ML24130A236
| ML24130A236 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/09/2024 |
| From: | Borgen T Northern States Power Company, Minnesota, Xcel Energy |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-Pl-24-020 | |
| Download: ML24130A236 (1) | |
Text
(l Xcel Energy*
May 09, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 Prairie Island Independent Spent Fuel Storage Installation Docket No. 72-10 Renewed Materials License No. SNM-2506 1717 Wakonade Drive Welch, MN 55089 L-Pl-24-020 Tech Spec 5.6.2 ISFSI Tech Spec 5.2 2023 Annual Radiological Environmental Monitoring Program Report Pursuant to the requirements of Prairie Island Nuclear Generating Plant Technical Specificati ons, Section 5.6.2 and ISFSI Technical Specifications, Section 5.2, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits the enclosed Annual Radiological Environmental Monitoring Program Report for the period of January 1, 2023 through December 31, 2023.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
J3>>_d Timothy P. Borgen Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure Document Control Desk L-PI-24-020 Page 2
cc: Administrator, Region III, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator
ENCLOSURE
ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION
Radiological Environmental Monitoring Program
JANUARY 1, 2023 - DECEMBER 31, 2023
73 pages to follow
©) MICROBAC"
700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517
XCEL ENERGY CORPORATION
PRAIRIE ISLAND NUCLEAR GENERATING PLANT
ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION
Radiological Environmental Monitoring Program
January 1 to December 31, 2023
Docket No. 50-282 Renewed Operating License No. DPR-42 Docket No. 50-306 Renewed Operating License No. DPR-60
ISFSI Docket No. 72-10 Renewed License No. SNM-2506
Prepared under Contract by
Microbac Laboratories - Northbrook
Project No. 8010
Approved:
Ashok Banavali, Ph.D.
Laboratory Manager PREFACE
The staff of Microbac Laboratories - Northbrook was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Northern States Power Co. - Minnesota, for XCEL Energy Corporation.
The report was prepared by Microbac Laboratories - Northbrook.
ii TABLE OF CONTENTS
Section Page
Preface.................................................................................................................................................... ii
List of Tables.......................................................................................................................................... iv
List of Figures.......................................................................................................................................... v
1.0 INTRODUCTION
..................................................................................................................................... 1
2.0
SUMMARY
.............................................................................................................................................. 2
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)............................................ 3
3.1 Program Design and Data Interpretation....................................................................................... 3 3.2 Program Description...................................................................................................................... 4 3.3 Program Execution........................................................................................................................ 5 3.4 Laboratory Procedures.................................................................................................................. 5 3.5 Program Modifications................................................................................................................... 5 3.6 Land Use Census.......................................................................................................................... 6
4.0 RESULTS AND DISCUSSION................................................................................................................ 7
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents............................................................ 7
4.2 Summary of Preoperational Data.................................................................................................. 7
4.3 Program Findings.......................................................................................................................... 8
5.0 FIGURES AND TABLES........................................................................................................................ 12
6.0 REFERENCES
CITED.......................................................................................................................... 24
APPENDICES
A Interlaboratory Comparison Program Results....................................................................................... A-1 Attachment A, Acceptance Criteria for "Spiked" Samples................................................................ A-2
B Data Reporting Conventions................................................................................................................. B-1
C Annual Average Effluent Concentration Limits of Radioactivity in Air and Water Above Background in Unrestricted Areas.......................................................................................... C-1
D Sampling Location Maps..................................................................................................................... D-1
E Special Well and Surface Water Samples........................................................................................... E-1
iii LIST OF TABLES
No. Title Page
5.1 Sample Collection and Analysis Program................................................................................................. 15
5.2 Sampling Locations................................................................................................................................... 16
5.3 Missed Collections and Analyses.............................................................................................................. 19
5.4 Radiological Environmental Monitoring Program Summary...................................................................... 20
In addition, the following tables can be found in the Appendices:
Appendix A
A-1 Environmental Resources Associates, Crosscheck Program Results.....................................................A1-1
A-2 Program Results; (TLDs)..................................................................................................................... A2-1
A-3 In-house "Spiked" Samples................................................................................................................. A3-1
A-4 In-house Blank Samples...................................................................................................................... A4-1
A-5 In-house "Duplicate" Samples........................................................................................................................A5-1
A-6 Department of Energy MAPEP comparison results.................................................................................A6-1
A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement)............A7-1
Appendix C
C-1 Average Annual Effluent Concentration Limits of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas................................................................................. C-2
Appendix E
E-4.1 Sample collection and analysis program................................................................................................ E-5
E-4.2 Sampling locations................................................................................................................................. E-6
E-4.3 REMP Summary..................................................................................................................................... E-8
E-4.4 REMP Complete Data Tables................................................................................................................ E-9
E-4.5 Supplementary Data Tables.................................................................................................................. E-14
iv LIST OF FIGURES
No. Title Page
5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control............................................................................................................................... 13
5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6,7) versus control location (P-1).................................................................................... 14
MAPS
Appendix D Title Page
TLD locations within a one mile radius..................................................................................................... D-2 TLD locations, Controls.............................................................................................................................. D-3 TLD locations, surrounding the ISFSI Area................................................................................................ D-3 TLD locations within a five mile radius..................................................................................................... D-4
REMP sampling points within a one mile radius...................................................................................... D-5 REMP sampling points within a five mile radius....................................................................................... D-6 REMP sampling points, Control locations............................................................................................... D-7
Appendix E
Groundwater Monitoring Well locations................................................................................................... E-15
v
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Microbac Laboratories - Northbrook at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2023.
This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulations of the individual analyses made during the year are not included in this report.
These data are included in a reference document (Microbac Laboratories - Northbrook, 2023b) available at Prairie Island Nuclear Generating Plant.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-
Minnesota. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.
