (50 / 50) M-99 12.9(4/4) N/A 0 TLDs (mR/Qtr)

(6.9 - 13.2] (Sector J, 0.4 mi.) (7.9 - 13.2]

Outer Ring Gamma/ 28 [Note6] 9.7 (28 I 28) M-57 11.7(4/4) N/A 0 TLDs (mR/Qtr) [4.5 - 12.4] (Sector F, 4.5 mi.) [11.3 - 12.4]

Special Interest TLDs Gamma/ 28 [Note6) 9.5 (28 I 28) M-01 11.4(4/4) NIA 0 (mR/Qtr) [7.5 - 12.2] (Sector E, 3.5 mi.) [10.7-12.2]

Control TLD [Note 6) N/A 10.7 (4 I 4) 0 Gamma/ 4 N/A N/A (mR/Qtr) [10.0 -11.3]

Plant: Grand Gulf Nuclear Station I Year: 2019 l Page 23 of 46 Annual Radiological Environmental Operating Report Table 7, Radiological Environmental Monitoring Program Summary Location with the Highest Annual Control Type/ Number Indicator Locations Mean Number of Sample Type Locations of Analyses LLD [Note 2] Mean (f )[Note 3] Mean (f)[Note 3] Non-Routine (Units) [Note 1] [Range] Mean (f)[Note 3] Results [Note 51 Location [Note 41 [Range]

[Range]

H-3 / 38 3000 1760 (5 I 30) Outfall 007 797 (5 / 20) < LLD 0

[1570 - 2020] (Sector N, 0.2 mi.) [1570 - 2020]

GS I 16 Mn-54 15 < LLD N/A N/A < LLD 0 Fe-59 30 < LLD N/A N/A < LLD 0 Co-58 15 < LLD N/A N/A < LLD 0 Co-60 15 < LLD N/A N/A < LLD 0 Surface Water < LLD 0 Zn-65 30 < LLD N/A N/A (pCi/1) < LLD 0 Zr-95 30 < LLD N/A NIA Nb-95 15 < 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

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 24 of 46 Annual Radiological Environmental Operating Report Table 7, Radiological Environmental Monitoring Program Summary Location with the Highest Annual Control Type/ Number Indicator Locations Mean Number of Sample Type LLD Mean (F)(Note 3) Locations of Analyses (Note 2)

Mean (F)(Note 3) Non-Routine (Units) (Note 1)

[Range] Mean (F)(Note 3) Results [Note SJ Location [Note 41 [Range]

[Range]

1-131 /4 1 < LLD N/A N/A < LLD 0 H-3 / 4 2000 < LLD N/A N/A < LLD 0 GS I 4 Mn-54 15 < LLD N/A N/A < LLD 0 Fe-59 30 < LLD N/A N/A < LLD 0 Co-58 15 < LLD N/A N/A < LLD 0 Drinking Water Co-60 15 < LLD N/A N/A < LLD 0 (pCi/1)

Zn-65 30 < LLD N/A N/A < LLD 0 Zr-95 30 < LLD N/A N/A < LLD 0 Nb-95 15 < LLD N/A N/A < LLD 0 Cs-134 15 < LLD N/A N/A < LLD 0 Cs-137 18 < LLD N/A N/A < LLD 0 Ba-140 60 < LLD N/A NIA < LLD 0 La-140 15 < LLD N/A N/A < LLD 0 GS/4 Sediment 150 < LLD N/A N/A N/A 0 Cs-134 (pCi/kg) 180 < LLD N/A N/A N/A 0 Cs-137

Plant: Grand Gulf Nuclear Station I Year:2019 J Page 25 of 46 Annual Radiological Environmental Operating Report Table 7, Radiological Environmental Monitoring Program Summary Location with the Highest Annual Control Type/ Number Indicator Locations Mean Number of Sample Type LLD [Note 2] Mean (F)(Note 3] Locations of Analyses Mean (F)(Note 3] Non-Routine (Units) (Note 1] Mean (F)(Note 3] Results [Note S]

[Range] Location (Note 41 [Range]

[Range]

GS/4 Mn-54 130 < LLD N/A N/A < LLD 0 Fe-59 260 < LLD N/A N/A < LLD 0 Fish (pCi/kg) Co-58 130 < 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 1-131 / 12 60 < LLD N/A N/A N/A 0 Food Products GS I 12 (pCi/kg)

Cs-134 60 < LLD N/A N/A N/A 0 Cs-137 80 < LLD N/A NIA N/A 0

Plant: Grand Gulf Nuclear Station I Year: 2019 J Page 26 of 46 Annual Radiological Environmental Operatin~R~port Table 7, Radiological Environmental Monitoring Program Summary Location with the Highest Annual Control Type/ Number Indicator Locations Mean Number of Sample Type LLD Mean (F)(Note 3) Locations of Analyses (Note 2)

Mean (F)[Note 3) Non-Routine (Units) (Note 1) Mean (F)[Note 3) Results [Note 51

[Range] Location [Note 41 [Range]

[Range]

