ML24120A255
| ML24120A255 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 04/29/2024 |
| From: | Minnick S Constellation Energy Generation |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| TMl-24-006 | |
| Download: ML24120A255 (1) | |
Text
Constellation.
TMl-24-006 April 29, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility License No. DPR-50 NRC Docket Nos. 50-289 Three Mile Island Nuclear Station, Unit 2 Possession Only License No. DPR-73 NRC Docket No. 50-320 Three Mile Island Nuclear Station 2625 River RD Middletown, PA 17057
Subject:
2023 Annual Radiological Environmental Operating Report In accordance with TMl-1 Decommissioning Quality Assurance Program Section E.7.2, enclosed is the Annual Radiological Environmental Operating Report covering the time period for January 1 through December 31, 2023, for the Three Mile Island Nuclear Station.
There are no commitments in this letter.
Should you have any questions concerning this letter, please contact Mr. Dave Moore, Chemistry/Environmental Specialist, at (267)-533-5579 Respectfully,
~()/ ~
Stephen A Minnick Jr.
Site Decommissioning Director (Acting)
Three Mile Island Nuclear Station, Unit 1
Attachment:
Three Mile Island 2023 Annual Radiological Environmental Operating Report cc: w/ Attachment Regional Administrator - NRC Region I NRC Project Manager, NMSS - Three Mile Island, Unit 1 and Unit 2 David Saracco - Commonwealth of Pennsylvania - Bureau of Radiation Protection T.R. Devik - TMl-2 Solutions, LLC
THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 2023 Document Number: 50-289, 50-320 Annual Radiological Environmental Operating Report
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TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................ 3 2.0 EXECUTIVE
SUMMARY
............................................................................................................ 4 2.1 Summary of
Conclusions:
............................................................................................... 5
3.0 INTRODUCTION
........................................................................................................................ 8 4.0 SITE DESCRIPTION AND SAMPLE LOCATIONS..................................................................... 9 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS.............. 11 6.0 MAPS OF COLLECTION SITES.............................................................................................. 23 7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES................................................................................................. 26 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTEPRETATION OF RESULTS................................................................................................................................ 27 8.1 Environmental Direct Radiation Dosimetry Results....................................................... 27 8.2 Air Particulate and Radioiodine Sample Results........................................................... 29 8.3 Waterborne Sample Results......................................................................................... 30 8.4 Ingestion Pathway Sample Results............................................................................... 33 9.0 LAND USE CENSUS............................................................................................................... 34 10.0 SAMPLE DEVIATIONS, ANOMALIES AND UNAVAILABILITY................................................ 36 11.0 OTHER SUPPLEMENTAL INFORMATION............................................................................. 37 11.1 NEI 07-07 Onsite Radiological Groundwater Monitoring Program................................. 37 11.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program.................... 38 11.3 Corrections to Previous Reports................................................................................... 38 12.0 Bibliography............................................................................................................................. 39 TABLES Table 1, Radiological Environmental Monitoring Program - Direct Radiation....................................... 11 Table 2, Radiological Environmental Monitoring Program - Airborne................................................... 12 Table 3, Radiological Environmental Monitoring Program - Waterborne............................................. 13 Table 4, Radiological Environmental Monitoring Program - Ingestion.................................................. 14 Table 5, REMP Sampling Locations - Direct Radiation........................................................................ 16 Table 6, Reporting Levels for Radioactivity Concentrations in Environmental Samples....................... 26 Table 7, Maximum Values for the Limit of Detection............................................................................ 26 Table 8: Land Use Census - Nearest Receptors within 5 miles........................................................... 36 Table 9: Sample Deviation Summary................................................................................................... 37 Table 10: Quarterly isotopic data - Air (pCi/m3), Milk (pCi/L), and Water (pCi/L) and Semi Annual Sr89/90 at K1-1.................................................................................................................................... 44 Table 11: Continued: Complete REMP Results................................................................................... 45 Table 12: Cross Check Intercomparison Results................................................................................. 60 FIGURES Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations [7]............... 8 Figure 2, REMP Sample Locations (Near Field/Site Boundary)........................................................... 23
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Figure 3, REMP Sample Locations (Far Field)..................................................................................... 24 Figure 4, REMP Sample Locations (Onsite)......................................................................................... 25 Figure 5, Air Particulate: Analysis for Gross Beta, Average for All Indicator vs. Control Location......... 29 Figure 6: Surface Water Tritium Results.............................................................................................. 30 Figure 7: REMP Beta Emitters in Drinking Water Split Sample Comparison........................................ 31 Figure 8: Drinking Water Gross Beta Samples Control vs. Indicator Comparison................................ 32 Figure 9: Drinking Water Tritium Sample Results................................................................................. 32 ATTACHMENTS, Data Table Summary.................................................................................................... 42, Complete Data Table for All Analysis Results Obtained In 2023................................... 44, Cross Check Intercomparison Program......................................................................... 56, Environmental Direct Radiation Dosimetry Results....................................................... 77, Annual Radiological Groundwater Protection Program.................................................. 81
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1.0 LIST OF ACRONYMS AND DEFINITIONS 1.
Airborne Activity Sampling: Continuous sampling of air through the collection of particulates and radionuclides on filter media.
2.
ARERR: Annual Radioactive Effluent Release Report 3.
AREOR: Annual Radiological Environmental Operating Report 4.
BWR: Boiling Water Reactor 5.
Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.
6.
Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the station.
7.
Curie (Ci): A measure of radioactivity; equal to 3.7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.
8.
Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using Thermoluminescent Dosimeters (TLD), Optically Stimulated Luminescence Dosimeters (OSLD) and pressurized ionization chambers.
9.
EPA: Environmental Protection Agency 10.
GPI: Groundwater Protection Initiative 11.
Grab Sample: A single discrete sample drawn at one point in time.
12.
Indicator: A sampling location that is likely to be affected by plant effluents due to its proximity and/or direction from the plant.
13.
Ingestion Pathway: The ingestion pathway includes milk, fish, drinking water and garden produce. Also sampled (under special circumstances) are other media such as vegetation or animal products when additional information about particular radionuclides is needed.
14.
ISFSI: Independent Spent Fuel Storage Installation 15.
Lower Limit of Detection (LLD): An a priori measure of the detection capability of a radiochemistry measurement based on instrument setup, calibration, background, decay time, and sample volume. An LLD is expressed as an activity concentration. The MDA is used for reporting results. LLD are specified by a regulator, such as the NRC and are typically listed in the ODCM.
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16.
MDA: Minimum Detectable Activity. For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95%
probability, with only five % probability of falsely concluding that a blank observation represents a true signal.
17.
MDC: Minimum Detectable Concentration. Essentially synonymous with MDA for the purposes of radiological monitoring.
18.
Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.
19.
Microcurie: 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.
20.
N/A: Not Applicable 21.
NEI: Nuclear Energy Institute 22.
NIST: National Institute of Standards and Technology.
23.
NRC: Nuclear Regulatory Commission 24.
ODCM: Offsite Dose Calculation Manual 25.
OSLD: Optically Stimulated Luminescence Dosimeter 26.
pCi/L: picocuries / Liter 27.
PWR: Pressurized Water Reactor 28.
REMP: Radiological Environmental Monitoring Program 29.
TLD: Thermoluminescent Dosimeter 2.0 EXECUTIVE
SUMMARY
THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 Radiological Environmental Monitoring Program (REMP) was established prior to the station becoming operational to provide information on background radiation present in the area. The goal of TMI REMP is to evaluate the impact of the station on the environment. Environmental samples from different media are monitored as part of the program in accordance with specifications detailed in the Offsite Dose Calculation Manual (ODCM) and TMI Technical Specifications. The program compares data from Indicator locations near the plant, to Control locations farther away from the site to assess operation impacts.
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The Annual Radiological Environmental Operating Report (AREOR) provides data obtained through analyses of environmental samples collected at TMI for the reporting period of January 1st through December 31st, 2023. During that time period 1960 analyses were performed on 1654 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and/or 10-year average values, it was concluded that the operation of TMI, radioactive materials related to TMINS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS effluents in 2023 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.
Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2023 did not have any adverse effects on the health of the public or on the environment.
2.1 Summary of
Conclusions:
No measurable activities above background levels were detected that are attributed to the fuel cycle at Three Mile Island. All values were consistent with historical results which indicate no adverse radiological environmental impacts associated with the operation of TMI. Naturally occurring radionuclides are present in the Earths crust and atmosphere and exists in detectable quantities throughout the world. It is common to detect naturally occurring radionuclides in many of the samples collected for REMP.
Some examples of naturally occurring radionuclides that are frequently seen in samples are potassium-40, beryllium-7, actinium-228 (present as a decay product of radium-228),
and radium-226. Additionally, some relatively long-lived anthropogenic radioisotopes, such as strontium-90 and cesium-137, are also seen in some REMP samples; these radionuclides exist in measurable quantities throughout the world as a result of fallout from historic atmospheric nuclear weapons testing.
Air particulate samples were analyzed for concentrations of gross beta and gamma-emitting nuclides. Gross beta activity is consistent with data from previous years.
Cosmogenic beryllium-7 (Be-7) was detected at levels consistent with those detected in previous years. No other activation products were detected.
Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma-emitting nuclides.
Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish or in sediment samples.
Cow milk samples were analyzed for concentrations of I-131, gamma-emitting nuclides, Sr-89 and Sr-90. Concentrations of naturally occurring potassium-40 (K-40) were consistent with those detected in previous years. No I-131, Sr-89 or Sr-90 activities were detected. Occasionally Sr-90 activity may be detected and attributed to fallout from nuclear weapons testing. No other fission or activation products were found.
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Food Product samples were analyzed for concentrations of gamma-emitting nuclides including I-131 and Sr-90. Concentrations of naturally occurring Be-7 and K-40 were consistent with those detected in previous years. Low level Strontium 90 was detected in cabbage collected 08/16/2023 at B10-2 Milton Hershey School at 17.6 +/- 2.9 pCi/kg wet.
No other fission or activation products were detected. Detailed information on the exposure of the U.S. population to ionizing radiation can be found in NCRP Report No.
160 [1].
Calcula.ted Maximum Hypothetical Doses to an l'ndiiVidual fr.om 2023 TMl'-1 and ]Ml-2 Liquid and Ai1rborn.e Effluents Maxjmumi Hynomet;ca11 Doses to Am lndjyjdua1 From Rad'io11uclides l11 Liquid Rele*ases From Rad1011uclides in Airbo.rne Rel!eases (Noble Gases}
From Rad'io11uclides in Airborne Releases ~
, Tritium and Particullates)
USN IRC 10 CFR 50 A:P..*l?:._li G 1111ideli1111.es
<w rnrn{Vcl 3 totaJ body, or 10 ai:1y* organ 5, totaJ body, o:r 15 skin 15 ai:1y organ
- No 11ob!e gases were released from TMl-2_
Total from Site USEPA 40 CFiR 190 Limits iwr:e*wtnl1 75~
25 M al body or o~her organs Caleti lated Dose dfllrernlll.l) lt4b:1 IM.b2 1.'.l 5E-02 1.06E-03 1.55E-02 1_68E-03 O*
0..
O*
O"'
1.70E-04 3_.S9E-06 Cafcul!ated D os,e limremJ¥.J)
TMl-1 and JMl-2 comibined"'
0_013 o_ou
- "This sums toge1her TMl-1 amnMl-2 maximum doses regardless of age group for different pathways. Tile oom'bin e-d dos,es iinch.1de tlhose due to radioactive effluents allld direct radiation from TIM INS,. _The direct radiati'on dos,e is calculated from environmental: dosimet.er data,.* For this ca cEJllatiolll, e*xposure 1is assumed to bee.quail to dlos*e_
The dtrect radialiorn dose from 2023 TMINS operations was 0-259 mreml¥,1;based1 on calculations from AN SIJHI standard N 13_37 _
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Calculated Whole Body Doses to, *the Maximum Individual ftram 2023 TMl,-1 and TMl-2 Uquid! and Ai:rborn.e Efflluents From Rad'ionuclides ID Liquid: :Releases From Radionuclides in Airborne Releases (Noble Gases}
From Rad'ionuclides ID Airbome*
Releases ~
Tritium and Particulates)
- No noble g1ases were released from TMl-1 or TMll-2.