1 2.0
SUMMARY
The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 2023 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
3.1 Program Design and Data Interpretation
The purpose of the Radiological Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1) Natural background radiation arising from cosmic rays and primordial radionuclides;
(2) Fallout from atmospheric nuclear detonations;
(3) Releases from nuclear power plants;
(4) Industrial and medical radioactive waste; and
(5) Fallout from nuclear accidents.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plants monitoring program includes analyses for tritium and iodine-131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10%
of the total activity of fission products 10 days after reactor shutdown. Alternatively, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered radiological impact indicators.
The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and - 60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plants effluents, but are not produced in significant quantities by nuclear detonations.
3 3.1 Program Design and Data Interpretation (continued)
Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the plants monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
3.2 Program Description
The sampling and analysis schedule for the radiological environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2022). Maps of fixed sampling locations are included in Appendix D.
To monitor the airborne environment, air is sampled by continuous pumping at six stations, four site boundary indicators (P-2, P-3, P-4 and P-7), located in the highest calculated D/Q sectors, one community indicator (P-6), and one control (P-1). The particulates are collected on membrane filters, airborne iodine is trapped by activated charcoal canisters. Particulate filters are analyzed for gross beta activity and charcoal canisters for iodine-131. Quarterly composites of particulate filters from each location are analyzed for gamma-emitting isotopes.
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI)
Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
To monitor the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from five locations near the plant and analyzed for tritium and gamma-emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
4 3.2 Program Description (continued)
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution
The Program was executed as described in the preceding section in 2023 with the following exception:
(1) Airborne Particulates /Airborne Iodine
The air sampler at location P-4 was found not running. No power was available due to loss of power to various buses from U-1 Plant trip 10/19/23. Power was restored 10/26/23. The sample for the week of 10/26/23 was declared missing due to insufficient running time.
3.4 Laboratory Procedures
The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses were performed using high-purity germanium (HPGe) detectors.
Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
Tritium concentrations were determined by liquid scintillation.
Analytical Procedures used by Microbac Laboratories - Northbrook are on file and are available for inspection. Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Department of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Microbac Laboratories - Northbrook has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Microbac Laboratories - Northbrook, 2023). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Program Modifications
None.
5 3.6 Land Use Census
In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest residence, nearest milk animals, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and September 30. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiological environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after September of the year in which the land use census was conducted.
This land use census ensures the updating of the radiological environmental monitoring program should sampling locations change within the 5-mile radius from the plant.
The Land Use Census was conducted during September 2023. The ranking of the highest D/Q garden remained the same for 2023 as 2022, 5016 Lock & Dam Rd., Welch, MN (SSE at 0.6 miles). The highest D/Q residence remained the same for 2023 as for 2022, 1860 Edoka St.,
Welch, MN (WNW at 0.7 miles).
The Minnesota and Wisconsin Departments of Natural Resources were both consulted and both confirmed that no irrigation permits had been issued the past year for crop fields within the file mile Mississippi River area downstream of the Prairie Island Plant. Plant biologists conducted visual surveys while electro-fishing and visual observations were taken while driving. No irrigating was observed. Therefore, no crop sampling was performed.
There are no dairy farms within a 5-mile radius of the plant therefore no milk samples were collected.
Vegetation samples were taken from three close gardens in the vicinity of the plant this year plus a control site.
There were no land use changes within five miles of the plant resulting in new special interest areas such as: new population centers, new residences, new schools or recreation centers.
6 4.0 RESULTS AND DISCUSSION
All scheduled collections and analyses were made in 2023 except those listed in Table 5.3..
The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents
There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2023. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
There were no reported atmospheric nuclear tests in 2020. The last reported test was conducted on October 16, 1980 by the Peoples Republic of China.
4.2 Summary of Preoperational Data
The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m3 to 1,020 pCi/m3, and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during pre-operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m3.
3 Average present day levels have stabilized at around 0.025 pCi/m. Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, I-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and I-131 are below detection levels.
Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137.
Gross beta measured in soil averaged 52 pCi/g.
The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish, aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium measure below a detection limit of approximately 160 pCi/L. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well water, and11.0 pCi/L for lake water. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g, 46.0 pCi/g, and 13.6 pCi/g, respectively.
7 4.3 Program Findings
Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi.
distant from the Plant, at special interest areas and at one control location. The means were from 15.8 mR/91 days at both the inner ring and outer ring locations. The mean at special interest locations was 15.4 mR/91 days and 16.3 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were comparable to 2022 dose rates and consistent with results from previous years. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).
Average (Inner and Average (Inner and Year Outer Rings) Control Year Outer Rings) Control 2001 16.8 17.2 2013 15.1 16.0
2002 17.4 16.9 2014 15.3 16.2 2003 16.2 16.0 2015 16.0 17.4 2004 17.6 17.6 2016 16.7 17.4 2005 16.8 16.3 2017 16.1 16.3 2006 16.6 16.6 2018 16.6 17.4 2007 17.5 17.7 2019 15.8 15.3 2008 16.9 17.1 2020 15.4 14.2 2009 15.9 16.3 2021 16.4 15.9 2010 16.0 16.0 2022 16.7 17.5 2011 15.7 15.7 2023 15.8 16.3 2012 16.5 16.5
Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR/91 days).
ISFSI Facility Operations Monitoring
Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 197.8 mR/91 days inside the ISFSI earth berm and 23.6 mR/91 days outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2023, a total of fifty loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.
Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. The cumulative average of the two special Prairie Island Indian Community TLDs (Locations P-07S and P-08S) measured 14.7 and 15.3 mR/91 days.
Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, TN-40 Dose Rates at Short Distances. Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
8 Airborne Particulates
Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1999 through 2006, and also in 2008 through 2019. The elevated activity observed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading.
Average annual gross beta concentrations in airborne particulates were 0.033 pCi/m3 for both the indicator and control locations and are similar to levels observed from 1999 through 2006 and 2008 to 2022. The results are tabulated below.