GS I 5 Mn-54 15 < LLD N/A N/A < LLD 0 Fe-59 30 < LLD N/A N/A < LLD 0 Co-58 15 < LLD N/A N/A < LLD 0 Co-60 15 < LLD N/A N/A < LLD 0 Surface Water Zn-65 30 < LLD N/A N/A < LLD 0 (Special) Zr-95 30 < LLD NIA N/A < LLD 0 (pCi/1) Nb-95 15 < LLD N/A N/A < LLD 0 Cs-134 15 < LLD N/A N/A < LLD 0 Cs-137 18 < LLD N/A N/A < LLD 0 Ba-140 60 < LLD N/A N/A < LLD 0 La-140 15 < LLD N/A N/A < LLD 0

Plant: Grand Gulf Nuclear Station 1 Year: 2019 I Pag~ 27 of 46 Annual Radiological Environmental Operating Report Table 7, Radiological Environmental Monitoring Program Summary Location with the Highest Annual Control Type/ Number Indicator Locations Mean Number of Sample Type LLD (Note 2) Mean (f )[Note 3) Locations of Analyses Mean (f)[Note 3) Non-Routine (Units) (Note 1) Mean (F)(Note 3) Results [Note S]

[Range] Location (Note 41 [Range]

(Range]

GS/ 1 Mn-54 130 < LLD N/A N/A < LLD 0 Fe-59 260 < LLD N/A N/A < LLD 0 Meat Co-58 130 < LLD NIA N/A < LLD 0 (Special)

Co-60 130 < LLD N/A N/A < LLD 0 (pCi/kg)

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 LEGEND:

[Note 1] - GB= Gross beta; 1-131 = lodine-131; H-3 = Tritium; GS= Gamma scan.

[Note 2] - LLD = Required lower limit of detection based on ODCM Table 6.12.1-3.

[Note 3] - Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthesis (F).

[Note 4] - Where applicable, locations are specified (1) by name, (2) distance from reactor site, and (3) meteorological sector.

[Note 5] - 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.

[Note 6] - LLD is not defined in ODCM Table 6.12.1-3.

Plant: Grand Gulf Nuclear Station I Year:2019 j___Page 28 of 46 Annual Radic:>lc:>_g_ic:al Environmental Operating Report Attachment 1 Page 1 of 1 Sample Deviations Table 8, Sample Deviations Table Sample Comment Sample Media Date Problem Evaluation/ Actions No. Location Affected During collection of 1st quarter 2019 TLDs, two locations, M-23 and M-25, M-23, were inaccessible due to high Mississippi River water level. New TLDs 1 TLD 04/09/19 Inaccessible M-25 were installed when the locations became accessible in October 2019. CR-GGN-2019-02900 documents the condition.

During collection of 2nd quarter 2019 TLDs, two locations, M-23 and M-25, M-23, were inaccessible due to high Mississippi River water level. New TLDs 2 TLD 07/10/19 Inaccessible M-25 were installed when the locations became accessible in October 2019. CR-GGN-2019-05597 documents the condition.

During collection of 3rd quarter 2019 TLDs, two locations, M-23 and M-25, M-23, were not available due to high Mississippi River water level. New TLDs 3 TLD 10/09/19 Inaccessible M-25 were installed when the locations became accessible in October 2019. CR-GGN-2019-08312 documents the condition.

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 29 of 46 Annual Radiological Environmental Operating Report Page 1 of 15 Monitoring Results Tables Table 9, Air Particulate Data Summary Table Analysis: Gross Beta Units: pCi/m 3 I

Station Station Station Station Start Date End Date AS-7 AS-20 AS-3 [Note 1]

AS-1 (Indicator)

(Indicator) (Indicator) (Control)

REQUIRED LLD+ 0.01 0.01 0.01 0.01 12/26/18 01/02/19 0.01670 0.01660 0.01430 0.01540 01/02/19 01/08/19 0.01310 0.01370 0.01710 0.01720 01/08/19 01/15/19 0.01330 0.01300 0.01320 0.01440 01/15/19 01/22/19 0.01360 0.01470 0.01430 0.01630 01/22/19 01/29/19 0.01730 0.01850 0.01780 0.01920 01/29/19 02/05/19 0.01600 0.01080 0.01480 0.01390 02/05/19 02/12/19 0.01390 0.01530 0.01710 0.01760 02/12/19 02/19/19 0.01780 0.01690 0.01650 0.01560 02/19/19 02/26/19 0.01450 0.01170 0.01280 0.01070 02/26/19 03/05/19 0.01500 0.01100 0.01480 0.01190 03/05/19 03/12/19 0.01530 0.01740 0.01670 0.01750 03/12/19 03/19/19 0.01440 0.01350 0.01180 0.01470 03/19/19 03/26/19 0.01680 0.01740 0.01250 0.01680 03/26/19 04/02/19 0.01630 0.01610 0.01660 0.01710 04/02/19 04/09/19 0.01140 0.01030 0.00981 0.01050 04/09/19 04/16/19 0.01310 0.01290 0.01200 0.01220 04/16/19 04/23/19 0.01050 0.01370 0.01240 0.01450 04/23/19 04/30/19 0.02040 0.02420 0.01710 0.02540 04/30/19 05/07/19 0.01540 0.01460 0.01310 0.01350 05/07 /19 05/14/19 0.00946 0.01180 0.01220 0.00856 05/14/19 05/21 /19 0.01940 0.02010 0.01950 0.02080 05/21 /19 05/28/19 0.01580 0.01430 0.01740 0.02080 05/28/19 06/04/19 0.01490 0.02000 0.01800 0.01700 06/04/19 06/11/19 0.01620 0.01480 0.01760 0.01600 06/11/19 06/18/19 0.01240 0.01490 0.01420 0.01540 06/18/19 06/25/19 0.01470 0.01090 0.01180 0.01130 06/25/19 07/02/19 0.02180 0.02000 0.01930 0.02210