Cafoulated Maximum 1:11dividual Whole Body
!Jose (rnrem'Yl) 1.15E-02 1_O6E-O3 o*
1.7OE-04 3_89E-O6 lndMdua'I Wbiole Bamr liJose Oue to TM1~1 and f'IMll-2 Operations:
O.013mrem(Y{
lndividua:I Whole Bamr IDose Oue* to Natural Background Radiati:on m 311 mremfMjr (1. NCRP 60 - f2009)
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3.0 INTRODUCTION
The Radiological Environmental Monitoring Program (REMP) provides data on measurable levels of radiation and radioactive materials in the environment. This program also evaluates the relationship between quantities of radioactive materials released from the plant and resultant doses to individuals from principal pathways of exposure. In this capacity, REMP provides a check on the effluent release program and dispersion modeling to ensure that concentrations in the environment due to radioactive effluents conform to the As Low as Is Reasonably Achievable (ALARA) design objectives of 10 CFR 50, Appendix I [2], and implements the requirements of Section IV.B.2 and IV.B.3 of Appendix I. REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guide 4.1 [3], NUREG 1301/1302
[4] [5], and the 1979 NRC Branch Technical Position [6].
Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations [7]
Quality assurance aspects of the sampling program and OSLD data collection are conducted in accordance with Regulatory Guides 4.15 [8] and 4.13 [9]. REMP also adheres to the requirements of Pennsylvania, TMI Unit 1 and Unit 2 Decommissioning Quality Assurance Programs (DQAPs) and Offsite Dose Calculation Manual (ODCM). These governing documents dictate the environmental sampling, sample analysis protocols, data reporting and quality assurance requirements for the environmental monitoring program.
Ga ou 0
- 0.
cffiucnts c:;:,i..
Live tock product
- Radiation O
- Radionuclides
- * * * * : Behavior of radionuclides
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The Annual Radiological Environmental Operating Report provides summaries of the environmental data from exposure pathways, interpretations of the data, and analyses of trends of the results. Routinely monitored pathways include ingestion, inhalation, and direct radiation. Routes of exposure are based on site specific information such as meteorology, receptor locations, and water usage around the plant.
4.0 SITE DESCRIPTION AND SAMPLE LOCATIONS THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 is a commercial nuclear power plant that achieved initial criticality in 1974 and 1978 respectively. The Three Mile Island Nuclear Station (TMINS), consisting of two pressurized water reactors (PWR), is located on the northern end of Three Mile Island in the Susquehanna River approximately 2.5 miles south of Middletown in Londonderry Township, Dauphin County, Pennsylvania. TMI-1 is owned and operated by Constellation Energy Company (formerly Exelon). TMI-2 is operated and owned by TMI-2 Solutions, LLC. The Three Mile Island Unit 2 (TMI-2) operating license was issued on February 8, 1978, and commercial operation was declared on December 30, 1978. On March 28, 1979, the unit experienced an accident that resulted in severe damage to the reactor core. TMI-2 has been in a non-operating status since that time. GPU Nuclear (GPUN) conducted a substantial program to defuel the Reactor Vessel (RV) and decontaminate the facility. As a result, TMI-2 was defueled and decontaminated to the extent that the plant was placed in a safe, inherently stable condition suitable for long-term management, and any threat to public health and safety had been minimized. This long-term management condition, termed Post-Defueling Monitored Storage (PDMS), was entered in December 1993.
In December 2020, the Nuclear Regulatory Commission (NRC) approved the transfer of GPUN Possession Only License No. DPR-73 for Three Mile Island Nuclear Station (TMINS)
Unit 2 to TMI-2 Solutions. In February 2021, TMI-2 Solutions submitted a License Amendment Request (LAR) to the NRC to modify the TMI-2 Technical Specifications to permit the completion of the decommissioning of TMI-2. Following NRC approval and issuance of associated changes to the Possession Only License, TMI-2 exited PDMS and entered Decommissioning on March 31, 2023.
See the Land Use Census in Section 9 for population around the area, nearest privately-owned land, etc.
TMI sampling media are selected based on site specific information such as meteorology, receptor locations, and water usage around the plant. Sampling and analysis frequencies are documented in the Offsite Dose Calculation Manual and site procedures. Required sampling, analysis frequencies and location of sample collected are captured in the following tables and figures:
Table 1, Radiological Environmental Monitoring Program - Direct Radiation
Table 2, Radiological Environmental Monitoring Program - Airborne
Table 3, Radiological Environmental Monitoring Program - Waterborne
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Table 4, Radiological Environmental Monitoring Program - Ingestion
Table 5, REMP Sampling Locations - Direct Radiation
Figure 2, REMP Sample Locations (Near Field/Site Boundary)
Figure 3, REMP Sample Locations (Far Field)
Figure 4, REMP Sample Locations (Onsite)
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5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS Table 1, Radiological Environmental Monitoring Program - Direct Radiation Requirement Sample Location Description, Distance, and Direction Sampling Collection/
Frequency Type and Frequency of Analyses Direct Radiation 40 Routine monitoring stations with two or more dosimeters placed as follows:
An inner ring of stations, one in each compass sector in the general area of the site boundary.
An outer ring of stations, one in each compass sector at approximately 6-8 kilometers or 3.7-5 miles from the site; and Special interest areas, such as population centers, nearby recreation areas, and control stations See Table 5 Quarterly Analyze for gamma dose quarterly
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Table 2, Radiological Environmental Monitoring Program - Airborne Requirement Sample Location Description, Distance, and Direction Sampling Collection/
Frequency Type and Frequency of Analyses Airborne Radioiodine and Particulates Samples from 5 locations:
Three locations close to the site boundary in different sectors of the highest calculated annual average ground level D/Q.
One sample from the vicinity of a community having the highest calculated annual average ground level D/Q.
One sample from a Control Location, approximately 15 to 30 kilometers or 9 to 19miles away in a less prevalent wind direction E1-2: Visitors Center 0.4 miles 97 degrees F1-3: 500kv Substation 0.6 miles 112 degrees G2-1: Farm on Becker Rd 1.4 miles 126 degrees M2-1: Goldsboro 1.3 miles 256 degrees A3-1: Mill St Substation 2.7 miles 357 degrees H3-1: Falmouth-Collins Substation 2.2 miles 160 degrees Q15-1: behind West Fairview Fire Dept. 13.4 miles 309 degrees Continuous sampler operation with sample collection weekly Particulate sampler: Analyze for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change / Weekly. Perform gamma isotopic analysis on each sample when gross beta activity is >
10 times the yearly mean of control samples.
Perform gamma isotopic analysis on composite sample (by location)/Quarterly.
Radioiodine canister: I131 analysis/Weekly.
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Table 3, Radiological Environmental Monitoring Program - Waterborne Requirement Sample Location Description, Distance, and Direction Sampling Collection/
Frequency Type and Frequency of Analyses Surface Water 1 sample upstream (control) and 1 sample downstream (indicator)
A3-2: Swatara Creek, Middletown, 2.7 miles 356 degrees Q9-1: near intake Steelton Water Company, 8.5 miles 310 degrees J1-2: Downstream of TMINS liquid discharge, 0.5 miles 188 degrees Composite sample over 1 monthly period Gamma isotopic analysis monthly. Composite for tritium analysis quarterly.
Drinking Water 1 sample upstream (control) and 1 sample at nearest water supply that could be affected by the station discharge (indicator)
G15-2: Wrightsville Water Treatment Plant, 13.3 miles 129 degrees G15-3: Lancaster Water Treatment Plant, 15.7 miles 124 degrees Q9-1: at Steelton Water Company, 88.5 miles 310 degrees Composite sample over 1 monthly period Perform gross beta and gamma isotopic analysis monthly. Perform Sr-90 analysis if gross beta of monthly composite >10 times control. Composite for tritium analysis quarterly.
Sediment from Shoreline 1 sample upstream (control) 1 sample downstream (indicator)
A1-3: near north tip of TMI in Susquehanna River, 0.6 miles 359 degrees K1-3: downstream of TMINS liquid discharge in Susquehanna River, 0.2 miles 213 degrees J2-1: South of TMINS upstream of York Haven Dam, in Susquehanna River, 1.4 miles 179 degrees Semiannual (Spring and Fall)
Gamma isotopic analysis on each sample.
I
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Table 4, Radiological Environmental Monitoring Program - Ingestion Requirement Sample Location Description, Distance, and Direction Sampling Collection/
Frequency Type and Frequency of Analyses Milk:
Four samples from milking animals in three locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.
One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.
Farm F4-1: ESE Turnpike Rd. 3.2 miles 104 degrees Farm G2-1: Becker Farm 1.4 miles 126 degrees P4-1: Fisher Farm 3.6 miles 295 degrees Farm J18-1: York, 17.6 miles 188 degrees Semimonthly when animals are on pasture, monthly at other times.
Gamma isotopic analysis and I-131 analysis on each sample. Composite for Sr-90 analysis quarterly.
Fish and Invertebrates:
Four samples from 2 locations:
One sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge.
One sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not 1influenced by the station discharge.
IND: Downstream of Station Discharge BKG: Upstream of Station Discharge Sample twice per year (Spring and Fall).
Perform gamma isotopic and Sr-90 analysis on edible portions.
1 P4-1 Farmer indicated milk to be produced again in the future.
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Food Products:
Samples from 2 locations (when available)
1 sample of each principle class of food products at a location in the immediate vicinity of the station.
(indicator)
1 sample of same species or group from a location not influenced by the station discharge.
Three different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed and one sample collected from the control location.
One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in a less prevalent wind direction if milk sampling is not performed.
Station E1-2: East of site at Visitors Center 0.4 miles 97 degrees Station B10-2: Milton Hershey School 10.0 miles 31 degrees Station E1-2: East of site at Visitors Center 0.4 miles 97 degrees Station H1-2: Red Hill Market 1.0 mile 151 degrees Station B10-2: Milton Hershey School 10.0 miles 31 degrees Sample at time of harvest.
Monthly during growing season Perform gamma isotopic, and I-131, analysis on edible portions. Sr-90 analysis on green leafy vegetables or vegetation only.
Perform gamma isotopic I-131 analysis.