Average of Year Indicators Control Concentration (pCi/ m3)
2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 2008 0.028 0.027 2009 0.029 0.029 2010 0.025 0.025 2011 0.026 0.027 2012 0.031 0.032 2013 0.027 0.028 2014 0.026 0.026 2015 0.029 0.029 2016 0.027 0.027 2017 0.026 0.025 2018 0.027 0.027 2019 0.023 0.023 2020 0.027 0.025 2021 0.030 0.029 2022 0.030 0.031 2023 0.033 0.033 Average annual gross beta concentrations in airborne particulates.
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples, with an average activity of 0.074 pCi/m3 for indicator locations and 0.068 pCi/m3 at the control location. All other isotopes were below the lower limit of detection.
There was no indication of a plan t effect.
Airborne Iodine
Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m3 in all samples. There was no indication of a pla nt effect.
9 Drinking Water
In drinking water from the City of Red Wing well, tritium activity measured below a detection limit of 169 pCi/L for all samples.
Gross beta concentrations averaged 9.8 pCi/L throughout the year, ranging from 7.1-13.7 pCi/L.
These concentrations are consistent with the 2022 average of 8.9 pCi/L and with levels observed from 2000 through 2021. The most likely contribution is the relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2023 data of any effect of plant operation.
Year Gross Beta concentration (pCi/L)
2000 10.1 2001 8.3 2002 8.7 2003 9.9 2004 9.8 2005 11.5 2006 13.4 2007 11.6 2008 11.6 2009 11.4 2010 11.7 2011 12.4 2012 11.8 2013 12.2 2014 11.5 2015 11.4 2016 12.3 2017 10.1 2018 10.2 2019 9.7 2020 8.6 2021 9.2 2022 8.9 2023 9.8 Average annual gross beta concentrations in drinking water.
River Water
Analyses for H-3 in river water was below an LLD of 161 pCi/L for the four quarterly composites from the upstream location for 2023. H-3 was detected at the River Water Lock and Dam #3 location P-6 in the second quarter composite sample at a concentration of 419 +/- 97 pCi/L. The original sample vial was reanalyzed with a result of 324 +/- 94 pCi/L. Further analysis of the constituent monthly and weekly samples identified positive results for the May composite of (897 +/- 120 pCi/L), and weekly samples from 5/3/23 (3670 +/- 202 pCi/L) and from 5/30/23 (306 +/- 93 pCi/L). All other samples analyzed from location P-6 were below an MDC of 169 pCi/L. The positive H-3 results are due to the samples being taken during routine radioactive liquid releases from the plant. Gamma-emitting isotopes were below detection limits in all samples.
10 Well Water
Water samples tested from the control well, P-43 (Peterson Farm) and from four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm) showed no tritium detected above a detection limit of 173 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2023 show no radiological effects of the plant operation.
Broadleaf Vegetation and Crops
Four samples of broadleaf vegetation, cabbage leaves, were collected in August 2023 and analyzed for gamma-emitting isotopes, including iodine-131. The I-131 level was below 0.032 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-7 and potassium-40, all other gamma-emitting isotopes were below their respective detection limits.
There was no indication of a plant effect.
Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within five miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required since the fields have not been irrigated.
Fish
Fish were collected in June and September 2023 and analyzed for gamma-emitting isotopes.
Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.
Aquatic Insects or Periphyton
Aquatic insects (invertebrates) or periphyton were collected in June and October 2023 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes measured below detection limits with the exception of naturally occurring potassium-40 which was detected in all four samples. There was no indication of any plant effect.
Bottom and Shoreline Sediments
Upstream and downstream bottom sediments and downstream recreational area shoreline sediments were sampled in June and October 2023. All gamma-emitting isotopes measured below detection limits with the exception of naturally occurring beryllium-7 and potassium-40.
Beryllium-7 was detected at the upstream bottom sediment sample taken from location P-20 in October and potassium-40 was detected in all four bottom sediment samples and both shoreline sediment samples. There was no indication of any plant effect.
11 5.0 FIGURES AND TABLES
12 13
111A-Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.
Collection Analysis Location Type and Type and No. Codes (and Type)a Frequencyb Frequencyc Medium
Ambient radiation (TLD's) 54 P-01A - P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-08S P-01IA - P-08IA P-01IB - P-08IB P-01IX-P-04IX, P-01C
Airborne Particulates 6 P-1(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6, P-7 each location)
Airborne Iodine 6 P-1(C), P-2, P-3, P-4, P-6, P-7 C/W I-131
River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC)
Drinking water 1 P-11 G/W GB(MC), I-131(MC)
Well water 5 P-6, P-8, P-9, P-24, G/Q H-3, GS P-43 (C)
Edible cultivated crops 1 P-30(C) G/A GS (I-131)
Leafy green vegetables 4 P-8, P-24, P-28, P-38(C) G/A GS (I-131)
Fish (three species, edible portion) 2 P-19(C), P-13 G/SA GS
Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS
Bottom sediment 2 P-20(C), P-6 G/SA GS
Shoreline sediment 1 P-12 G/SA GS
a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.