Plant: Grand Gulf Nuclear Station I Year: 2019 l Page 30 of 46 Annual Radiological Environmental Operating Report Attachment 2 Page 2 of 15 Monitoring Results Tables Table 9, Air Particulate Data Summary Table Analysis: Gross Beta Units: pCi/m 3 I

Station Station Station Station Start Date End Date AS-7 AS-20 AS-3 [Note 1]

AS-1 (Indicator)

(Indicator) (Indicator) (Control)

REQUIRED LLD + 0.01 0.01 0.01 0.01 07/02/19 07/09/19 0.01330 0.01380 0.01200 0.01460 07/09/19 07/16/19 0.01350 0.01120 0.00895 0.01130 07/16/19 07/23/19 0.01180 0.01120 0.01000 0.01110 07/23/19 07/30/19 0.01440 0.01050 0.01290 0.01470 07/30/19 08/06/19 0.01920 0.02230 0.01890 0.02140 08/06/19 08/13/19 0.01540 0.01850 0.01330 0.01670 08/13/19 08/20/19 0.02060 0.01800 0.01740 0.01940 08/20/19 08/27/19 0.01400 0.01180 0.01140 0.01230 08/27/19 09/03/19 0.02280 0.02230 0.02570 0.02460 09/03/19 09/10/19 0.03870 0.03660 0.03780 0.03940 09/10/19 09/17/19 0.03470 0.03420 0.03380 0.03570 09/17/19 09/24/19 0.01970 0.01670 0.01650 0.01710 09/24/19 10/01/19 0.02390 0.02420 0.02140 0.02610 10/01 /19 10/08/19 0.02760 0.02450 0.02110 0.02630 10/08/19 10/15/19 0.01820 0.01650 0.01610 0.01670 10/15/19 10/22/19 0.01970 0.02340 0.02130 0.02150 10/22/19 10/29/19 0.00852 0.01160 0.01050 0.01140 10/29/19 11/05/19 0.01970 0.01590 0.01760 0.02010 11/05/19 11/12/19 0.02400 0.02460 0.02650 0.02750 11/12/19 11/19/19 0.03290 0.02880 0.03170 0.03190 11/19/19 11/26/19 0.02040 0.02040 0.01500 0.02110 11/26/19 12/03/19 0.01260 0.01250 0.01430 0.01290 12/03/19 12/10/19 0.02560 0.02220 0.01960 0.02150 12/10/19 12/17/19 0.01940 0.01620 0.01800 0.01820 12/17/19 12/23/19 0.01870 0.02240 0.02190 0.01860 12/23/19 12/31/19 0.01030 0.01220 0.01230 0.01010

[Note 1] - Station with highest annual mean.

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 31 of 46 Annual Radiological Environmental Operating Report Page 3 of 15 Monitoring Results Tables Table 10, Radioiodine Cartridge Data Table Summary Analysis: 1-131 Units: pCi/m 3 I

AS-1 AS-7 AS-20 AS-3 Start Date End Date (Indicator) (Indicator) (Indicator) (Control) 12/26/18 01/02/19 <0.03822 <0.04010 <0.03819 <0.03829 01/02/19 01/08/19 <0.04828 <0.04948 <0.04877 <0.04834 01/08/19 01/15/19 <0.03529 <0.03686 <0.03633 <0.03534 01/15/19 01/22/19 <0.03160 <0.03992 <0.03820 <0.03778 01/22/19 01/29/19 <0.02140 <0.02264 <0.02168 <0.01770 01/29/19 02/05/19 <0.04847 <0.04765 <0.04899 <0.04652 02/05/19 02/12/19 <0.03234 <0.03186 <0.03332 <0.03149 02/12/19 02/19/19 <0.04843 <0.04699 <0.04985 <0.04711 02/19/19 02/26/19 <0.04028 <0.03901 <0.04140 <0.03921 02/26/19 03/05/19 <0.02643 <0.02601 <0.02759 <0.02610 03/05/19 03/12/19 <0.05818 <0.05736 <0.06082 <0.05735 03/12/19 03/19/19 <0.04205 <0.04188 <0.04249 <0.04235 03/19/19 03/26/19 <0.05138 <0.05054 <0.05285 <0.05071 03/26/19 04/02/19 <0.04473 <0.04344 <0.04607 <0.04352 04/02/19 04/09/19 <0.06263 <0.05975 <0.06423 <0.06045 04/09/19 04/16/19 <0.05670 <0.05667 <0.05597 <0.05660 04/16/19 04/23/19 <0.03025 <0.04344 <0.01568 <0.02981 04/23/19 04/30/19 <0.03424 <0.03324 <0.03229 <0.03381 04/30/19 05/07/19 <0.04033 <0.03939 <0.03858 <0.04045 05/07/19 05/14/19 <0.01344 <0.01339 <0.01332 <0.01325 05/14/19 05/21/19 <0.02826 <0.02781 <0.02767 <0.02873 05/21/19 05/28/19 <0.02017 <0.01986 <0.01931 <0.02112 05/28/19 06/04/19 <0.02012 <0.01980 <0.01949 <0.02129 06/04/19 06/11/19 <0.04642 <0.04637 <0.04571 <0.05112 06/11/19 06/18/19 <0.04469 <0.04596 <0.04519 <0.04520 06/18/19 06/25/19 <0.03106 <0.03098 <0.03108 <0.03116 06/25/19 07/02/19 <0.02560 <0.02560 <0.02585 <0.02563 07/02/19 07/09/19 <0.01979 <0.01931 <0.01949 <0.01965