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description A1-4 Inner Ring A
0.3 N of Reactor Building on W fence adjacent to North Weather Station, TMI B1-1 Inner Ring B
0.6 NNE of site on light pole in middle of North Bridge, TMI B1-2 Inner Ring B
0.4 NNE of Reactor Building on top of dike, TMI C1-2 Inner Ring C
0.3 NE of site along Route 441 N D1-1 Inner Ring D
0.2 ENE of Reactor Building on top of dike, TMI E1-2 Inner Ring E
0.4 E of site at TMI Visitors Center E1-4 Inner Ring E
0.2 E of Reactor Building on top of dike, TMI F1-2 Inner Ring F
0.2 ESE of Reactor Building on top of dike midway within ISWSF, TMI G1-3 Inner Ring G
0.2 SE of Reactor Building on top of dike, TMI H1-1 Inner Ring H
Inner Ring H
0.1 SSE of site, TMI J1-1 Inner Ring J
0.8 S of site, TMI J1-3 Inner Ring J
0.3 S of Reactor Building just S of SOB, TMI J1-4*
Inner Ring J
0.1 S of site, TMI K1-4 Inner Ring K
0.2 SSW of Reactor Building on top of dike behind Warehouse 2, TMI
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description K1-5*
Inner Ring K
0.1 SSW of site, TNI L1-1 Inner Ring L
0.1 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI M1-1 Inner Ring M
0.1 WSW of Reactor Building on SE corner of U-2 Screenhouse fence, TMI N1-3 Inner Ring N
0.1 W of Reactor Bldg on fence adjacent to Screenhouse entrance gate, TMI P1-1 Inner Ring P
0.4 WNW of site on Shelley Island P1-2 Inner Ring P
0.1 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI Q1-2 Inner Ring Q
0.2 NW of Reactor Building on fence W of Warehouse 1, TMI R1-1 Inner Ring R
0.2 NNW of Reactor Building along W fence, TMI C2-1 Inner Ring C
1.5 NE of site at Middletown Junction K2-1 Inner Ring K
1.2 SSW of site on S. Shelley Island M2-1 Inner Ring M
1.3 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro A3-1 Inner Ring A
2.7 N of site at Mill Street Substation H3-1 Inner Ring H
2.2 SSE of site, TMI L1-2 Inner Ring L
1 Beech Island, 2nd dock down from the northern tip on the western side of the island R3-1 Inner Ring R
2.6 NNW of site at Crawford Station, Middletown
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description F1-1 Inner Ring F
1 500 KV Substation G2-4 Inner Ring G
2 East Falmouth G1-2 Inner Ring G
1 Red Hill A5-1 Outer Ring A
4.4 N of site on Vine Street Exit off Route 283 B5-1 Outer Ring B
4.9 NNE of site at intersection of School House and Miller Roads C5-1 Outer Ring C
4.7 NE of site on Kennedy Lane E5-1 Outer Ring E
4.7 E of site at intersection of N. Market Street (Route 230) and Zeager Road F5-1 Outer Ring F
4.7 ESE of site along Amosite Road G5-1 Outer Ring G
4.8 SE of site at intersection of Bainbridge and Risser Roads H5-1 Outer Ring H
4.1 SSE of site by Guard Shack at Brunner Island Steam Electric Station J5-1 Outer Ring J
4.9 S of site along Canal Road, Conewago Heights K5-1 Outer Ring K
4.9 SSW of site along Conewago Creek Road, Strinestown L5-1 Outer Ring L
4.1 SW of site at intersection of Stevens and Wilson Roads M5-1 Outer Ring M
4.3 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown N5-1 Outer Ring N
4.9 W of site off of Old York Road along Robin Hood Drive
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description P5-1 Outer Ring P
5.0 WNW of site at intersection of Valley Rd (Route 262) and Beinhower Rd Q5-1 Outer Ring Q
5.0 NW of site along Lumber Street, Highspire R5-1 Outer Ring R
4.9 NNW of site at intersection of Spring Garden Drive and Route 441 D6-1 Special Interest D
5.2 ENE of site off Beagle Road E7-1 Special Interest E
6.7 E of site along Hummelstown Street, Elizabethtown Q9-1 Special Interest Q
8.5 NW of site at the Steelton Water Company B10-1 Special Interest B
9.2 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey G10-1 Special Interest G
9.7 SE of site at farm along Engles Tollgate Road, Marietta G15-1 Special Interest G
14.4 SE of site at Columbia Water Treatment Plant J15-1 Special Interest J
12.6 S of site in Met-Ed York Load Dispatch Station Q15-1 Special Interest Q
13.4 NW of site behind West Fairview Fire Dept. Social Hall (abandoned)
R15-1 Special Interest R
15 Colonial Park A9-3 Special Interest A
8 N of site at Duke Street Pumping Station, Hummelstown B2-1 Inner Ring B
1.9 NNE of site on Sunset Dr. (off Hillsdale Rd.)
C1-1 Inner Ring C
0.7 NE of site along Route 441 N
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description C8-1 Special Interest C
7.1 NE of site at Schenks Church on School House Road D1-2 Inner Ring D
0.5 ENE of site off Route 441 along lane between garden center
& residence D2-2 Inner Ring D
1.6 ENE of site along Hillsdale Rd. (S of Zion Rd.)
D15-1 Special Interest D
10.8 ENE of site along Route 241, Lawn E2-3 Inner Ring E
2 E of site along Hillsdale Rd. (N of Creek Rd.)
F1-4 Inner Ring F
0.2 ESE of Reactor Building on top of dike, TMI F2-1 Inner Ring F
1.3 ESE of site along Engle Road F10-1 Special Interest F
9.4 ESE of site along ESE of site along Donegal Springs F25-1 Special Interest F
22 ESE of site at intersection of Steel Way and Loop Roads, Lancaster G1-5 Inner Ring G
0.3 SE of Reactor Building on top of dike, TMI G1-6 Inner Ring G
0.3 SE of Reactor Building on top of dike, TMI L15-1 Special Interest L
11.8 SW of site on W side of Route 74, rear of church, Mt. Royal M1-2 Inner Ring M
0.4 WSW of site on E side of Shelley Island, Lot #157 M9-1 Special Interest M
8.7 WSW of site along Alpine Road, Maytown N1-1 Inner Ring N
0.7 W of site on W side of Shelley Island, between lots #13 and
- 14
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description N2-1 Inner Ring N
1.2 W of site at Goldsboro Marina N8-1 Special Interest N
7.7 W of site along Route 382, 1/2 mile north of Lewisberry N15-2 Special Interest N
10.4 W of site at intersection of Lisburn Road and Main Street, Lisburn P2-1 Inner Ring P
1.9 WNW of site along Route 262 P8-1 Special Interest P
7.9 WNW of site along Evergreen Road, Reesers Summit Q1-1 Inner Ring Q
0.5 NW of site on E side of Shelley Island Q2-1 Inner Ring Q
1.9 NW of site along access road along river R1-2 Inner Ring R
1.7 NNW of site on central Henry Island R9-1 Special Interest R
8 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights L2-1 Inner Ring L
2 River Road K3-1 Inner Ring K
3 On utility pole 0.4 miles past baseball field J3-1 Inner Ring J
3 On Utility pole directly under power lines H3-1 Inner Ring H
3 Falmouth K8-1 Special Interest K
8 Zions View J7-1 Special Interest J
7 On utility pole past garage on right
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Table 5, REMP Sampling Locations - Direct Radiation Site #
Location Type Sector Distance Description H8-1 Special Interest H
8 Starview H15-1 Special Interest H
15 Wilshire Hills K15-1 Special Interest K
15 Robins Nest L8-1 Special Interest L
8 Andersontown
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6.0 MAPS OF COLLECTION SITES Figure 2, REMP Sample Locations (Near Field/Site Boundary)
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Figure 3, REMP Sample Locations (Far Field)
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Figure 4, REMP Sample Locations (Onsite) p
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7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Table 6, Reporting Levels for Radioactivity Concentrations in Environmental Samples Radionuclide Water (pCi/L)
Air Particulates or Gases (pCi/m3)
Fish (pCi/Kg-wet)
Milk (pCi/L)
Food Products (pCi/Kg-wet)
H-3 20,000 (2)
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 Sr90 8
0.1 100 8
100 I-131 2 (3) 0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 Table 7, Maximum Values for the Limit of Detection Radionuclide Water (pCi/L)
Air Particulates or Gases (pCi/m3)
Fish (pCi/Kg-wet)
Milk (pCi/L)
Food Products (pCi/Kg-wet)
Sediment (pCi/Kg-dry)
Gross Beta 4.0 0.01 H-3 2,000 (4)
Mn-54 15 130 Fe-59 30 260 Co-58, Co-60 15 130 Zn-65 30 260 Zr-95 30 Sr-90 2
0.01 10 2
10 Nb-95 15 I-131 1 (5) 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 2 For drinking water samples: If no drinking water pathway exists, a value of 30,000 pCi/L may be used.
3 If no drinking water pathway exists, a value of 20 pCi/l may be used 4 If no drinking water pathway exists, a value of 3,000 pCi/L may be used. Some states may require a lower LLD for drinking water sources-per 40 CFR 141 Safe drinking water ACT.
5 If no drinking water pathway exists, a value of 15 pCi/l may be used
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8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTEPRETATION OF RESULTS At most nuclear stations, data was collected prior to plant operation to determine background radioactivity levels in the environment. Annual data is routinely compared to preoperational and/or 10-year average values to determine if changes in the environs are present. Strict comparison is difficult to make due to fallout from historical nuclear weapon testing. Cesium-137 can be routinely found in environmental samples as a results of above ground nuclear weapons testing. It is important to note, levels of Cs-137 in environment are observed to fluctuate, for example as silt distributions shift due to natural erosion and transport processes, Cs-137 may or may not be observed in sediment samples. Results from samples collected and analyzed during the year, 2023, are described below.
In the following sections, results from direct radiation, air, water, and food products analyzed as part of REMP in 2023 will be discussed. Sampling program descriptions and deviations will also be discussed.
8.1 Environmental Direct Radiation Dosimetry Results Dose is measured as net exposure (field reading less transit reading) normalized to 91-day quarters. Data is treated and analyzed consistent with ANSI/HPS N13.37-2014, which compares the measured dose for each location to the baseline background dose for that location. Environmental dose rates vary by location, depending on geological and land use considerations, and remain relatively constant for any given location (unless land use changes). Some facilities observe seasonal variation in environmental doses. Baseline Background Doses have been determined for both quarterly and annual measurements at each location using historical field measurements.
ANSI/HPS N13.37-2014 uses the concept of minimum differential dose (MDD), which is the minimum facility-related dose that can be detected above background. Due to natural background variations and measurement sensitivities and uncertainties, minimum differential dose is not zero. MDD is calculated based on statistical performance of the dosimetry system in the environment and is site specific.
Normalized doses that exceed the Minimum Differential Dose value above the Baseline Background Dose are considered to indicate Facility-Related Dose; a quality assurance review is performed to verify that any results indicating Facility-Related Dose are accurate.
During the calendar year 2023, a total of 90 locations were monitored and data analyzed in accordance with the requirements in Table 1, Radiological Environmental Monitoring Program
- Direct Radiation. Attachment 4, Environmental Direct Radiation Dosimetry Results, provides the annual direct radiation dosimetry analysis.
All OSLD measurements were analyzed, and two of the OSLD analysis results indicated detectable radiation from the facility. The maximum estimated dose to the nearest member of the public was 0.017 mrem/yr total body based on occupancy and extrapolation methods.
H1-1 Facility related dose was 28.7mrem/yr and J1-3 had facility related dose of 50.2mrem/yr.
All locations were evaluated further to determine the mean and range of OSLD measurements at indicator and control locations respectively. These locations are in near proximity to the ISFSI pad.
There were no significant anomalies or program modifications in 2023.
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In 2023 there were two instances of lost dosimeters resulting in a loss of data.
Dosimeters P2-1 Upon arrival on 6/20/23 at the TMI P2-1 sample station for the dosimeter collection, field tech found that the 2nd quarter 2 environmental dosimeters and bracket were missing. The field tech did a complete sweep of the area, but nothing was found.
The missing dosimeter numbers are EX00000332E and EX000887477.
Dosimeters D1-1 The field paperwork indicated the dosimeters at field location D1-1 were collected from that location, including the QA dosimeter. According to Landauers records, the 2 dosimeters for D1-1 (Serial numbers EX00059488C and EX000135028) are still in a shipped state which means they were never received back into their system. When the dosimeters were returned to Landauer for processing, each one is scanned back in before getting sent to the Lab for processing. After speaking with CGS, the dosimeters were collected and placed in the bag with all the other dosimeters and sent to Landauer. All other dosimeters were received at the lab. It is suspected that the dosimeters were lost after being sent to Landauer during their analysis process.
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8.2 Air Particulate and Radioiodine Sample Results Air particulate filters and charcoal canisters were collected from locations specified in Table 1, Radiological Environmental Monitoring Program - Direct Radiation. During the calendar year 2023, a total of 728 samples were collected and analyzed for gross beta, gamma emitters and iodine. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1 and Q15-1).
The control location was Q15-1. Particulate samplers are used to continuously collect airborne particulates on a filter. The samples are analyzed for gross beta activity following filter changeout which occurs weekly. Gamma isotopic analysis is also performed on the samples collected at each location and is analyzed quarterly.
Radioiodine (I-131) analysis is performed weekly on radioiodine sample cartridges.
All radioiodine samples were below detection limit.
All air particulate samples contained detectable amounts of beta emitters within trend as compared to the control location. Gross beta activity at indicator locations averaged 2.35E-2 pCi/m3 and ranged from 8.69E-3 to 4.59E-2 pCi/m3. This is comparable with the control location Q15-1 which averaged 2.38E-2 pCi/m3 and ranged from 7.74E-3 to 4.28E-2 pCi/m3.
Air particulate results from this monitoring period, 2023, were compared to 10-year average as shown in Figure 5. There was a noticeable change in the baseline trending gradually upward. Control and indicator locations are well in line with each other when reviewing the weekly data from both CGS and TBE laboratories. This upward trend is not attributed to the fuel cycle at TMI. Similar trending has been observed at other nuclear facilities across the region and may be attributed to ambient environmental shifts.