b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, I-131 = iodine-131.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
15
111A-Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction Code Typea Collection Site Sample Typeb from Reactor
Air Station P-1 AP, AI 11.8 mi @ 316o/NNW P-1 C P-2 Air Station P-2 AP, AI 0.5 mi @ 294o/WNW P -3 Air Station P-3 AP, AI 0.8 mi @ 313o/NW P -4 Air Station P-4 AP, AI 0.4 mi @ 359o/N P -5 C Upstream of Plant RW 1.8 mi @ 11o/N
P-6 Lock and Dam #3 & Air Station P-6 AP, AI, RW 1.6 mi @ 129o/SE WW, BS, BOc P-7 Air Station P-7 AP, AI 0.5 mi @ 271o/W P-8 Community Center WW 1.0 mi @ 321o/WNW P-9 Plant Well #2 WW 0.3 mi @ 306o/NW P-11 Red Wing Service Center DW 3.3 mi @ 158o/SSE P-12 Downstream of Plant SS 3.0 mi @ 116o/ESE P-13 Downstream of Plant Fc 3.5 mi @ 113o/ESE
P-19 C Upstream of Plant Fc 1.3 mi @ 0o/N P-20 C Upstream of Plant BS 0.9 mi @ 45o/NE P-24 Suter Residence WW 0.6 mi @ 158o/SSE P-28 Hager Residence VE 1.0 mi @ 152o/SSE P-38 C Cain Residence VE 14.2 mi @ 359o/N P-40 C Upstream of Plant BOc 0.4 mi @ 0o/N P-43 C Peterson Farm WW 13.9 mi. @ 355o/N
General Area of the Site Boundary
P-01A Property Line TLD 0.4 mi @ 359o/N P-02A Property Line TLD 0.3 mi @ 10o/N P-03A Property Line TLD 0.5 mi @ 183o/S P-04A Property Line TLD 0.4 mi @ 204o/SSW P-05A Property Line TLD 0.4 mi @ 225o/SW P-06A Property Line TLD 0.4 mi @ 249o/WSW P-07A Property Line TLD 0.4 mi @ 268o/W P-08A Property Line TLD 0.4 mi @ 291o/WNW P-09A Property Line TLD 0.7 mi @ 317o/NW P-10A Property Line TLD 0.5 mi @ 333o/NNW
16
111A-Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Typea Collection Site Sample Typeb from Reactor
Approximately 4 to 5 miles Distant from the Plant
P-01B Thomas Killian Residence TLD 4.7 mi @ 355o/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 17o/NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 46o/NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 61o/ENE P-05B County Road E and Coulee TLD 4.2 mi @ 102o/ESE P-06B William Hauschildt Residence TLD 4.4 mi @ 112o/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140o/SE P-08B David Wnuk Residence TLD 4.1 mi @ 165o/SSE P-09B Highway 19 South TLD 4.2 mi @ 187o/S P-10B Cannondale Farm TLD 4.9 mi @ 200o/SSW P-11B Wallace Weberg Farm TLD 4.5 mi @ 221o/SW P-12B Ray Gergen Farm TLD 4.6 mi @ 251o/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270o/W P-14B David J. Anderson Farm TLD 4.9 mi @ 306o/NW P-15B Holst Farms TLD 3.8 mi @ 345o/NNW
Special Interest Locations
P-01S Federal Lock & Dam #3 TLD 1.6 mi @ 129o/SE P-02S Charles Suter Residence TLD 0.5 mi @ 155o/SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 173o/S P-04S Richard Burt Residence TLD 2.0 mi @ 202o/SSW P-05S Kinney Store TLD 2.0 mi @ 270o/W P-06S Earl Flynn Farm TLD 2.5 mi @ 299o/WNW P-07S Indian Community TLD 0.7 mi @ 271o/W P-08S Indian Community TLD 0.7 mi @ 287o/WNW P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331o/NNW
17
111A-Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Typea Collection Site Sample Typeb from ISFSI Center.
ISFSI Area Inside Earth Berm
P-01IA ISFSI Nuisance Fence TLD 190' @ 45o/NE P-02IA ISFSI Nuisance Fence TLD 360' @ 82o/E P-03IA ISFSI Nuisance Fence TLD 370' @ 100o/E P-04IA ISFSI Nuisance Fence TLD 200' @ 134o/SE P-05IA ISFSI Nuisance Fence TLD 180' @ 219o/SW P-06IA ISFSI Nuisance Fence TLD 320' @ 258o/WSW P-07IA ISFSI Nuisance Fence TLD 320' @ 281o/WNW P-08IA ISFSI Nuisance Fence TLD 190' @ 318o/NW P-01IX ISFSI Nuisance Fence TLD 140' @ 180o/S P-02IX ISFSI Nuisance Fence TLD 310' @ 270o/W P-03IX ISFSI Nuisance Fence TLD 140' @ 0o/N o
P-04IX ISFSI Nuisance Fence TLD 360' @ 90 /E
ISFSI Area Outside Earth Berm
P-01IB ISFSI Berm Area TLD 340' @ 3o/N P-02IB ISFSI Berm Area TLD 380' @ 28o/NNE P-03IB ISFSI Berm Area TLD 560' @ 85o/E P-04IB ISFSI Berm Area TLD 590' @ 165o/SSE P-05IB ISFSI Berm Area TLD 690' @ 186o/S P-06IB ISFSI Berm Area TLD 720' @ 201o/SSW P-07IB ISFSI Berm Area TLD 610' @ 271o/W P-08IB ISFSI Berm Area TLD 360' @ 332o/NNW
a "C" type denotes control location. All other locations are indicators.
b Sample Codes:
AP Airborne particulates F Fish AI Airborne Iodine SS Shoreline Sediments BS Bottom (river) sediments SW Surface Water BO Bottom organisms VE Vegetation/vegetables (periphyton or macroinvertebrates) WW Well water DW Drinking water c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
18
111A-Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed with the following exceptions:
Sample Analysis Location Collection Reason for not Plan for Type Date or Conducting REMP Preventing Period as Required Recurrence
AP Gross P-4 10/26/23 Sampler was found not Power was Beta running due to an outage. restored.
AI I-131 P-4 10/26/23 Sampler was found not Power was running due to an outage. restored.