Plant: Grand Gulf Nuclear Station I Year:2019 I Page 32 of 46 Annual Radiological Environmental Operating Report Page 4 of 15 Monitoring Results Tables Table 10, Radioiodine Cartridge Data Table Summary Units: pCi/m 3 Analysis: 1-131 I

AS-1 AS-7 AS-20 AS-3 Start Date End Date (Indicator) (Indicator) (Indicator) (Control) 07/09/19 07/16/19 <0.03666 <0.03778 <0.03720 <0.03660 07/16/19 07/23/19 <0.03090 <0.03117 <0.03112 <0.03080 07/23/19 07/30/19 <0.04742 <0.04838 <0.04870 <0.04817 07/30/19 08/06/19 <0.06683 <0.06739 <0.06779 <0.06594 08/06/19 08/13/19 <0.02965 <0.06246 <0.02971 <0.02969 08/13/19 08/20/19 <0.02613 <0.02694 <0.02615 <0.02580 08/20/19 08/27/19 <0.02470 <0.02515 <0.03188 <0.02495 08/27/19 09/03/19 <0.04095 <0.04088 <0.04079 <0.04041 09/03/19 09/10/19 <0.02638 <0.02552 <0.02555 <0.02626 09/10/19 09/17/19 <0.03998 <0.04088 <0.04091 <0.03994 09/17/19 09/24/19 <0.03815 <0.03900 <0.03834 <0.03817 09/24/19 10/01/19 <0.05204 <0.05180 <0.05238 <0.05138 10/01/19 10/08/19 <0.03706 <0.03786 <0.03722 <0.03080 10/08/19 10/15/19 <0.05350 <0.05401 <0.05368 <0.02198 10/15/19 10/22/19 <0.04360 <0.04327 <0.04317 <0.04222 10/22/19 10/29/19 <0.02916 <0.02888 <0.02878 <0.02911 10/29/19 11/05/19 <0.02173 <0.02165 <0.02151 <0.02183 11 /05/19 11/12/19 <0.01530 <0.01535 <0.01538 <0.01530 11 /12/19 11/19/19 <0.02687 <0.02664 <0.02677 <0.02682 11/26/19 11/26/19 <0.04537 <0.04466 <0.04539 <0.04483 11 /26/19 12/03/19 <0.03003 <0.03003 <0.02990 <0.02505 12/03/19 12/10/19 <0.03032 <0.03015 <0.03020 <0.03051 12/10/19 12/17/19 <0.02788 <0.02755 <0.02743 <0.02768 12/17/19 12/23/19 <0.02717 <0.02695 <0.02684 <0.02740 12/23/19 12/31/19 <0.02954 <0.02930 <0.01641 <0.02958

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 33 of 46 Annual Radiological Environmental Operating Report Page 5 of 15 Monitoring Results Tables Table 11, Air Gamma Quarterly Composite Analysis: Gamma Isotopic Units: pCi/cu.m Location Date CS-134 CS-137 REQUIRED LLD + 0.05 0.06 AS-1 <0.002094 <0.001558 AS-3 <0.001674 <0.001407 02/16/19 AS-7 <0.002557 <0.002632 AS-20 <0.002976 <0.002238 AS-1 <0.00275 <0.001860 AS-3 <0.001959 <0.001704 05/17/19 AS-7 <0.001661 <0.001826 AS-20 <0.002166 <0.000899 AS-1 <0.001822 <0.001110 AS-3 08/16/19 <0.001403 <0.001292 AS-7 <0.002082 <0.001854 AS-20 <0.002082 <0.001036 AS-1 <0.002292 <0.00883 AS-3 <0.003055 <0.002902 11/15/19 AS-7 <0.001694 <0.001147 AS-20 <0.002143 <0.001166

Plant: Grand Gulf Nuclear Station l Year:2019 l Page 34 of 46 Annual Radiological Environmental Operating Report Page 6 of 15 Monitoring Results Tables Table 12, Thermoluminescent Dosimeters - Inner Ring Analysis: Gamma Dose Units: mrem I

Annual Station 1st Qtr 2019 2nd Qtr 2019 3 rd Qtr 2019 4th Qtr 2019 Mean 2019 M-16 9.9 10.8 10.1 10.9 10.4 M-19 8.6 9.3 9.9 9.2 9.2 M-21 12.7 11.8 11.9 12.5 12.2 M-22 8.2 8.4 8.4 8.4 8.4 M-23 Lost[Note 2] Lost[ Note 3] Lost[Note 4] 9.5 9.5 M-25 Lost[Note 2] Lost[Note 3] Lost[Note 4] 7.7 7.7 M-28 11.5 10.9 11.1 12.0 11.4 M-94 10.8 10.9 10.3 11.0 10.7 M-95 7.1 7.6 6.9 8.4 7.5 M-96 8.2 9.0 8.0 8.9 8.5 M-97 7.8 8.3 7.1 9.0 8.1 M-98 11.3 11.8 11.3 12.1 11.6 M-99[Note 1] 12.8 13.2 12.6 13.2 12.9 M-100 11.4 10.8 11.2 11.7 11.3

[Note 1] - Station with highest annual mean.