Figure 5, Air Particulate: Analysis for Gross Beta, Average for All Indicator vs. Control Location 0
20 16 20 18 1020
+ AJ-1 (I)
-+- Control monthly mean
+ Fl -3 (I)
+ G2-l (I)
Indicator monthly mean + M2 - l (I) 1022
[l-2 (I)
+ H3-l(I)
+
QlS - l(C) 2024
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8.3 Waterborne Sample Results 8.3.1 Surface Water (i.e., Bay, Lake etc.)
Composite water samples are collected monthly at the upstream control location and at the downstream indicator locations. Monthly composite samples are analyzed for gamma emitters. Aliquots from the monthly composites are combined to form a quarterly composite which is then analyzed for tritium. During the calendar year 2023, a total of 48 surface water samples were collected and analyzed in accordance with the requirements in the ODCM at J1-2, A3-2 and Q9-1and shown in Table 3, Radiological Environmental Monitoring Program - Waterborne. Low level I-131 was detected at A3-2 on two occasions at 1.10 +/- 0.43 pCi/L and 2.48 +/- 0.61 pCi/L and are known to be attributed to medical sources from Hershey Medical. Tritium was detected once at the control location Q9-1, at 152 +/- 87 pCi/L. J1-2 which is downstream was detected in monthly and quarterly samples in the first half of the year. Monthly tritium averaged 920 pCi/L and ranged from 680 to 1090 pCi/L and quarterly tritium dropped from 1520 +/- 198 pCi/L in quarter 1 to 635 +/- 140 pCi/L in quarter 2 and was undetectable the remainder of the year. No program modifications, or any changes in the environs 2023. Tritium concentrations in surface water were well below the EPA tritium drinking water limit of 20,000 pCi/L.
Figure 6: Surface Water Tritium Results 8.3.2 Effluent Surface Water Monthly samples were collected from a continuous water sampler at one location (K1-1) and analyzed for Gamma emitters including Low level Iodine, Tritium and Sr90.
...J --
0
- a.
1 ~.ooo 10,000 5000 0
+ Control monthly mean -+- Indicator monthly mean TM Jl 2 (I)
...., TM Q9 l (C)
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Tritium was detected in 6 of 12 monthly samples and averaged 3867 pCi/L and ranged from 650 to 5620 pCi/L. Of the quarterly composite samples Tritium was detected in the first quarter at 6460pCi/L and dropped to 2760pCi/L in second quarter and was undetectable in quarters 3 and 4. There was no Sr90 detected in K1-1 samples in 2023.
Figure 7: REMP Beta Emitters in Drinking Water Split Sample Comparison 8.3.3 Drinking Water A total of 36 drinking water samples were obtained in 2023 at G15-2, G15-3 and Q9-1 (DW). These samples were analyzed for gross beta, tritium and gamma analysis monthly, tritium quarterly in accordance with requirements in the ODCM and shown in Table 3, Radiological Environmental Monitoring Program - Waterborne. One analysis of G15-3 indicated low level tritium in quarter 1 composite sample at 118 +/- 83 pCi/L.
Beta emitters were observed in 35 of 36 samples and within historical trends.
Indicator samples averaged 2.50pCi/L and detectable results ranged from 0.94 to 4.20 pCi/L. There were no program modifications or changes in the environs 2023.
Tritium concentrations in drinking water were well below the EPA tritium drinking water limit of 20,000 pCi/L.
~
7.0 6.0 5.0 0 4.o Q.
~.,
i: 3.0 E
- 2.0 1.0 0.0 2023 Comparison of Beta Emitters in Split Samples CGS and TBE Analysis of 9-1 Drinking Water 2/2/2023 3/2/2023 4/2/2023 5/2/2023 6/2/2023 7/2/2023 8/2/2023 9/2/2023 10/2/2023 11/2/2023 12/2/2023
-1.0 calendar (CGS) Q9-1 OW (TBE) ~lQ OW, plot shown at 0.0 are <MDA
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Figure 8: Drinking Water Gross Beta Samples Control vs. Indicator Comparison Figure 9: Drinking Water Tritium Sample Results
...I R
6 0
4
- a.
...I 0 a.
2 0
201G
+ Control monthly mean
.... I M-IJW-c; 11-*1 (!)
1000 750
~OU 250 0
?016
+ Control monthly mean TM OW G l '.i 3 (I) 2018 2020
-+- Indicator monthly mean
+
I M-DW-q9-I (C) 7018
- ,070
-+- Indicator monthly mean
...., TM OW Q9 l (Cl 2022 202'1 TM-OW-Gl 5-2 (I)
- )0;)4 TM-OW-Gl 5-2 (I)
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8.3.4 Sediment from Shoreline Shoreline sediment collections were made in June and October, 2023 and analyzed for gamma-emitting isotopes. Samples are collected at both indicator and control locations. A total of 6 shoreline samples were analyzed in accordance with requirements in the ODCM and shown in Table 3, Radiological Environmental Monitoring Program - Waterborne.
Sediment samples from all locations were analyzed for gamma-emitting nuclides. All analyses met Minimum Detectable Activities. No fission or activation products were detected.
8.4 Ingestion Pathway Sample Results 8.4.1 Milk Milk samples from milking animals were collected at 3 locations within 8 km having the highest dose potential, along with samples collected from the control location 15-30 km in the least prevalent wind direction, monthly from December through February and biweekly March through July. 69 samples were collected and analyzed for gamma emitters and a total of 12 quarterly composites of those samples were analyzed for strontium 90.
All Milk samples from all locations were analyzed as required by the ODCM for gamma-emitting nuclides and Strontium 90. All analyses met Minimum Detectable Activities. No fission or activation products were detected.
8.4.2 Fish and Invertebrates A total of 8 fish and invertebrate samples were collected in 2023. These samples were analyzed for strontium 90 and gamma emitting radionuclides in edible portions, in accordance with requirements of the ODCM and summarized in Table 4, Radiological Environmental Monitoring Program - Ingestion. These samples are collected from the indicator and control areas as required by the ODCM. Only the edible portions are analyzed excluding head, tail, bones, and shell fragments All Fish samples from all locations were analyzed as required by the ODCM for gamma-emitting nuclides and Strontium 90. All analyses met Minimum Detectable Activities. No fission or activation products were detected.
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8.4.3 Food Products A total of 6 samples of non-leafy vegetation were analyzed in 2023, for gamma emitting radionuclides, and strontium 90 in accordance with requirements of the ODCM, as summarized in Table 4, Radiological Environmental Monitoring Program -
Ingestion.
All non-leafy samples from all locations were analyzed as required by the ODCM for gamma-emitting nuclides and Strontium 90. All analyses met Minimum Detectable Activities. No fission or activation products were detected.
8.4.4 Leafy Vegetation In accordance with the ODCM and as described in Table 4, Radiological Environmental Monitoring Program - Ingestion, 36 broad leaf vegetation samples were collected from growing locations nearest site boundary in areas of highest predicted annual average ground level D/Q. Samples are collected and analyzed for gamma emitting radionuclides including I-131 from the indicator and control locations monthly during growing season, June through September. It is common to detect Cs-137 in broadleaf samples at both indicator and control locations. Cs-137 can be attributed to offsite sources such as weapons testing, Chernobyl, and Fukushima events. While Cs-137 is periodically found in vegetation samples, there was no Cs-137 detected in samples collected in 2023.
All leafy samples from all locations were analyzed as required by the ODCM for gamma-emitting nuclides and Strontium 90. All analyses met Minimum Detectable Activities. Strontium 90 was detected in cabbage collected 08/16/2023 at B10-2 Milton Hershey School at 17.6 +/- 2.9 pCi/kg wet. No other fission or activation products were detected in any other samples. This is below the investigation value of 50 pCi/kg for Sr-90 as listed in Attachment 1 of CY-AA-170-1000 Radiological Environmental Program and Meteorological Program Implementation.
9.0 LAND USE CENSUS An annual land use census is required by the Offsite Dose Calculation Manual and is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and modifications to REMP are made if required by changes in land use. The land use census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50 [2]. NUREG-1301/1302 Control 3.12.2 specifies that "a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 mi.) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation. Note, per NUREG-1301/1302, Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.
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A Land Use Census was conducted during the calendar year, 2023, within the growing season to identify changes in land use, receptor locations, and new exposure pathways. The results for the 2023 Land Use Census are listed in Table 8: Land Use Census - Nearest Receptors within 5 miles. In summary, the highest D/Q locations for nearest garden, nearest residence and nearest milk animal did not change following the 2023 census. Milk sites were identified in Seven (7) of sixteen (16) meteorological sectors. Milk sites were identified in N. NE, ENE, E, ESE, SE and S sectors. The nearest milk-producing animal in the WNW sector stopped producing milk and no other was found.
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Table 8: Land Use Census - Nearest Receptors within 5 miles Sector Direction Nearest Residence (Miles)
Nearest Milk Animal (Miles)
Nearest Garden (Miles)
A N
1.0 2.1 1.9 B
NNE 0.76 Not Found in Sector 1.2 C
NE 0.53 4.2 1.1 D
ENE 0.46 4.5 0.5 E
E 0.06 1.1 0.5 F
ESE 1.10 3.2 0.5 G
SE 0.71 1.4 0.6 H
SSE 0.71 Not Found in Sector 0.8**
J S
2.24
>5.0*
2.5 K
SSW 0.61 Not Found in Sector 1.6 L
SW 0.54 Not Found in Sector 1.7 M
WSW 1.20 Not Found in Sector 1.3 N
W 1.22 Not Found in Sector 1.3 P
WNW 1.11 Not Found in Sector 1.5 Q
NW 1.11 Not Found in Sector 1.2 R
NNW 1.14 Not Found in Sector 2.4
- Farm is outside the 5-mile radius but is included because it is a regularly sampled REMP milk farm
- A regularly sampled REMP farm 10.0 SAMPLE DEVIATIONS, ANOMALIES AND UNAVAILABILITY Sampling and analysis are performed for media types addressed in the Offsite Dose Calculation Manual. Sampling and analysis challenges may be experienced due to a multitude of reasons including environmental factors, loss of TLDs/OSLDs, contamination of samples, etc. To aid classification of sampling and analysis challenges experienced in 2023, the following three terms are used to describe the issues: Sample Anomalies, Sample Deviation, and Unavailable Samples.
Media that experienced downtime (i.e., air samplers or water samplers) during a surveillance period are classified a Sample Deviation. Sample Anomalies are defined as errors that were introduced to a sample once it arrived in the laboratory, errors that prevents the sample from being analyzed as it normally would or may have altered the outcome of the analysis (i.e., cross contamination, human error).
Sample Unavailability is defined as sample collection with no available sample (i.e.,
food crop, TLD).
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All required samples were collected and analyzed as scheduled except for the following:
Table 9: Sample Deviation Summary Sample Type and Analysis Location Collection Date or Period Reason for not conducting REMP sampling as required by ODCM Plans for preventing reoccurrence Milk /
Gamma P4-1 01/01/2023
-12/31/2023 Milk Farm did not have samples available due to farmer selling his herd.
Farmer indicated milk to be produced again in the future.
OSLD /
Dosimetry D1-1 12/14/2022
-03/28/2023 Lost upon receipt of OSLD at vendor lab (Landauer)
Entered into corrective action tracking to document occurrence OSLD /
Dosimetry P2-1 03/22/2023
-06/20/2023 Dosimeters and holder missing from location Metal frame is substantial and had to be pulled down forcefully from the pole 11.0 OTHER SUPPLEMENTAL INFORMATION 11.1 NEI 07-07 Onsite Radiological Groundwater Monitoring Program THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. It is important to note, samples and results taken in support of NEI 07-07 on-site groundwater monitoring program are separate from the Radiological Environmental Monitoring Program (REMP). Results of the NEI 07-07 Radiological Groundwater Monitoring Program for onsite groundwater wells are provided in the AREOR Attachment 5.