19
111A-Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January -December, 2023
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse
Direct Radiation
TLD (Inner Ring, Gamma 40 3.0 15.8 (40/40) P-06A Property Line 18.7 (4/4) (See Control 0 Area at Site (12.1-20.4) 0.4 mi @ 249° /WSW (15.9-20.4) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 60 3.0 15.8 (60/60) P-04B, Nelson Drive 19.6 (4/4) (See Control 0 4-5 mi. distant) (11.5-23.9) 4.2 mi @ 61o/ENE (17.1-23.9) below.)
mR/91 days)
TLD (Special Gamma 32 3.0 15.4 (32/32) P-04S, Richard Burt, 18.9 (4/4) (See Control 0 Interest Areas) (11.1-20.6) 2.2 mi @ 202° /SSW (15.9-20.4) below.)
mR/91 days)
TLD (Control) Gamma 4 3.0 None P-01C, Robert Kinneman 16.3 (4/4) 16.3 (4/4) 0 mR/91 days) 11.1 mi @ 331° /NNW (14.7-18.1) (14.7-18.1)
Airborne Pathway
P-02, Air Station 0.034 (53 /53)
GB 317 0.005 0.033 (264/264) 0.5 mi @ 294° /WNW (0.014-0.095) / 0.033 (53/53) 0 Airborne (0.013-0.095) & P-06, Air Station 0.034 (53/53) (0.013-0.101)
Particulates 1.6 mi. @ 129° /SE 129 (0.013-0.086)
GS 24 Be-7 0.015 0.074 (20/20) P-06, Air Station 0.076 (4/4) 0.068 (4/4) 0 (0.044-0.099) 1.6 mi @ 129° /SE (0.057-0.088) (0.051-0.087)
Mn-54 0.0007 < LLD ) < LLD 0 Co-58 0.0010 < LLD - - < LLD 0 Co-60 0.0014 < LLD - - < LLD 0 Zn-65 0.0035 < LLD - - < LLD 0 Zr-Nb-95 0.0018 < LLD - - < LLD 0 Ru-103 0.0011 < LLD - - < LLD 0 Ru-106 0.0066 < LLD - - < LLD 0 Cs-134 0.0008 < LLD - - < LLD 0 Cs-137 0.0010 < LLD - - < LLD 0 Ba-La-140 0.0038 < LLD - - < LLD 0 Ce-141 0.0021 < LLD - - < LLD 0 Ce-144 0.0038 < LLD - - < LLD 0
Airborne Iodine (pCi/m3) I-131 317 0.030 < LLD - - < LLD 0
20
111A-Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306
Location of Facility Goodhue, Minnesota Reporting Period January -December, 2023
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine Analysesa c (Units) Range Locationd Rangec Rangec Resultse
Terrestrial Pathway
Crops - Cabbage I-131 4 0.032 < LLD - - < LLD 0 (pCi/gwet)
Well Water H-3 20 173 < LLD - - < LLD 0 (pCi/L)
GS 20 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 46 < LLD - - < LLD 0
21
111A-Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306
Location of Facility Goodhue, Minnesota Reporting Period January-December, 2023
( County, state )
Sample Type and Indicator Location with Highest Control Number Number of Locations Annual Mean Locations Non-Type a LLDb Mean (F)c Mean (F)c c (Units) Analyses Rangec c Mean (F) Routine Locationd Range Rangec Resultse
Waterborne Pathway Drinking Water GB 12 1.0 9.8 (12/12) P-11, Red Wing S.C. 9.8 (12/12) None 0 (pCi/L) (7.1-13.7) 3.3 mi @ 158° /SSE (7.1-13.7)
I-131 12 1.0 < LLD - - None 0 H-3 4 169 < LLD - - None 0 GS 12 - -
Mn-54 10 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 10 < LLD - - None 0 Co-60 10 < LLD - - None 0 Zn-65 30 < LLD - - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 10 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 44 < LLD - - None 0
River Water H-3 8 169 419 (1/4) P-6, Lock and Dam #3 419 (1/4) < LLD 0 1.6 mi @ 129° /SE (pCi/L) GS 24
Mn-54 10 < LLD - - < LLD 0 Fe -59 30 < LLD - - < LLD 0 Co -58 10 < LLD - - < LLD 0 Co -60 10 < LLD - - < LLD 0 Zn -65 30 < LLD - - < LLD 0 Zr -Nb -95 15 < LLD - - < LLD 0 Cs -134 10 < LLD - - < LLD 0 Cs -137 10 < LLD - - < LLD 0 Ba -La -140 15 < LLD - - < LLD 0 Ce -144 54 < LLD - - < LLD 0
Fish GS 12 (pCi/g wet) K-40 0.10 3.2 4 (6/6) P -19, Upstream 3.48 (6/6) 3.48 (6/6) 0 (2.53 -3.80 ) 1.3 mi @ 0° /N (2.72-4.25) (2.72-4.25)
Mn-54 0.018 < LLD - - < LLD 0 Fe -59 0.0 64 < LLD - - < LLD 0 Co -58 0.0 26 < LLD - - < LLD 0 Co -60 0.0 44 < LLD - - < LLD 0 Zn -65 0.036 < LLD - - < LLD 0 Zr -Nb -95 0.0 28 < LLD - - < LLD 0 Cs -134 0.0 33 < LLD - - < LLD 0 Cs -137 0.0 37 < LLD - - < LLD 0 Ba -La -140 0.137 < LLD - - < LLD 0
22
111A-Table 5.4 Radiological Environmental Monitoring Program Summary
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December 2023
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse
Waterborne Pathway Invertebrates GS 4 (pCi/g wet)
Be-7 0.104 < LLD - - < LLD 0 K-40 0.37 1.07 (2/2) P-6, Lock & Dam #3 1.07 (2/2) 0.91 (2/2) 0 (0.59-1.55) 1.6 mi @ 129° /SE (0.59-1.55) (0.26-1.55)
Mn-54 0.009 < LLD - - < LLD 0 Co -58 0.0 11 < LLD - - < LLD 0 Co -60 0.0 10 < LLD - - < LLD 0 Zn -65 0.0 18 < LLD - - < LLD 0 Zr -Nb -95 0.0 19 < LLD - - < LLD 0 Ru -103 0.0 18 < LLD - - < LLD 0 Ru -106 0.1 20 < LLD - - < LLD 0 Cs -134 0.0 13 < LLD - - < LLD 0 Cs -137 0.0 08 < LLD - - < LLD 0 Ba -La -140 0.060 < LLD - - < LLD 0 Ce -141 0.0 33 < LLD - - < LLD 0 Ce -144 0.0 57 < LLD - - < LLD 0
Bottom and GS 6 Shoreline 83(1/2)
< lld P -20, Upstream of Plant Sediments Be -7 0.1 1 < LLD 0.9 mi @ 45° /NE 0.25 (1/2) 0.25 (1/2) 0
(pCi/g dry) K-40 6.89 (4/4) P-20, Upstream of Plant 8.91 (2/2) 8.90 (2/2) 0 (4.95-8.66) 0.9 mi @ 45° /NE (8.17-9.64) (8.17-9.64)
Mn-54 0.012 < LLD - - < LLD 0 Co-58 0.015 < LLD - - < LLD 0 Co-60 0.013 < LLD - - < LLD 0 Zn-65 0.033 < LLD - - < LLD 0 Zr-Nb-95 0.021 < LLD - - < LLD 0 Ru-103 0.020 < LLD - - < LLD 0 Ru-106 0.105 < LLD - - < LLD 0 Cs-134 0.015 < LLD - - < LLD 0 Cs-137 0.011 < LLD - - < LLD 0 Ba-La-140 0.097 < LLD - - < LLD 0 Ce-141 0.031 < LLD - - < LLD 0 Ce-144 0.069 < LLD - - < LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations
is indicated in parentheses (F).