[Note 2] - Reference Attachment 1, Sample Deviations, Table 8, Sample Deviations Table, Comment 1

[Note 3] - Reference Attachment 1, Sample Deviations, Table 8, Sample Deviations Table, Comment 2

[Note 4] - Reference Attachment 1, Sample Deviations, Table 8, Sample Deviations Table, Comment 3

Plant: Grand Gulf Nuclear Station Year: 2019 I Page 35 of 46 Annual Radiological Environmental Operating Report Page 7 of 15 Monitoring Results Tables Table 13, Thermoluminescent Dosimeters - Outer Ring Analysis: Gamma Dose I Units: mrem Annual Mean Station 1st Qtr 2019 2 nd Qtr 2019 3rd Qtr 2019 4th Qtr 2019 2019 M-36 8.6 9.4 8.3 8.8 8.7 M-40 4.5 4.6 4.9 5.6 4.9 M-48 10.1 10.9 10.1 10.5 10.4 M-49 11.2 11.7 10.7 11.3 11.3 M-50 9.7 10.0 10.2 10.0 10.0 M-55 11.1 11.0 10.9 11.5 11.1 M-5?[Note 1] 11.3 12.4 11.4 11.7 11.7

[Note 1] - Station with highest annual mean.

Table 14, Thermoluminescent Dosimeters - Special Interest Areas Analysis: Gamma Dose Units: mrem I

Annual Mean Station 1st Qtr 2019 2 nd Qtr 2019 3 rd Qtr 2019 4th Qtr 2019 2019 M-01 [Note 1] 10.7 11.8 10.8 12.2 11.4 M-O7 9.9 10.6 10.7 11.0 10.6 M-O9 8.8 9.6 9.7 10.1 9.6 M-10 8.1 8.5 8.3 9.5 8.6 M-33 7.6 8.0 7.5 8.5 7.9 M-38 9.1 9.9 8.9 9.8 9.4 M-39 8.5 9.3 9.2 9.5 9.1

[Note 1] - Station with highest annual mean.

Table 15, Thermoluminescent Dosimeters - Control Analysis: Gamma Dose Units: mrem I

Annual Mean Station 1st Qtr 2019 2nd Qtr 2019 3 rd Qtr 2019 4th Qtr 2019 2019 M-14 10.0 10.9 11.3 10.5 10.7

Plant: Grand Gulf Nuclear Station I Year: 2019 J Page 36 of 46 Annual Radiological Environmental Operating Report Attachment 2 Page 8 of 15 Monitoring Results Tables Table 16, Surface Water-Gamma Analysis: Gamma Isotopic Units: pCi/L Location l 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 REQUIRED LLD + 15 15 30 15 30 15 30 15 15 18 60 15 MRDOWN <8.907 <8.885 <9.608 <5.69 <11.41 <10.69 <7.122 <5.592 <31.77 <12.27 02/04/19 <5.378 <6.151 (Indicator)

MRUP <10.7 <6.186 <11.28 <6.502 <11.18 <10.57 <6.110 <5.571 <33.32 <10.94 02/04/19 <6.285 <6.282 (Control)

MRDOWN <13.42 <8.033 <12.09 <6.928 <11.44 <11.1 <5.409 <5.894 <25.56 <7.213 05/01/19 <5.493 <6.611 (Indicator)

MRDOWNGG <14.89 <6.851 <13.3 <7.449 <13.41 <12.75 <7.704 <6.325 <33.98 <9.87 05/01/19 <6.52 <7.462 (Indicator)

MRUP <11.28 <6.396 <10.58 <4.862 <7.9 <11.42 <5.354 <5.859 <22.21 <9.849 05/01/19 <5.319 <6.094 (Control)

MRUP GG <5.088 <9.184 <5.134 <9.041 <8.199 <4.644 <5.222 <21.92 <8.648 05/01/19 <5.281 <3.763 <10.47 (Control)

MRDOWN <13.51 <7.51 <14.46 <12.24 <5.537 <7.102 <34.71 <7.711 08/08/19 <5.801 <8.109 <13.72 <5.867 (Indicator)

MRDOWNGG <16.24 <7.364 <12.71 <12.48 <7.469 <8.73 <38.35 <11.63 08/08/19 <8.534 <8.466 <15.37 <7.213 (Indicator)

MRUP <10.16 <6.009 <14.35 <10.11 <6.362 <8.444 <29.67 <13.16 08/08/19 <4.172 <7.829 <11.8 <7.760 (Control)

MRUP GG <8.692 <7.261 <11.89 <7.129 <10.63 <8.301 <13.24 <14.3 <9.200 <9.137 <37.15 <11.43 08/08/19 (Control)