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11.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program ISFSI operations began in October 2021. Forty-seven casks were added to the Constellation TMI-1 ISFSI pad in 2022 utilizing the NAC MAGNASTOR System. Site boundary Environmental OSLDs, which measure gamma radiation closest to ISFSI are C1-2, D1-1, E1-4, F1-2, G1-3, K1-3, K1-5, L1-1, M1-1 and N1-3. OSLD K1-5 was added at the site boundary and OSLDs H1-3 and J1-4 were added as closest to the ISFSI pad. There was no radiation detected above background. Therefore, there was no direct radiation attributed to TMI from ISFSI operations to any real individual who is located beyond the control area. True Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeters (OSLD). Ninety-three OSLD locations were established around the site and listed in Table 5. Results of OSLD measurements are given in Attachment 4.
11.3 Corrections to Previous Reports No Errata to report in 2023.
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12.0 Bibliography
[1]
NCRP, "Report No. 160, Ionizing Radiation Exposure of the Population of the United States,"
National Council on Radiation Protection, Bethesda, 2009.
[2]
"10 CFR 50, "Domestic Licensing of Production and Utilization Facilities"," US Nuclear Regulatory Commission, Washington, DC.
[3]
"Regulatory Guide 4.1, "Radiological Environmental Monitoring for Nuclear Power Plants",
Revision 2," Nuclear Regulatory Commission, 2009.
[4]
"NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,.," Nuclear Regulatory Commission, April 1991.
[5]
"NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors,," Nuclear Regulatory Commission, April 1991.
[6]
"Branch Technical Position, Revision 1," NRC000096, Submitted March 30, 2012, November 1979.
[7]
"Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:
https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.
[8]
"Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"
Nuclear Regulatory Commission, July, 2007.
[9]
"Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019.
[10] "NUREG/CR-2919, XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,," Nuclear Regulatory Commission, September, 1982.
[11] "Measurements of Radionuclides in the environment Sampling and Analysis of plutonium in soil,"
Nuclear Regulatory Commission, 1974.
[12] "Ionizing Radiation Exposure of the Population of the United States," Bethesda, MD, 2009.
[13] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].
[14] "ICRP Publication 60, ICRP Publication 60: 1990 Recommendations of the International Commission on Radiological Protection, 60, Annals of the ICRP Volume 21/1-3,," International Commission on Radiation Protection, October, 1991.
[15] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html.
[Accessed 10 November 2020].
[16] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants,"
Nuclear Regulatory Commission, 1987.
[17] "Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I,,"
Nuclear Regulatory Commission, Ocotober, 1977.
[18] [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020].
[19] "NEI 07-07, Industry Ground Water Protection InitiativeFinal Guidance Document,," Nuclear Energy Institute, Washington, D.C..
Annual Radiological Environmental Operating Report YEAR: 2023 Page 40 of 88
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[20] "ANSI 13.37, Environmental Dosimetry-Criteria for System Design and Implementation," Health Physics Society (HPS), May, 2019.
[21] "40 CFR Part 141, National Primary Drinking Water Regulations,," US Environmental Protection Agency, Washington, DC..
[22] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].
[23] "NEI 07-07, Industry Ground Water Protection InitiativeFinal Guidance Document, Rev. 1,"
Nuclear Energy Institute, Washington, D.C., 2019.
[24] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].
[25] [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020].
[26] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:
https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.
[27] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html.
[Accessed 10 November 2020].
[28] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants,"
Nuclear Regulatory Commission, 1987.
[29] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].
[30] "Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019.
[31] "Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"
Nuclear Regulatory Commission, July, 2007.
[32] "10 CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.
[33] "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.
[34] "NUREG-0324 - XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," Nuclear Regulatory Commission, September, 1977.
[35] "NCRP Report No. 160 - Ionizing Radiation Exposure of the Population of the United States,"
National Council on Radiation Protection and Measurements, Bethesda, MD, 2009.
[36] "Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I,"
Nuclear Regulatory Commission, Ocotober, 1977.
[37] "40 CFR 141 - National Primary Drinking Water Regulations," US Environmental Protection Agency, Washington, DC..
[38] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.
[39] Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.
[40] Three Mile Island Nuclear Station, Unit 2, PDMS Technical Specifications, DPR 73.
Annual Radiological Environmental Operating Report YEAR: 2023 Page 41 of 88
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[41] Radiation Management Corporation. Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 - June 5, 1974. RMC-TR 17, January 1975.
[42] Constellation. Three Mile Island Nuclear Station Offsite Dose Calculation Manual (ODCM).
[43] National Council of Radiation Protection and Measurements Report No. 160. Ionizing Radiation Exposure of the Population of the United States. 2009.
[44] Teledyne Brown Engineering Environmental Services. "4th Quarter 2023 Quality Assurance Report", January - December 2023.
[45] GEL 2023 Annual Quality Assurance Report for the Radiological Environmental Monitoring Program (REMP) Rev.1.
[46] AMO Environmental Decisions, "2023 Annual RGPP Monitoring Report Summary of Results and Conclusions Three Mile Island Generating Station Middletown, Pennsylvania
Annual Radiological Environmental Operating Report YEAR: 2023 Page 42 of 88
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(( "#(
(!)""&*
Medium Sampled (Units)
Type, Total Number of Analyses performed (e.g., I-131, 400)
Lower Limit of Detection (LLD)
Indicator Mean;
(f).
Range1 Location with Highest Annual Mean Control Mean1 (f2).
Range1 Number of Nonroutine Reported Measurements Name Distance and Direction Mean1 (f2)
Range1 Air Particulates (pCi/m3)
Beta, 364 (0.01) 2.35 E-2, (312/312)
Q15-1, 13.4 miles, Sector Q 2.38 E-2, (52/52)
(7.74 E-3-4.28E-2) 2.38 E-2, (52/52)
(7.74 E-3-4.28E-2) 0 Direct Radiation (mrem/qtr.)
Gamma Dose, 716 NA 10.1 (15/16)
(7.1 - 13.4)
J1-3, 0.3 miles in Sector J 12.5 (8/8)
(11.8 - 13.4)
NA 0
Vegetation (pCi/kg-wet)
Strontium 90, 6 (10)
NA B10-2, 10 miles, Sector B 1.76E-2,(1/10)
(1.76E-2 +/- 2.9E-3) 1.76E-2, (1/10)
(1.76E-2 +/- 2.9E-3) 0 Effluent Water (pCi/L)
Gross Beta, 12 (4) 1.92, (12/12)
(1.05-2.72)
K1-1, 0.2miles, Sector K 1.92, (12/12)
(1.05-2.72)
NA 0
Tritium, 12 Monthly (200) 3867, (6/12),
(650-5620)
K1-1, 0.2miles, Sector K 867, (6/12),
(650-5620)
NA 0
Tritium, 4 Quarterly (200) 4610, (2/4)
(2760-6460)
K1-1, 0.2miles, Sector K 4610, (2/4)
(2760-6460)
NA 0
6 Mean and range are based on detectable measurements only.
7 Fraction of detectable measurements at specified locations is indicated in parentheses.
Annual Radiological Environmental Operating Report YEAR: 2023 Page 43 of 88
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Medium Sampled (Units)
Type, Total Number of Analyses performed (e.g., I-131, 400)
Lower Limit of Detection (LLD)
Indicator Mean;
(f).
Range1 Location with Highest Annual Mean Control Mean1 (f2).
Range1 Number of Nonroutine Reported Measurements Name Distance and Direction Mean1 (f2)
Range1 Surface Water (pCi/L)
Low Level I-131, 24 (1.0)
NA A3-2, 2.7 miles, Sector A 1.89, (2/12)
(1.10-2.48) 1.89, (2/12)
(1.10-2.48) 0 Tritium, 36 (200) 920, (5/12),
(680-1090)
J1-2, 0.5 miles Sector J 920, (5/12),
(680-1090) 152+/-87, (1/12)
(152-152) 0 Tritium:
8 Quarterly (200) 1078, (2/4)
(635-1520)
J1-2, 0.5 miles Sector J 1078, (2/4)
(635-1520)
NA 0
Drinking Water (pCi/L)
Tritium:
12 Quarterly (200) 118 +/- 83, (1/4),
(118+/-83)
G15-3, 15.7 miles, Sector G 118 +/- 83, (1/4),
(118+/-83)
NA 0
Gross Beta, 36 (4) 2.50, (23/24)
(0.94-4.20)
G15-2, 13.3 miles, Sector G 3.01, (12/12) 1.75, (12/12)
(1.08-2.78) 0
Annual Radiological Environmental Operating Report YEAR: 2023 Page 44 of 88
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(( "#( $"%!(
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13.0 REMP RESULTS: Data Tables Table 10: Quarterly isotopic data - Air (pCi/m3), Milk (pCi/L), and Water (pCi/L) and Semi Annual Sr89/90 at K1-1 Location Nuclide Q1 Q2 Q3 Q4 Quarterly Air Filter Composite for Gamma Emitters (pCi/m3)
E1-2 Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs F1-3 Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs G2-1 Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs M2-1 Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs A3-1 Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs H3-1 Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs Q15-1 (Control)
Cs134, Cs137
<MDAs
<MDAs
<MDAs
<MDAs Quarterly Strontium 90 in Milk (pCi/L)
F4-1 Sr90
<MDA
<MDA
<MDA
<MDA G2-1 Sr90
<MDA
<MDA
<MDA
<MDA J18-1 (Control)
Sr90
<MDA
<MDA
<MDA
<MDA Quarterly Tritium in Water (pCi/L)
G15-2 (Control)
<MDA
<MDA
<MDA
<MDA G15-3 H-3
<MDA 118 +/- 83
<MDA
<MDA
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Q9-1 (DW)