d Locations are specified: (1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
e Non -routine results are those which exceed ten times the control station value. If no control station value is available, the
result is considered non -routine if it exceeds ten times the typical preoperational value for the medium or location.
23
111A-
6.0 REFERENCES
CITED
Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
Environmental, Inc., Midwest Laboratory.
2001a through 2021a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2019.
2001b through 2023b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2023.
1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.
1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December, 1978 through 1982.
2022. Quality Manual, Rev. 8, 17 October 2022.
2012. Quality Assurance Program Manual, Rev. 3, 14 November 2012.
2022. Quality Control Procedures Manual, Rev. 5, 9 May 2022.
2009. Quality Control Program, Rev. 2, 12 November 2009.
Microbac Laboratories - Northbrook (Before June 1, 2023 Environmental Inc.)
_________2023. Quality Manual, Rev 9, 25 August 2023
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Northern States Power Company.
1972 through 1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971, 1972, 1973. Minneapolis, Minnesota.
1979 to 2008. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2007. Minneapolis, Minnesota.
Prairie Island Nuclear Generating Plant, 2013. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
24
111A-
6.0 REFERENCES
CITED (continued)
U.S. Environmental Protection Agency.
1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
2012. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981-2009.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
Xcel Energy Corporation.
2009 to 2022. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2021. Minneapolis, Minnesota.
2009 to 2022. Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2021.
Minneapolis, Minnesota
25
111A-
A-1 A-2
A-3
A-4 A-5 A-6
A-7 A-8
A-9
A-10
A-11
A-12
A-13
A-14
A-15
A-16
Appendix B
Data Reporting Conventions
APPENDIX B. DATA REPORTING CONVENTIONS
Data Reporting Conventions
1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements
Each single measurement is reported as follows: x +/- s where: x = value of the measurement; s = 2 counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66 uncertainty for a background sample.
3.0. Duplicate analyses
If duplicate analyses are reported, the convention is as follows. :
3.1 Individual results: For two analysis results; x1 +/- s1 and x2 +/- s2
Reported result: x +/- s; where x = (1/2) (x1 + x2) and s = (1/2)
3.2. Individual results: < L1, < L2 Reported result: < L, where L = lower of L1 and L2
3.3. Individual results: x +/- s, < L Reported result: x +/- s if x L; < L otherwise.
4.0. Computation of Averages and Standard Deviations
4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average and standard deviation s of a set of n numbers x1, x2... xn are defined as follows:
1 (x- )2
= n x s = n-1
4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
B-1
Appendix C
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas APPENDIX C
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCi/m3) Water (pCi/L)
Gross alpha 1 x 10-3 Strontium-89 8,000
Gross beta 1 Strontium-90 500
Iodine-131b 2.8 x 10-1 Cesium-137 1,000
Barium-140 8,000
Iodine-131 1,000 Potassium-40 c 4,000
Gross alpha 2
Gross beta 10 Tritium 1 x 106
a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
C-1 APPENDIX D
Sample Collection and Analysis Program
D-1 D-2
D-3
D-4
D-5
D-6
D-7
APPENDIX E
Special Well and
Surface Water Samples
E-1
1.0 INTRODUCTION
This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2023. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.
Tabulations of the special sampling pro gram individual analyses made during the year are included i n this appendix. A summary table of tritium analyses is also included in this appendix.
2.0
SUMMARY
This special sampling program was established following the detection of tritium in a residence well water sample south of the PINGP during 1989. This program is described and the results fo r 2023 are summarized and discussed.
Program findings for 2023 detected low levels of tritium in nearby residence wells, ground water, surface samples, and storage tanks at or near the expected natural background levels with the exception of ground water sample well MW-8, Barrelyard stormwater drain, septic system, and the D5 Fuel Oil Storage Tank (FOST) vault. The 2023 sample results (except for MW-8, Barrelyard stormwater drain, septic system, and the D5 FOST vault) ranged from <19 pCi/L to 191 pCi/L. Sample well MW-8 ranged from 381 pCi/L to 534 pCi/L. The Barrelyard stormwater drain ranged from 558 to 1403 pCi/L. The septic system ranged from 76 to 4571 pCi/L. D5 FOST had one sample that read 2039 pCi/L. All tritium results are far below the Environmental Protection Agen cys drinking water standard of 20,000 pCi/L and present no harm to any members of the public.
None of th e wa ter samples monitore d for gamma-emitting isotopes sho wed any activity greater than the LLD.
E-2 3.0 Special Tritium Sampling Program
3.1 Program Design and Data Interpretation
The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from the PINGP. For this purpose, special water samples are collected and analyzed for tritium content.
3.2 Program Description
The sampling and analysis schedule for the special water sampling program is summarized in Table E-4.1 and briefly reviewed below. Table E-4.2 defines the additional sample locations and codes for the special water sampling program.