Plant: Grand Gulf Nuclear Station I Year: 2019 7 Page 37 of 46

~nnual Radiological Environmental Operating Report Attachment 2 Page 9 of 15 Monitoring Results Tables Table 16, Surface Water- Gamma Analysis: Gamma Isotopic Units: pCi/L 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 MRDOWN*

10/10/19 <6.28 <6.369 <13.39 <7.013 <14.32 <7.989 <10.14 <14.16 <6.530 <6.099 <31.77 <13.05 (Indicator)

MRDOWNGG*

10/10/19 <6.634 <6.209 <14.25 <8.744 <10.48 <6.978 <12.71 <14.15 <7.674 <6.559 <40.81 <9.316 (Indicator)

MRDOWN 11/06/19 <6.846 <7.266 <11.52 <5.136 <14.56 <7.563 <14.1 <10.15 <8.293 <7.861 <34.53 <12.19 (Indicator)

MRDOWNGG 11/06/19 <5.75 <5.599 <12.04 <4.829 <13.23 <6.67 <10.11 <10.19 <5.638 <7.143 <31.73 <9.418 (Indicator)

MRUP 11/06/19 <5.985 <5.706 <13.36 <5.909 <15.23 <5.988 <8.467 <11.85 <7.238 <7.426 <26.73 <10.38 (Control)

MRUP GG 11/06/19 <5.237 <6.342 <11.43 <7.460 <11.79 <6.169 <10.82 <10.46 <6.352 <6.173 <24.60 <7.39 (Control)

GG - indicates duplicate sample

  • - indicates Annual Sample collected during liquid discharge

Plant: Grand Gulf Nuclear Station Year:2019 I Page 38 of 46 Annual Radiological Environmental Operating Report Page 10 of 15 Monitoring Results Tables Table 17, Surface Water-Tritium Analysis: H-3 Units: pCi/L Location Date H-3 REQUIRED LLD + 3000 OUTFALL 007 01/24/19 <569 MRDOWN 02/04/19 <560 MRDOWNGG 02/04/19 <571 MRUP 02/04/19 <582 MRUP GG 02/04/19 <573 OUTFALL 007 02/18/19 <533 OUTFALL 007 GG 02/18/19 <542 OUTFALL 007 03/20/19 <593 OUTFALL 007 04/24/19 <447 OUTFALL 007 GG 04/24/19 <447 MRDOWN 05/01 /19 <494 MRDOWNGG 05/01/19 <510 MRUP 05/01 /19 <498 MRUP GG 05/01/19 <494 OUTFALL 007 05/21/19 <514 OUTFALL 007 06/20/19 1850 OUTFALL 007 GG 06/20/19 2020 OUTFALL 007 07/23/19 1700 MRDOWN 08/08/19 <490 MRDOWNGG 08/08/19 <493 MRUP 08/08/19 <494 MRUP GG 08/08/19 <492 OUTFALL 007 08/21 /19 <532 OUTFALL 007 GG 08/21 /19 <534 OUTFALL 007 09/25/19 <504

GNRO 2020-00012 l Rev.2019 I Page 39 of 46 Annual Radiological Environmental Operating Report Page 11 of 15 Monitoring Results Tables Table 17, Surface Water-Tritium Analysis: H-3 Units: pCi/L Location Date H-3 OUTFALL 007 GG 09/25/19 <510 MRDOWN* 10/10/19 <565 MRDOWNGG* 10/10/19 <559 OUTFALL 007 10/23/19 <558 OUTFALL 007 GG 10/23/19 <544 MRDOWN 11/06/19 <531 MRDOWNGG 11/06/19 <529 MRUP 11/06/19 <537 MRUP GG 11/06/19 <521 OUTFALL 007 11/29/19 <586 OUTFALL 007 GG 11/29/19 <570 OUTFALL 007 12/19/19 1660 OUTFALL 007 GG 12/19/19 1570 GG - indicates duplicate sample

  • - indicates Annual Sample collected during liquid discharge

Plant: Grand Gulf Nuclear Station T Year: 2019 I Page 40 of 46 Annual Radiological Environmental Operating Report Attachment 2 Page 12 of 15 Monitoring Results Tables Table 18, Drinking Water - Gamma, 1-131 Analysis: Gamma Isotopic, 1-131 Units: pCi/L Location Date 1-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 REQUIRED LLD + 1 15 15 30 15 30 15 30 15 18 60 15 CONSTWELL 3 11/13/19 <0.798 <6.168 <6.418 <14.56 <6.594 <12.29 <7.964 <13.16 <6.541 <6.667 <25.98 <10.72 CONSTWELL 3 GG 11/13/19 <0.756 <6.952 <6.692 <12.62 <8.3 <17.8 <6.106 <9.767 <7.917 <5.793 <25.45 <6.679 PGWELL 11/13/19 <0.759 <6.669 <6.092 <12.17 <8.774 <17.36 <8.993 <12.56 <8.448 <7.687 <26.85 <9.866 PGWELL GG 11/13/19 <0.805 <5.317 <6.968 <12.17 <8.732 <14.32 <6.438 <10.4 <8.317 <7.8 <28.42 <11.16 GG - indicates duplicate sample