<MDA
<MDA
<MDA
<MDA Q9-1 (SW)
<MDA
<MDA
<MDA
<MDA J1-2 H-3 1520 +/- 198 635 +/- 140
<MDA
<MDA K1-1 H-3 6460 +/- 3888 2760 +/- 244
<MDA
<MDA NOTE: <MDA denotes laboratory analysis detected No non-natural radionuclides at or above the ODCM required Minimum Detectable Activity Table 11: Continued: Complete REMP Results Monthly Radionuclides in Surface Water (pCi/L)
Date A3-2 (Control)
Q9-1 (SW)
J1-2 K1-1 I-131 Tritium Gamma Tritium Gamma Emitters Tritium Gamma Emitters Gross Beta Tritium Sr89/90 (Semi-Annual Composite) 2/2/2023 1.10 +/- 0.43 ND 1020 +/- 109 1.55+/-0.82 4350 +/- 174 3/2/2023 ND 880 +/- 138 2.47+/-0.72 4280 +/- 229 3/30/2023 ND 152 +/- 87 680 +/- 136 1.05+/-0.69 4860 +/- 329 4/26/2023 2.48 +/- 0.61 ND 1090 +/- 193 1.64+/-0.69 5620 +/- 405 6/1/2023 ND 932 +/- 191 2.02+/-0.68 3440 +/- 331 6/29/2023 ND 2.25+/-0.81 650 +/- 145 7/27/2023 ND 1.73+/-0.72 8/31/2023 ND 2.15+/-0.73 9/28/2023 ND 1.53+/-0.71 11/2/2023 ND 2.72+/-0.77 11/29/2023 ND 1.93+/-0.76 12/28/2023 ND 2.03+/-0.78
- All Non Natural Radionuclides <MDA ND No Data, Samples not analyzed for this parameter
Annual Radiological Environmental Operating Report YEAR: 2023 Page 46 of 88
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Monthly Radionuclides in Drinking Water (pCi/L)
Location G15-2 G15-3 Q9-1 (DW) (Control)
Date Gamma Emitters Tritium Gross Beta Activity Uncertainty (2-)
Gamma Emitters Tritium Gross Beta Activity Uncertainty (2-)
Gamma Emitters Tritium Gross Beta Activity Uncertainty (2-)
2/2/2023 3.24E+00 8.16E-01 1.29E+00 6.70E-01 1.37E+00 6.76E-01 3/2/2023 1.89E+00 6.78E-01 1.78E+00 6.68E-01 1.70E+00 6.62E-01 3/30/2023 2.25E+00 7.87E-01
<MDA 1.16E+00 7.03E-01 4/26/2023 2.44E+00 7.56E-01 9.44E-01 6.36E-01 1.08E+00 6.47E-01 6/1/2023 4.20E+00 8.35E-01 2.78E+00 7.35E-01 2.78E+00 7.34E-01 6/29/2023 3.05E+00 8.56E-01 2.01E+00 7.89E-01 1.60E+00 7.60E-01 7/27/2023 3.21E+00 8.29E-01 3.16E+00 8.22E-01 1.98E+00 7.42E-01 8/31/2023 3.79E+00 8.43E-01 2.45E+00 7.49E-01 1.97E+00 7.15E-01 9/28/2023 2.99E+00 8.23E-01 1.89E+00 7.44E-01 2.14E+00 7.63E-01 11/2/2023 3.50E+00 8.28E-01 1.43E+00 6.75E-01 2.08E+00 7.27E-01 11/29/2023 3.07E+00 8.41E-01 2.07E+00 7.67E-01 1.43E+00 7.21E-01 12/28/2023 2.44E+00 8.12E-01 1.61E+00 7.46E-01 1.65E+00 7.51E-01
- All Non Natural Radionuclides <MDA Monthly Gamma Emitters in Milk (pCi/L)
Date F4-1 G2-1 J18-1 (Control) 1/11/2023 2/15/2023 3/8/2023 3/22/2023 4/6/2023
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4/20/2023 5/3/2023 5/17/2023 5/31/2023 6/14/2023 6/28/2023 7/12/2023 7/26/2023 8/9/2023 8/23/2023 9/6/2023 9/21/2023 10/4/2023 10/18/2023 11/1/2023 11/15/2023 11/29/2023 12/14/2023
- All Non Natural Radionuclides <MDA
Annual Radiological Environmental Operating Report YEAR: 2023 Page 48 of 88
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Radionuclides in Vegetation (pCi/kg wet)
Sample Code Sample Date Sample Type Sr90 Gamma Emitters E1-2
$%%$*(
East of site at Visitors Center
756$4'4((05
41&&1.,
$.(
$%%$*(
41&&1.,
$.(
$%%$*(
$7.,).19(4
16$61(5
!1/$61(5
140
1..$4'5
9,55+$4'
$.(
H1-2
$%%$*(
Red Hill Market
- 7&&+,0,
7&7/%(4
37$5+
7&7/%(4
- 7&&+,0,
7/2-,0($8(5
Annual Radiological Environmental Operating Report YEAR: 2023 Page 49 of 88
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(.10($8(5
- 7&&+,0,
$7.,).19(4
41&&1.,
4755(.5 241765
B10-2 (Control)
$%%$*(
Milton Hershey School
41&&1.,
1-+1:($8(5
$.(
1..$4'5
41&&1.,
$.(
1..$4'5
$%%$*(
;
!1/$61(5
16$61(5
140
**2.$06($8(5
(22(4($8(5
7/2-,0($8(5
- All Non-Natural Gamma Emitters <MDA ND No Data, Analysis not required
Annual Radiological Environmental Operating Report YEAR: 2023 Page 50 of 88
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Radionuclides in Vegetation (pCi/kg wet)
Sample Code Sample Date Sample Type Sr90 Gamma Emitters BKG (Control)
1661/(('(4 Upstream of Station Discharge
4('$614,5+
10/10/2023
1661/(('(4 10/10/2023
4('$614,5+
IND 6/15/2023
1661/(('(4 Downstream of Station Discharge 6/19/2023
4('$614,5+
10/4/2023
4('$614,5+
- All Non-Natural Gamma Emitters <MDA Radionuclides in Sediment (pCi/kg dry)
Sample Code Sample Date Gamma Emitters A3-1 (Control) 6/14/2023 North Tip of TMI 10/19/2023 in Susquehanna River J2-1 6/14/2023 South of TMINS & upstream of York Haven Dam, in Susquehanna River 10/19/2023 K1-3 downstream of TMINS liquid discharge in Susquehanna River 6/14/2023 10/19/2023
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Weekly Airborne Samples for I-131 (pCi/m3)
Date E1-2 F1-3 G2-1 M2-1 A3-1 H3-1 Q15-1 Control) 1/4/2023
1/11/2023
1/18/2023
1/26/2023
2/2/2023
2/8/2023
2/15/2023
2/23/2023
3/2/2023
3/9/2023
3/16/2023
3/23/2023
3/30/2023
4/6/2023
4/13/2023
4/20/2023
4/26/2023
5/4/2023
5/11/2023
5/18/2023
5/25/2023
6/1/2023
6/8/2023
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6/15/2023
6/22/2023
6/29/2023
7/5/2023
7/13/2023
7/20/2023
7/27/2023
8/3/2023
8/9/2023
8/17/2023
8/24/2023
8/31/2023
9/7/2023
9/14/2023
9/21/2023
9/28/2023
10/4/2023
10/12/2023
10/18/2023
10/25/2023
11/2/2023
11/9/2023
11/16/2023
11/22/2023
11/29/2023
Annual Radiological Environmental Operating Report YEAR: 2023 Page 53 of 88
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12/7/2023
12/14/2023
12/21/2023
12/28/2023
- <MDA, Minimum Detectable Activity Gross Beta activity in Air Particulates (pCi/m3)
E1-2 F1-3 G2-1 M2-1 A3-1 H3-1 Q15-1 Control)
Date Gross Beta Activity (2-)
Gross Beta Activity (2-)
Gross Beta Activity (2-)
Gross Beta Activity (2-)
Gross Beta Activity (2-)
Gross Beta Activity (2-)
Gross Beta Activity (2-)
1/4/2023 3.27E-02 2.80E-03 3.52E-02 2.85E-03 3.54E-02 2.85E-03 3.55E-02 2.85E-03 2.56E-02 2.12E-03 3.32E-02 2.79E-03 3.93E-02 2.99E-03 1/11/2023 2.38E-02 2.39E-03 2.60E-02 2.44E-03 2.72E-02 2.48E-03 2.56E-02 2.38E-03 2.18E-02 2.28E-03 2.44E-02 2.41E-03 2.71E-02 2.46E-03 1/18/2023 2.11E-02 2.23E-03 2.06E-02 2.19E-03 2.31E-02 2.26E-03 1.98E-02 2.15E-03 1.99E-02 2.15E-03 2.11E-02 2.20E-03 2.15E-02 2.23E-03 1/26/2023 1.57E-02 1.77E-03 1.49E-02 1.73E-03 1.50E-02 1.73E-03 1.40E-02 1.68E-03 1.43E-02 1.69E-03 1.47E-02 1.73E-03 1.51E-02 1.77E-03 2/2/2023 2.54E-02 2.34E-03 2.55E-02 2.33E-03 2.72E-02 2.37E-03 2.56E-02 2.36E-03 2.59E-02 2.33E-03 2.54E-02 2.31E-03 2.66E-02 2.40E-03 2/8/2023 2.80E-02 2.61E-03 2.92E-02 2.62E-03 3.24E-02 2.73E-03 2.90E-02 2.54E-03 3.07E-02 2.63E-03 2.99E-02 2.66E-03 2.99E-02 2.60E-03 2/15/2023 2.75E-02 2.44E-03 2.78E-02 2.43E-03 2.62E-02 2.37E-03 2.71E-02 2.42E-03 2.87E-02 2.45E-03 2.63E-02 2.38E-03 2.87E-02 2.49E-03 2/23/2023 2.34E-02 2.10E-03 2.43E-02 2.11E-03 2.27E-02 2.05E-03 2.34E-02 2.10E-03 2.45E-02 2.10E-03 2.41E-02 2.09E-03 2.45E-02 2.14E-03 3/2/2023 1.76E-02 2.12E-03 1.78E-02 2.10E-03 1.66E-02 2.05E-03 1.54E-02 2.01E-03 1.67E-02 2.04E-03 1.86E-02 2.13E-03 1.80E-02 2.12E-03 3/9/2023 1.74E-02 2.05E-03 1.67E-02 2.01E-03 1.81E-02 2.05E-03 1.87E-02 2.07E-03 1.95E-02 2.09E-03 1.79E-02 2.05E-03 1.78E-02 2.06E-03 3/16/2023 1.09E-02 1.92E-03 1.13E-02 1.92E-03 1.16E-02 1.92E-03 1.21E-02 1.94E-03 1.11E-02 1.89E-03 1.14E-02 1.92E-03 1.06E-02 1.90E-03 3/23/2023 2.35E-02 2.33E-03 2.53E-02 2.36E-03 2.42E-02 2.32E-03 2.40E-02 2.31E-03 2.34E-02 2.28E-03 2.33E-02 2.30E-03 2.55E-02 2.37E-03 3/30/2023 2.49E-02 2.32E-03 2.56E-02 2.32E-03 2.58E-02 2.32E-03 2.68E-02 2.36E-03 2.63E-02 2.33E-03 2.70E-02 2.37E-03 2.67E-02 2.37E-03 4/6/2023 2.32E-02 2.25E-03 2.55E-02 2.30E-03 2.63E-02 2.33E-03 2.49E-02 2.22E-03 2.55E-02 2.27E-03 2.72E-02 2.38E-03 2.64E-02 2.30E-03 4/13/2023 2.79E-02 2.51E-03 3.01E-02 2.70E-03 2.95E-02 2.52E-03 3.19E-02 2.63E-03 3.01E-02 2.54E-03 3.16E-02 2.58E-03 3.05E-02 2.60E-03 4/20/2023 2.03E-02 2.26E-03 2.18E-02 2.30E-03 2.06E-02 2.24E-03 2.29E-02 2.36E-03 1.98E-02 2.22E-03 1.85E-02 2.17E-03 2.20E-02 2.34E-03 4/26/2023 1.92E-02 2.39E-03 1.93E-02 2.37E-03 2.20E-02 2.46E-03 2.30E-02 2.50E-03 1.88E-02 2.33E-03 2.21E-02 2.48E-03 1.84E-02 2.34E-03 5/4/2023 8.69E-03 1.61E-03 8.42E-03 1.58E-03 9.96E-03 1.64E-03 8.66E-03 1.59E-03 8.33E-03 1.57E-03 8.16E-03 1.57E-03 7.74E-03 1.56E-03
Annual Radiological Environmental Operating Report YEAR: 2023 Page 54 of 88
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5/11/2023 1.37E-02 1.90E-03 1.38E-02 1.89E-03 1.48E-02 1.91E-03 1.23E-02 1.71E-03 1.39E-02 1.89E-03 9.85E-03 3.89E-03 1.25E-02 1.83E-03 5/18/2023 2.66E-02 2.47E-03 2.67E-02 2.45E-03 2.79E-02 3.31E-03 2.57E-02 2.28E-03 2.40E-02 2.37E-03 2.77E-02 2.45E-03 2.48E-02 2.40E-03 5/25/2023 1.70E-02 2.06E-03 1.89E-02 2.11E-03 1.74E-02 2.06E-03 1.95E-02 2.00E-03 1.78E-02 2.07E-03 1.86E-02 2.07E-03 1.98E-02 2.14E-03 6/1/2023 1.57E-02 1.98E-03 1.67E-02 2.00E-03 1.62E-02 1.97E-03 1.61E-02 1.86E-03 1.60E-02 1.97E-03 1.75E-02 2.00E-03 1.74E-02 2.03E-03 6/8/2023 2.20E-02 2.22E-03 2.60E-02 2.34E-03 2.39E-02 2.26E-03 2.17E-02 2.06E-03 2.25E-02 2.21E-03 2.37E-02 2.23E-03 2.33E-02 2.25E-03 6/15/2023 1.58E-02 2.11E-03 1.55E-02 2.08E-03 1.57E-02 2.07E-03 1.44E-02 1.91E-03 1.51E-02 2.06E-03 1.72E-02 2.11E-03 1.88E-02 2.20E-03 6/22/2023 1.64E-02 2.07E-03 2.09E-02 2.21E-03 1.86E-02 2.12E-03 1.84E-02 1.99E-03 2.04E-02 2.19E-03 1.96E-02 2.14E-03 1.72E-02 2.09E-03 6/29/2023 1.39E-02 1.96E-03 1.46E-02 1.97E-03 1.36E-02 1.92E-03 1.24E-02 1.76E-03 1.28E-02 1.90E-03 1.31E-02 1.88E-03 1.45E-02 1.97E-03 7/5/2023 2.46E-02 2.62E-03 2.41E-02 2.58E-03 2.38E-02 2.55E-03 2.33E-02 2.40E-03 2.64E-02 2.65E-03 2.38E-02 2.53E-03 2.43E-02 2.59E-03 7/13/2023 3.31E-02 2.40E-03 2.88E-02 2.25E-03 2.89E-02 3.13E-03 2.73E-02 2.09E-03 3.15E-02 2.33E-03 3.20E-02 2.32E-03 2.85E-02 2.25E-03 7/20/2023 2.81E-02 2.55E-03 2.78E-02 2.52E-03 2.74E-02 2.49E-03 2.80E-02 2.38E-03 2.96E-02 2.57E-03 2.92E-02 2.53E-03 2.86E-02 2.55E-03 7/27/2023 2.42E-02 2.32E-03 2.32E-02 2.27E-03 2.37E-02 2.27E-03 2.40E-02 2.17E-03 2.12E-02 2.20E-03 2.43E-02 2.28E-03 2.41E-02 2.31E-03 8/3/2023 2.56E-02 2.37E-03 2.39E-02 2.29E-03 2.70E-02 2.45E-03 2.16E-02 