Special well, tank, and surface water samples were collected quarterly (spring, summer, fall) at seven locations, quarterly at one location, monthly at six locations, semi-annually at five locations, and annually at thirty-nine locations. The Peterson (P-43) and Hanson (SW-1) farm wells are used as control locations for these special samples.
To detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of Waterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.
3.3 Program Execution
The special water sampling was executed as described in the preceding section.
3.4 Program Modifications
Changes to the program in 2023 include:
- Samples taken from monitoring wells P-10 and MW-8 were sent to Environmental Incorporated for hard-to-detect nuclide analysis in accordance with American Nuclear Insurers recommendation
- No samples were taken from the D6 Fuel Oil Storage Tank vault because this area was dry in 2023
E-3 3.5 Results and Discussion
Results show tritium in well water and ground water samples at or near expected natural background levels except the MW-8 ground water sample well. Table E-4.4 provides the complete data table of results for each period and sampling location.
The tritium level annual averages have shown a downward trend since the special sampling began in 1989.
Except for MW-8, Barrelyard stormwater drain, septic system, and the D5 Fuel Oil Storage Tank (FOST) vault, the 2023 sample results are within the range of expected background tritium levels in shallow ground water and surface water due to tritium concentrations measured in precipitation.
Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No. 10; World Survey of Isotope Concentration in Precipitation (1988-1991)).
The higher-level results at the Suter residence and Birch Lake in 1989 were possibly due to seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Vermillion River. The PINGP discharge canal piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. This years sample results continue to indicate that these modifications have eliminated the suspected radioactive effluent flow into the local ground water.
The elevated tritium levels in sample well MW-8 in 2023 may be due to prior leakage from the PINGP liquid radwaste discharge pipe, discharge of turbine building sump water into the landlocked area, or discharge of heating steam condensate from the main warehouse in 1978/1979. The liquid radwaste discharge pipe was replaced in 1992 and the dischar ge to the landlocked area has been terminated, the last discharge took place on 11/14/09. The main warehouse heating system was repaired in 1979. The heating steam system has not been used in the outer plant buildings since the 2011 - 2012 heating season.
The elevated tritium levels in the Barrelyard stormwater drain, and the D5 Fuel Oil Storage Tank (FOST) vault are most likely due to tritium recaptured from effluent releases by precipitation. The levels found in the septic system have returned to background levels.
None of the water samples monitored for gamma-emitting isotopes showed any activity greater than the LLD.
E-4 Table E-4.1. Sample collection and analysis program for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2023.
Medium No. Location codes Collection type Analysis and type a and frequency b type c
P-8 post-treat, P-8 pre-treat, REMP P-6, REMP P-11, PIIC-22, Well water PIIC-26, PIIC-28, PIIC-29, P-7, P-9, Annual 25 P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, G/A H-3 MW-6, P-26, P-30, SW-3, SW-4, SW-5, SW-7, SW-8, SW-9
Well water 1 P-24D G/Q H-3 quarterly
Well water 7 P-2, P-3, P-5, P-6, G/Q H-3 quarterly PZ-8, MW-4, MW-5
Well water monthly 5 P-43(C), SW-1(C), G/M H-3 MW-7, MW-8, P-10
Surface water S-1, S-2, S-3, S-4, S-5, H-3 9 S-6, S-7, S-10, P-31 G/Ad
Storage Tank 5 11 CST, 21 CST, 22 CST, G/S H-3 U1/2 Demin Hdr
Storage Tank 1 D5 tank vault G/A H-3
Storage Tank 1 Septic System G/M H-3
Snow 5 S-6, S-7, S-8, S-9, P-43(C) G/A H-3
a Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators.
b Collection type is codes as follows: G/ = grab. Collection frequency is coded as follows: M = monthly; Q = quarterly; Q = quarterly (spring, summer, and fall); S= semiannually; A = annually.
c Analysis type is coded as follows: H-3 = tritium.
d Location S-6, S-7, and S-10 are sampled semi-annually, P-31 is sampled three times a year
E-5 Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2023.
Code Collection site Type of Distance and sample a direction from reactor
P-8 PI Community well post treat DW 1.0 mi. @ 321°/WNW P-8 PI Community well pre treat DW 1.0 mi. @ 321°/WNW REMP P-6 Lock & Dam #3 well DW 1.6 mi. @ 129°/SE REMP P-11 Red Wing Service Center DW 3.3 mi @ 158°/SSE PIIC-22 1773 Buffalo Slough Rd DW 1 mi. @ 315°/NW PIIC-26 1771 Buffalo Slough Rd DW 1 mi. @ 315°/NW PIIC-29 Buffalo Project DW 4.3 mi @ 302°/WNW P-24D Suter residence DW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control) DW 13.9 mi. @ 355°/N SW-1 Hanson Farm (Control) DW 2.2 mi. @ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well WW See map P-10 Sample well WW See map P-11 Sample well WW See map PZ-1 Sample well WW See map PZ-2 Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WW See map MW-6 Sample well WW See map MW-7 Sample well WW See map MW-8 Sample well WW See map P-26 PITC well DW 0.4 mi. @ 258°/WSW P-30 Environ lab well DW 0.2 mi. @ 32°/NNE
E-6 Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2023 (continued).