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 41 of 46 Annual Radiological Environmental Operating Report Page 13 of 15 Monitoring Results Tables Table 19, Drinking Water - Tritium Analysis: H-3 Units: pCi/L Location Date H-3 REQUIRED LLD + 2000 CONSTWELL 3 11/13/19 <516 CONSTWELL 3 GG 11/13/19 <534 PGWELL 11/13/19 <534 PGWELL GG 11/13/19 <524 GG - indicates duplicate sample Table 20, Sediment Analysis: Gamma Isotopic Units: pCi/kg Location Date Cs-134 Cs-137 REQUIRED LLD + 150 180 SEDCONT 09/12/19 <49.59 <46.67 SEDCONTGG 09/12/19 <71.56 <72.99 SEDHAM 09/12/19 <60.12 <46.72 SEDHAM GG 09/12/19 <69.58 <54.31 GG - indicates duplicate sample

Plant: Grand Gulf Nuclear Station Year: 2019 I Page 42 of 46 Annual Radiological Environmental Operating Report Attachment 2 Page 14 of 15 Monitoring Results Tables Table 21, Fish Analysis: Gamma Isotopic Units: pCi/kg Collection Location Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Date REQUIRED LLD + 130 130 260 130 260 130 150 FISHDOWN 09/09/19 <78.56 <71.83 <159.3 <47.8 <103.2 <86.42 <85.66 FISHDOWN GG 09/09/19 <72.55 <68.6 <129.5 <85.93 <145.5 <79.13 <79.49 FISHUP 09/09/19 <53.87 <56.01 <107.3 <58.49 <106.4 <63.92 <47.87 FISHUP GG 09/09/19 <55.76 <50.96 <99.02 <55.83 <95.6 <49.8 <64.44 GG - indicates duplicate sample Table 22, Food Products Analysis: Gamma Isotopic, 1-131 Units: pCi/kg Location Collection Date 1-131 Cs-134 Cs-137 REQUIRED LLD + 60 60 80 VEG-CONT 02/18/19 <37.4 <32.85 <28.46 VEG-J 02/18/19 <34.12 <25.63 <31.57 VEG-CONT 05/22/19 <27.05 <26.88 <23.05 VEG-CONT GG 05/22/19 <25.81 <26.29 <20.65 VEG-J 05/22/19 <21.78 <19.47 <17.8 VEG-J GG 05/22/19 <22.4 <23.17 <19.84 VEG-CONT 08/21/19 <35.92 <23.52 <27.55 VEG-J 08/21/19 <32.15 <23.14 <25.26 VEG-CONT 11/20/19 <38.6 <32.89 <30.79 VEG-CONT GG 11/20/19 <45.19 <34.4 <27.32 VEG-J 11/20/19 <35.97 <27.02 <22.17 VEG-J GG 11/20/19 <37.03 <25.42 <29.5 GG - indicates duplicate sample

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 43 of 46 Annual Radiological Environmental Operating Report Attachment 2 Page 15 of 15 Monitoring Results Tables Table 23, Special Samples, Surface Water Analysis: Gamma Isotopic Units: pCi/L 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 REQUIRED LLD + 15 15 30 15 30 15 30 15 15 18 60 15 OUTFALL 007 03/20/19 <4.877 <7.898 <11.23 <9.876 <17.94 <7.095 <13.15 <14.62 <8.379 <7.225 <34.95 <13.58 OUTFALL 007 06/12/19 <5.078 <4.676 <8.725 <3.151 <11.4 <5.632 <8.462 <13.85 <3.390 <4.737 <30.97 <10.85 OUTFALL 007 GG 06/12/19 <5.041 <4.657 <8.527 <4.716 <6.261 <4.611 <8.926 <13.46 <5.124 <4.894 <34.04 <10.9 OUTFALL 007 09/25/19 <3.54 <4.541 <7.592 <4.810 <8.601 <4.713 <7.984 <13.8 <4.047 <4.318 <32.86 <10.31 OUTFALL 007 GG 09/25/19 <3.946 <4.628 <9.181 <4.307 <8.539 <5.049 <7.767 <13.37 <4.407 <4.025 <32.04 <10.16 GG - indicates duplicate sample Table 24, Special Samples, Meat Analysis: Gamma Isotopic Units: pCi/kg Location I Date Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 REQUIRED LLD + 130 130 260 130 260 130 150 DEER j 10111119 <28.97 <27.14 <59.6 <27.64 <56.74 <26.29 <26.01

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 44 of 46 Annual Radiological Environmental Operating Report Attachment 3 Page 1 of 3 lnterlaboratory Comparison Program Results TELEDYNE BROWN ENGINEERING 1.0 Summary The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

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

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

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

  • Acceptable (flag = "A") - result within +/- 20% of the reference value
  • Acceptable with Warning (flag = "W") - result falls in the +/- 20% to +/-

30% of the reference value

  • Not Acceptable (flag = "N") - bias is greater than 30% of the reference value Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

For the TBE laboratory, 119 out of 129 analyses performed met the specified

Plant: Grand Gulf Nuclear Station l Year: 2019 J Page 45 of 46 Annual Radiological Environmental Operating Report Page 2 of 3 lnterlaboratory Comparison Program Results acceptance criteria. Ten analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program. A summary is found below:

1. The ERA April 2019 water Cs-134 result was evaluated as Not Acceptable. The reported value was 15.2 pCi/L (error 2.82 pCi/L) and the known result was 12.1 pCi/L (acceptance range of 8.39 - 14.4 pCi/L). With the error, the reported result overlaps the acceptable range. This sample was run as the workgroup duplicate on a different detector with a result of 10.7 pCi/L (within acceptable range). (NCR 19-10)
2. The ERA April 2019 water Sr-89 result was evaluated as Not Acceptable.