2.09E-03 2.64E-02 2.37E-03 2.41E-02 2.27E-03 2.46E-02 2.32E-03 8/9/2023 2.39E-02 2.63E-03 2.22E-02 2.54E-03 2.28E-02 2.59E-03 2.01E-02 2.32E-03 2.34E-02 2.59E-03 2.11E-02 2.46E-03 1.96E-02 2.46E-03 8/17/2023 2.35E-02 2.23E-03 2.52E-02 2.26E-03 2.38E-02 2.20E-03 2.31E-02 2.06E-03 2.64E-02 2.29E-03 2.36E-02 2.18E-03 2.59E-02 2.28E-03 8/24/2023 2.33E-02 2.38E-03 2.30E-02 2.35E-03 2.34E-02 2.35E-03 2.21E-02 2.18E-03 2.27E-02 2.34E-03 2.22E-02 2.29E-03 2.46E-02 2.41E-03 8/31/2023 2.28E-02 2.30E-03 2.17E-02 2.25E-03 2.23E-02 2.25E-03 2.04E-02 2.07E-03 2.36E-02 2.31E-03 2.16E-02 2.21E-03 2.29E-02 2.29E-03 9/7/2023 3.66E-02 2.78E-03 3.72E-02 2.77E-03 3.69E-02 2.75E-03 3.28E-02 2.50E-03 3.43E-02 2.69E-03 3.23E-02 2.60E-03 3.56E-02 2.73E-03 9/14/2023 2.87E-02 2.49E-03 2.76E-02 2.43E-03 2.99E-02 2.49E-03 2.87E-02 2.33E-03 2.91E-02 2.48E-03 2.70E-02 2.38E-03 2.69E-02 2.42E-03 9/21/2023 2.38E-02 2.36E-03 2.18E-02 2.28E-03 2.16E-02 2.26E-03 2.07E-02 2.10E-03 2.16E-02 2.27E-03 2.33E-02 2.29E-03 2.33E-02 2.33E-03 9/28/2023 1.50E-02 2.02E-03 1.40E-02 1.96E-03 1.39E-02 1.94E-03 1.45E-02 1.87E-03 1.51E-02 2.00E-03 1.35E-02 1.92E-03 1.45E-02 1.98E-03 10/4/2023 2.41E-02 2.63E-03 2.83E-02 2.74E-03 2.56E-02 2.64E-03 2.32E-02 2.41E-03 2.27E-02 2.55E-03 2.34E-02 2.54E-03 2.71E-02 2.71E-03 10/12/2023 2.98E-02 2.35E-03 2.68E-02 2.25E-03 2.55E-02 2.20E-03 2.51E-02 2.07E-03 2.62E-02 2.23E-03 2.49E-02 2.17E-03 2.68E-02 2.25E-03 10/18/2023 1.36E-02 2.25E-03 1.45E-02 2.27E-03 1.20E-02 2.16E-03 1.27E-02 2.01E-03 1.17E-02 2.14E-03 1.15E-02 2.13E-03 1.16E-02 2.12E-03 10/25/2023 2.11E-02 2.24E-03 1.99E-02 2.19E-03 1.84E-02 2.11E-03 1.85E-02 2.04E-03 1.61E-02 5.12E-03 2.04E-02 2.16E-03 1.72E-02 2.11E-03 11/2/2023 2.75E-02 2.29E-03 2.56E-02 2.21E-03 2.71E-02 2.26E-03 2.74E-02 2.14E-03 2.69E-02 2.25E-03 2.64E-02 2.22E-03 2.46E-02 2.19E-03 11/9/2023 4.22E-02 2.89E-03 4.26E-02 2.88E-03 3.82E-02 2.74E-03 3.82E-02 2.60E-03 4.15E-02 2.84E-03 4.59E-02 2.92E-03 4.28E-02 2.88E-03 11/16/2023 3.00E-02 2.51E-03 2.89E-02 2.45E-03 2.67E-02 2.36E-03 3.02E-02 2.35E-03 2.96E-02 2.47E-03 2.83E-02 2.40E-03 2.81E-02 2.43E-03
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11/22/2023 3.07E-02 2.87E-03 3.01E-02 2.83E-03 3.19E-02 2.87E-03 2.82E-02 2.60E-03 3.06E-02 2.84E-03 2.89E-02 2.75E-03 3.10E-02 2.86E-03 11/29/2023 2.30E-02 2.38E-03 2.22E-02 2.34E-03 2.34E-02 2.36E-03 2.20E-02 2.19E-03 2.41E-02 2.40E-03 2.24E-02 2.30E-03 2.28E-02 2.36E-03 12/7/2023 3.84E-02 2.55E-03 3.45E-02 2.43E-03 3.85E-02 2.53E-03 3.64E-02 2.35E-03 3.82E-02 2.53E-03 3.87E-02 2.52E-03 3.85E-02 2.54E-03 12/14/2023 2.94E-02 2.54E-03 2.71E-02 2.45E-03 2.68E-02 2.42E-03 2.60E-02 2.24E-03 2.88E-02 2.49E-03 2.95E-02 2.51E-03 2.72E-02 2.44E-03 12/21/2023 3.08E-02 2.56E-03 2.76E-02 2.44E-03 3.18E-02 2.56E-03 3.04E-02 2.43E-03 2.93E-02 2.50E-03 2.82E-02 2.41E-03 3.05E-02 2.57E-03 12/28/2023 2.24E-02 2.25E-03 2.21E-02 2.22E-03 2.02E-02 2.14E-03 2.30E-02 2.13E-03 2.47E-02 2.31E-03 2.22E-02 2.19E-03 2.32E-02 2.26E-03
Annual Radiological Environmental Operating Report YEAR: 2023 Page 56 of 88
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Participation in cross check intercomparison studies is mandatory for laboratories performing analyses of REMP samples satisfying the requirements in the Offsite Site Dose Calculation Manual. Intercomparison studies provide a consistent and effective means to evaluate the accuracy and precision of analyses performed by a laboratory.
Study results should fall within specified control limits and results that fall outside the control limits are investigated and corrected.
Constellation Generation Solutions Laboratory participated in the following proficiency testing studies provided by Environmental Resource Associates (ERA), and Eckert Ziegler Analytics etc.} in 2023. The Laboratorys intercomparison program results for 2023 are summarized below. is a summary of Constellation Generation Solutions (CGS) laboratorys quality assurance program. It consists of Table 12 which is a compilation of the results of the CGS laboratorys participation in an interlaboratory comparison program with Environmental Resource Associates (ERA) located in Arvada, Colorado and Eckert and Ziegler Analytics, Inc. (EZA) located in Atlanta, Georgia.
It also includes a compilation of the results of the Constellation Generation Solutions (CGS) Laboratorys participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee.
The CGS laboratorys intercomparison results, are in full agreement when they were evaluated using the NRC Resolution Test Criteria [1] except as noted in the Pass/Fail column and described below. The CGS laboratorys results are provided with their analytical uncertainties of 2 sigma. When evaluating with the NRC Resolution Test a one sigma uncertainty is used to determine Pass or Fail and noted accordingly.
All results reported passed their respective vendor acceptance ranges and NRC Resolution Test Criteria [1] with one exception for the Water Study ERA RAD 133, reference date 4/10/2023. The CGS lab reported a result of 26.3 pCi/L for Ba-133 which passed the NRC Resolution Test Criteria but failed the Vendor Acceptance Range of 17.1-25.8 pCi/L. This high result is for a low concentration of an isotope with low statistics that historically is observed at the lower end of acceptable data ranges. In this case however, the result was an outlier and should have been flagged out of trend and not passed internal QA review. This event has been entered into the Corrective Action Program for tracking and to prevent future occurrence.
The vendor laboratories used by CGS for subcontracting and interlaboratory comparison samples, GEL Laboratories and Teledyne Brown Engineering, also participate in the ERA and EZA interlaboratory comparison program. A presentation of their full data report is provided in their Annual Environmental Quality Assurance Program Reports, (Ref 44,45). In summary Gel and TBE reported results met vendor and laboratory acceptance ranges with the following exceptions discussed here:
For the TBE laboratory, 110 out of 115 analyses performed met the specified acceptance criteria. Five analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program. A summary is found below:
Annual Radiological Environmental Operating Report YEAR: 2023 Page 57 of 88
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- 1. TBE result for ERA RAD April 2023 water Ba-133 result was evaluated as Not Acceptable. The reported value was 26.0 pCi/L and the known was 22.3 (acceptance range 17.1 - 25.8 pCi) or 117% of the known (acceptable for TBE QC).
The sample was used as the workgroup duplicate with a result of 25.4 (114%). The sample had also been counted on a different detector with a result of 21.9 (98%).
This was TBEs first failure for Ba-133.
(NCR 23-10)
- 2. The ERA RAD October 2023 water Gross Alpha result was evaluated as Not Acceptable. The reported result was 53.2 pCi/L and the known result was 70.6 (acceptable range of 54.0 - 87.2 pCi/L). The reported result was the workgroup duplicate and was within 75% of the known value (within TBE QC range). The original result was 63.3 pCi/L (90% of the known). Because the LCS result was biased slightly high, the decision was made to report the lower value. (NCR 23-20)
The reported value was 23.5 pCi/L and the known result was 29.7 (acceptable range of 25.8 - 33.6) The reported result was 79% of the known, which is within the acceptable TBE QC range. The workgroup was reviewed with no anomalies found.
The LCS/LCSD results were 109% and 86.1%. The sample was not processed in a timely manner as per the ERA instructions which stated to analyze shortly after receipt due to the short half-life. Going forward, the QA &/or Lab Mgr. will ensure that this analysis is started sooner.
(NCR 23-21)
- 4. The MAPEP February 2023 vegetation Sr-90 result was evaluated as Not Acceptable. The reported value was 0.05 Bq (not detected) and the known result was a false positive. This was considered to be a statistical failure because TBEs reported result with 3 times the uncertainty resulted in a slightly positive net result (0.03194 Bq/kg). The reported result was significantly below TBEs average detection limit for vegetation samples.
(NCR 23-09)
- 5. The Analytics September 2023 milk Sr-90 result was evaluated as Not Acceptable.
The reported result was 7.28 pCi/L and the known result was 12.8 (57% of known).
This sample was used as the workgroup duplicate and the carrier yields for both samples were 107% and 75%. The LCS recovery for the workgroup was at 106%.
The ERA drinking water Sr-90 cross check that was analyzed around the same time was acceptable at 108%. There was no explanation for the failure. This is the first low biased failure for Sr-90 milk. The last failure (high) was in 2016. (NCR 23-24)
For the GEL Laboratory, nine analyses from four performance evaluation studies did not meet the specified acceptance criteria and were addressed through the GELs internal nonconformance system. A summary is found below:
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- 1. RAD-132 Water failed three parameters. All data and laboratory processes were evaluated and no errors were found. The investigation determined that the laboratory met all quality control criteria specified in the methods and failures were tracked through GELs internal nonconformance system.
Zinc-65 was reported at 126pCi/L with a Reference Value of 105pCi/L and acceptance range of (94.5 - 125 pCi/l). The unacceptable error is due to an un known error.
Tritium was reported at 18,000pCi/L with a Reference Value of 21,600pCi/L and acceptance range of (18,900-23,800pCi/L). The laboratory has concluded that this low bias was an isolated occurrence and that the overall process is within control.