Code Collection site Type of Distance and sample a direction from reactor
SW-3 Cooling Tower pump WW See map SW-4 New Admin Bldg DW 0.05 mi. @ 315/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ 0/N SW-6 SGR Building DW 0.2 mi @ 310/NW SW-7 Distribution Center DW 0.35 mi @ 271/W SW-8 Site Admin Building well WW 0.2 mi @ 310/NW SW-9 FLEX Building WW 0.2 mi @ 238°/WSW P-9 Plant well # 2 DW 0.3 mi. @ 306°/NW S-1 Upstream Miss. River SW See map S-2 Recirc/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end) SW See map S-5 Mid Discharge Canal SW See map S-6 Roof Stormwater Runoff (also snow) SW 0.05 mi. @ 0/N S-7 Parking Lot Stormwater (also snow) SW 0.3 mi @ 306/NW S-8 P-10 area snow SW See map S-9 MW-7/8 area snow SW See map S-10 Barrelyard SW Storm Water Drain SW Outside Barrelyard P-31 Birch Lake Seepage SW 0.69 mi. @ 172°/S 11 CST Storage Tank ST Turbine Building 21 CST Storage Tank ST Turbine Building 22 CST Storage Tank ST Turbine Building Unit 1/2 demin hdr Storage Tank ST Turbine Building Septic System Storage Tank ST Outside #1 Warehouse D5 Vault Concrete Vault ST Outside Turbine Bldg D6 Vault Concrete Vault ST Outside Turbine Bldg
a Sample codes: DW = Drinking Water: WW = Well Water; SW = Surface Water: ST = Storage Tank.
E-7 Table E-4.3 Radiation Environmental Monitoring Program Summary: Special well, storage tank, and surface water samples.
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December, 2023 (County, State)
Indicator Location with Highest Control Locations Annual Mean Locations Sample Type and Mean (F) c Location d Mean (F) c Mean (F) c Number Type Number of LLD b Range c Range c Range c Non-(Units) Analyses a Routine Results e
Offsite Well H-3 13 19 36 (7/13) Suter 44 (3/5) (See Control Water (24-55) Residence (24-55) Below) 0 (pCi/L)
Onsite H-3 74 19 147 (65/74) MW-8 468 (12/12) (See Control 12 Well Water (20-534) (381-534) Below)
(pCi/L)
Onsite H-3 18 19 237 (16/18) S-10 981 (2/2) (See Offsite Snow Surface Water (20-1403) (558-1403) Control Below) 2 (pCi/L)
Onsite H-3 23 19 529 (20/23) D5 FOST 2039 (1/1) (See Control Storage Tank (20-4571) Vault (2039) Below) 4 (pCi/L)
Control (offsite H-3 24 19 none P-43 32 (7/12) 33 (10/24) well water) (20-62) (20-62) 0
Control (offsite H-3 1 19 none P-43 50 (1/1) 50 (1/1) snow) (50) (50) 0
a H-3 = tritium b LLD = Nominal lower limit of detection base d on 4.66 sigma error for background sample. Value shown is lowest for the period.
c Mean and range are based on detectable measurements only. Fraction of detect able mea s urements at specified locations is
indicated in parentheses (F).
d Locations are spec ified by code.
e Non -routine results are those wh ich exceed ten times the control station mean value.
E-8 Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2023.
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023
CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L OFFSITE WELLS P-8 Post-treat PI Comm. Well <19
P-8 Pre-treat PI Comm. Well <19
REMP P-6 Lock & Dam #3 well <19
REMP P-11 Red Wing Service Center <19
PIIC-22 1773 Buffalo Slough Rd 28
PIIC-26 1771 Buffalo Slough Rd 25
PIIC-28 1960 Larson Lane 24
PIIC-29 Buffalo Project 43
P-24D Suter residence 24 52 <19 55 <19
21/50* 26 39 28 30 <19 <19 62 <19 20 <19 <19 P-43 Peterson Farm (Control *snow SW-1 Hanson Farm (Control) <19 23 <19 <19 35 <19 43 <19 <19 <19 <19 <19
E-9 Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2023 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023
CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS P-2 Sample well 20 86 26 P-3 Sample well <19 25 <19 P-5 Sample well 42 147 47 P-6 Sample well <19 48 32 P-7 Sample well 99 P-10 Sample well 43 59 44 32 112 134 191 129 91 112 65 99 P-11 Sample well 20 PZ-1 Sample well 37 PZ-2 Sample well 37 PZ-4 Sample well 48 PZ-5 Sample well 60 PZ-7 Sample well 40 PZ-8 Sample well 33 60 <19 MW-4 Sample well 38 54 <19 MW-5 Sample well 80 79 <19 MW-6 Sample well 51 MW-7 Sample well 164 110 91 93 103 86 137 139 125 127 90 109 MW-8 Sample well 524 477 452 381 435 493 516 534 522 444 435 404 P-26 PITC well 57 P-30 Env. lab well <19 SW-3 CT pump 30 P-9 Plant well # 2 36 SW-4 New Admin 62 SW-5 Plnt Scrnhs 58 SW-7 Dist Center <19
E-10 Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2023 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023
CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS SW-8 Site Admin Bldg 30 SW-9 FLEX Bldg <19
E-11 Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2023 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023
CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER
43 S-1 Mississippi River upstream
S-2 Recirculation/Intake canal 27
S-3 Cooling water canal 46
S-4 Discharge Canal (end) 29
S-5 Discharge Canal (midway) 28
S-6 Stormwater runoff 49* 37 79
S-7 Parking Lot runoff 174* 213 287
S-8 P-10 area snow 296*
S-9 MW-7/8 area snow 498*
S-10 Barrelyard SW Storm Water 1403 558 Drain
P-31 Birch Lake Seepage 20 <19 <19
- snow samples
E-12 Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2023 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023 2023
CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE STORAGE TANKS
11 CST Storage tank <19 38
21 CST Storage tank <19 44
22 CST Storage tank 36 24
U1/U2 Demin Storage tank 20/<19 86/115 Header
Septic Storage tank 98 103 91 170 131 208 119 76 126 1939 4571 541 System
D5 D5 Fuel Oil Storage Tank Vault 2039
E-13 Location P-10 MW-8 Collection Date 04-19-23 04-19-23
Lab Code PXW-1019 PXW-1020
Isotope Concentration (µCi/mL)
Ni-63 < 6.9 E-08 < 7.0 E-08
Sr-90 < 4.9 E-10 < 4.8 E-10
Less than (<), value is based on a 4.66 sigma counting error for the background sample. Analytical results relate only to the samples submitted to the Laboratory for testing, in the condition received by the laboratory.
E-14 Groundwater Monitoring Well Locations
E-15