The reported value was 44.9 pCi/L and the known result was 33.3 pCi/L (acceptance range of 24.5 - 40.1 pCi/L). The sample was only counted for 15 minutes instead of 200 minutes. The sample was re-prepped in duplicate and counted for 200 minutes with results of 30.7 +/- 5.37 pCi/L and 33.0 +/- 8.71 pCi/L. This was the 1st "high" failure for Sr-89 in 5 years.

(NCR 19-11)

3. The MAPEP February 2019 soil Sr-90 result was not submitted and therefore evaluated as Not Acceptable. The sample was run in duplicate, with results of -1.32 +/- 4.09 Bq/kg (<6.87) and -1.030 +/- 3.55 Bq/kg (<5.97).

The known result was a false positive test (no significant activity). TBE did not submit a result because it appeared that the results may not be accurate. TBE analyzed a substitute soil Sr-90 sample from another vendor, with a result within the acceptable range. (NCR 19-12)

4. The MAPEP February 2019 water Am-241 result was evaluated as Not Acceptable. The reported value was 0.764 +/- 0.00725 Bq/L with a known result of 0.582 Bq/L (acceptable range 0.407 - 0. 757 Bq/L). TBE's result falls within the upper acceptable range with the error. It appeared that a non-radiological interference was added and lead to an increased mass and higher result. (NCR 19-13)
5. The MAPEP February 2019 vegetation Sr-90 result was evaluated as Not Acceptable. The reported result was -0.1060 +/- 0.0328 Bq/kg and the known result was a false positive test (no significant activity). TBE's result was correct in that there was no activity. MAPEP's evaluation was a "statistical failure" at 3 standard deviations. (NCR 19-14)
6. The ERA October 2019 water Gross Alpha result was evaluated as Not Acceptable. TBE's reported result was 40.5 +/- 10.3 pCi/L and the known result was 27.6 pCi/L (ratio of TBE to known result at 135%). With the associated error, the result falls within the acceptable range (14.0 - 36.3 pCi/L). The sample was run as the workgroup duplicate on a different detector with a result of 30.8 +/- 9.17 pCi/L (within the acceptable range).

Plant: Grand Gulf Nuclear Station I Year: 2019 I Page 46 of 46 Annual Radiological Environmental Operating Report Page 3 of 3 lnterlaboratory Comparison Program Results This was the first failure for drinking water Gr-A since 2012. (NCR 19-23)

7. The ERA October 2019 water Sr-90 result was evaluated as Not Acceptable. TBE's reported result was 32.5 +/- 2.12 pCi/L and the known result was 26.5 pCi/L (ratio of TBE to known result at 123%). With the associated error, the result falls within the acceptable range (19.2 - 30.9 pCi/L). The sample was run as the workgroup duplicate on a different detector with a result of 20.0 +/- 1.91 pCi/L (within the acceptable range).

Both TBE results are within internal QC limits. A substitute "quick response" sample was analyzed with an acceptable result of 20.1 pCi/L (known range of 13.2 - 22.1 pCi/L). (NCR 19-24)

8. The MAPEP August 2019 soil Ni-63 result of 436 +/- 22.8 Bq/kg was evaluated as Not Acceptable. The known result was 629 Bq/kg (acceptable range 440 - 818 Bq/kg). With the associated error, the TBE result falls within the lower acceptance range. All associated QC was acceptable. No reason for failure could be found. This is the first failure for soil Ni-63 since 2012. (NCR 19-25).
9. The MAPEP August 2019 water Am-241 result was not reported and therefore evaluated as Not Acceptable. Initial review of the results showed a large peak where Am-241 should be (same as the February, 2019 sample results). It is believed that Th-228 was intentionally added as an interference. The sample was re-prepped and analyzed using a smaller sample aliquot. The unusual large peak (Th-228) was seen again and also this time a smaller peak (Am-241 ). The result was 436 +/- 22.8 Bq/L (acceptable range 0.365 +/- 0.679 Bq/L). Th-228 is not a typical nuclide requested by clients, so there is no analytical purpose to take samples through an additional separation step. TBE will pursue using another vendor for Am-241 water cross-checks that more closely reflects actual customer samples. (NCR 19-26)
10. The Analytics September 2019 soil Cr-51 sample was evaluated as Not Acceptable. TBE's reported result of 0.765 +/- 0.135 pCi/g exceeded the upper acceptance range (140% of the known result of 0.547 pCi/g). The TBE result was within the acceptable range (0.63 - 0.90 pCi/g) with the associated error. The Cr-51 result is very close to TBE's normal detection limit. In order to get a reportable result, the sample must be counted for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> (1 Ox longer than client samples). There is no client or regulatory requirement for this nuclide and TBE will remove Cr-51 from the reported gamma nuclides going forward. (NCR 19-27)

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

Retrieved from "https://kanterella.com/w/index.php?title=ML20108F575&oldid=2772355"