Iodine-131 was reported at 16.8pCi/L with a Reference Value of 27pCi/L and acceptance range of (22.4 - 31.8 pCi/l). Having found no errors the laboratory continues to investigate all steps of the analytical process including the standardization of the carrier reagent as a possible contributor to the low bias.
- 2. E13890 Milk failed Strontium-90. All data and laboratory processes were evaluated and no errors were found. The investigation determined that the laboratory met all quality control criteria specified in the method and failures were tracked through GELs internal nonconformance system. Strontium-90 was reported at 6.21pCi/L with a Reference Value of 12.7pCi/L and acceptance range of (7.62 - 15.88 pCi/l). The laboratory reviewed the data for this analysis and no errors were found. It was noted that both the Strontium and Yttrium carriers recovered greater than is typically seen for this method which could cause a potential low bias in the results. Due to the Sr-89 result being with acceptance limits, it is also suspected that an undetermined error occurred during the second separation resulting in a low Y-90 recovery.
- 3. RAD-134 Water failed three parameters. The investigation determined that the laboratory met all quality control criteria specified in the method. Additionally, all internal procedures and policies were performed as required. Thes failures were tracked through GELs internal non-conformance system.
Barium-133 was reported at 75.7pCi/L with a Reference Value of 66pCi/L and acceptance range of (55.4 - 73.2 pCi/l). The data was reviewed and no errors were found. The result recovered at 114% of the reference value which is within the laboratorys acceptance criteria for LCS recovery. The batch Duplicate result was within the acceptance range of the study and met batch replication criteria with the sample result. Historical performance evaluation results do not indicate a high bias for this parameter. Additionally, a contributing factor is how long the samples were counted. The laboratorys SOP indicates drinking water samples are typically counted for 4 hrs. This results in an uncertainty associated with the result that approaches the acceptable range.
Strontium 89 was reported at 61.8pCi/L and 59.6pCi/l with a Reference Value of 51.2pCi/L and acceptance range of (40.4 - 58.7pCi/l).Strontium 90 was reported at
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58.2pCi/L with a Reference Value of 45.0pCi/L and acceptance range of (33.2 -
51.6pCi/L). The data for the drinking water PT analysis has been reviewed and no anomalies were noted. The Strontium-89 result recovered at 118% (905.0 Mod) and 116% (905.0) which is within the laboratorys acceptance criteria for LCS recovery.
The sample was analyzed in duplicate for each method, and the duplicate results were within the acceptance range of the study. While the Stontium-90 LCS for the batch met recovery requirements, the recovery was higher than is typically recovered for these methods. The two gravimetrical yields that are determined in the drinking water method were reviewed. It was noted that the yields were closer to the lower end of the acceptance range. It is possible that the yield recoveries contributed to bias in the results. For the failed Strontium-90, it was noted also that the first prep of the sample needed to be reanalyzed due to low yields. A smaller sample volume was used in the reanalysis, and this may have contributed to variation in the results and greater uncertainty in the measurement.
Iodine-131 was reported at 29.1pCi/L with a Reference Value of 24.4pCi/L and acceptance range of (20.2 - 28.9 pCi/l). The data for the drinking water PT analysis has been reviewed and no anomalies were noted. The laboratory has reviewed the data for this analysis and no errors were found. The result recovered at 119% of the reference value which is within the laboratorys acceptance criteria for LCS recovery.
The Duplicate in the analysis batch was within the acceptance range of the study and met replication criteria with the sample result. Review of historical results for I-131 performance evaluation samples by this method does not indicate a high bias.
- 4. MRAD-39 Soil failed two parameters. The investigation determined that the laboratory met all quality control criteria specified in the method. Additionally, all internal procedures and policies were performed as required. These failures were tracked through GELs internal nonconformance system.
Cesium-137 was reported at 1290pCi/Kg with a Reference Value of 1780pCi/Kg and acceptance range of (1350 - 2250pCi/Kg).
Cobalt-60 was reported at 5760 pCi/Kg with a Reference Value of 7960pCi/Kg and acceptance range of (6270 - 9830 pCi/Kg).
The Interlaboratory results also consist of interlaboratory comparison results for routine samples split for analyses between CGS and its subcontractor, GEL, as the primary REMP Laboratory and TBE as the QA laboratory. Analysis evaluated were Tritium, Strontium 90, Beta and non-natural gamma emitters. The CGS laboratorys results are provided with their analytical uncertainties of 2 sigma.
When evaluating with the NRC Resolution Test a one sigma uncertainty is used to determine Pass or Fail and noted accordingly. In the event there are no non-natural isotopes detected, the samples are reported <MDA and designated as Pass.
The results contained in the Interlaboratory Comparison Table generally agree with their respective CGS laboratory original, and Teledyne Brown Engineerings split laboratory sample according to NRC
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Resolution Test Criteria1. Instances where the split data does not meet NRC Resolution test Criteria are for Gross Beta analysis and likely due to the fact that the CGS laboratory counts samples generally an order of magnitude below required MDAs thus achieving very low uncertainties which results in a very tight range of acceptance when comparing to TBEs results that are counted to meet the required MDAs resulting in greater uncertainty in the data.
Table 12: Cross Check Intercomparison Results Reference Date Standard Media Type Analysis Type Units Nuclide Reported Value Assigned Value NRC Resolution Test Pass / Fail
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88.6 90.1 Pass
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86.6 90.1 Pass
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83.2 90.1 Pass
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5
228 229 Pass
,.-
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69.1 82.0 Pass
5
177 200 Pass
5
133 140 Pass
(
150 139 Pass
4
307 302 Pass
0
172 180 Pass
1
125 131 Pass
(
118 122 Pass
1
267 279 Pass
- 0
284 306 Pass
,.-
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71.7 82.0 Pass
5
179 200 Pass
5
138 140 Pass
(
143 139 Pass
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Table 12: Cross Check Intercomparison Results Reference Date Standard Media Type Analysis Type Units Nuclide Reported Value Assigned Value NRC Resolution Test Pass / Fail
4
272 302 Pass
0
184 180 Pass
1
126 131 Pass
(
116 122 Pass
1
258 279 Pass
- 0
276 306 Pass
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26.3 22.3 Fail 1
5
75.6 77.6 Pass
5
61.0 61.0 Pass
1
31.8 30.3 Pass
- 0
230 242 Pass
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50.7 60.7 Pass
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28.1 28.7 Pass
1,.
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5
0.285 0.292 Pass
5
0.423 0.441 Pass
1,.
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0.320 0.292 Pass
5
0.490 0.441 Pass
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205 205 Pass
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91.0 82.5 Pass
1
102 94.7 Pass
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237 252 Pass
4
175 201 Pass
5
121 126 Pass
5
162 158 Pass
(
127 118 Pass
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Table 12: Cross Check Intercomparison Results Reference Date Standard Media Type Analysis Type Units Nuclide Reported Value Assigned Value NRC Resolution Test Pass / Fail
0
113 112 Pass
- 0
152 170 Pass
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93.8 82.5 Pass
1
92.9 94.7 Pass
1
267 252 Pass
4
237 201 Pass
5
118 126 Pass
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5
160 158 Pass
(
138 118 Pass
0
119 112 Pass
- 0
161 170 Pass 6/15/2023 E13844 Filter Gamma pCi Ce-141 77.0 76.7 Pass Co-58 84.8 88.1 Pass Co-60 227 235 Pass Cr-51 184 187 Pass Cs-134 97.3 117 Pass Cs-137 139 147 Pass
(
129 110 Pass
0
111 104 Pass
- 0
171 159 Pass
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80.3 76.7 Pass
1
83.9 88.1 Pass
1
237 235 Pass
4
180 187 Pass
5
101 117 Pass
5
147 147 Pass
(
131 110 Pass
0
113 104 Pass
- 0
167 159 Pass
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Table 12: Cross Check Intercomparison Results Reference Date Standard Media Type Analysis Type Units Nuclide Reported Value Assigned Value NRC Resolution Test Pass / Fail
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5
201 185 Pass
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260 237 Pass
1,.
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0.221 0.202 Pass
5
0.326 0.315 Pass
1,.
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5
0.213 0.202 Pass
5
0.268 0.315 Pass
,.6(4
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1188 1350 Pass
5
1010 932 Pass
1
113 95.5 Pass
- 0
175 161 Pass
"$6(4
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5
43.3 41.2 Pass
5
215 199 Pass
1
48.1 47.8 Pass
- 0
62.1 57.0 Pass
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28.9 29.7 Pass
"$6(4
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28.3 29.7 Pass
,.6(4
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161 189 Pass
5
156 160 Pass
(
119 117 Pass
4
176 201 Pass
0
138 130 Pass
(
163 142 Pass
1
123 123 Pass
- 0
163 168 Pass
Annual Radiological Environmental Operating Report YEAR: 2023 Page 64 of 88
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Table 12: Cross Check Intercomparison Results Reference Date Standard Media Type Analysis Type Units Nuclide Reported Value Assigned Value NRC Resolution Test Pass / Fail
,.6(4
$//$
2,
5
163 189 Pass
5
163 160 Pass
(
119 117 Pass
4
179 201 Pass
0
134 130 Pass
(
169 142 Pass
1
122 123 Pass
,.6(4
$//$
2,
- 0
174 168 Pass
"$6(4
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2,
5
229 189 Pass
$464,'*(
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72.9 79.9 Pass
$464,'*(
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72.1 79.9 Pass
$464,'*(
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73.3 79.9 Pass
,.-
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38.4 40.0 Pass
5
129 143 Pass
5
123 121 Pass
(
88.5 88.7 Pass
4
155 152 Pass
0
99.8 98.3 Pass
(
107 108 Pass
1
94.3 92.9 Pass
- 0
121 127 Pass
E13850 Milk Gamma pCi/L I-131 32.2 40.0 Pass
5
138 143 Pass
5
116 121 Pass
(
79.1 88.7 Pass
4
146 152 Pass
0
103 98.3 Pass
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Table 12: Cross Check Intercomparison Results Reference Date Standard Media Type Analysis Type Units Nuclide Reported Value Assigned Value NRC Resolution Test Pass / Fail
(
119 108 Pass
1
95.5 92.9 Pass
- 0
113 127 Pass 1 See Quality Assurance Program Discussion
Annual Radiological Environmental Operating Report YEAR: 2023 Page 66 of 88
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Table 12 Coninued.: Interlaboratory Split Sample Results Sample Type Location Sample Date Type of Analysis Result Units CGS Analysis w 2 Split Analysis w 2 Pass/Fail (Split)
Vegetation IB10 6/19/2023 Gamma pCi/kg
<MDA
<MDA Pass Vegetation 31G1 6/13/2023 Gamma pCi/kg
<MDA
<MDA Pass Fish(Mud Flapper)
Ginna-Control 7/11/2023 Gamma pCi/kg
<MDA
<MDA Pass Fish (Bowfin)
Ginna-Control 7/11/2023 Gamma pCi/kg
<MDA
<MDA Pass Fish (Carp)
Ginna-Control 7/11/2023 Gamma pCi/kg
<MDA
<MDA Pass Fish (Bottom Feeder)
PB-6 6/12/2023 Gamma pCi/kg
<MDA
<MDA Pass Bottom Sediment CC-WBS4 6/28/2023 Gamma pCi/kg
<MDA
<MDA Pass Bottom Sediment CC-WBS2 6/28/2023 Gamma pCi/kg
<MDA
<MDA Pass Oysters CC-IA3 8/23/2023 Gamma pCi/kg
<MDA
<MDA Pass Oysters CC-IA6 8/23/2023 Gamma pCi/kg
<MDA
<MDA Pass Bay Water CC-WA1 8/29/2023 Gamma pCi/L
<MDA
<MDA Pass Bay Water CC-WA2 8/29/2023 Gamma pCi/L
<MDA
<MDA Pass Filter Composite CC-A1 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-A2 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-A3 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-A4 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-A5 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-SFA1 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-SFA2 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-SFA3 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite CC-SFA4 10/2/2023 Gamma pCi/m3
<MDA
<MDA Pass
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Water Q9-1 2/2/2023 Gross Beta pCi/L 1.4 0.7
<1.96 Pass Water Q9-1 2/2/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 2/2/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 2/2/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 3/2/2023 Gross Beta pCi/L 1.7 0.7
<2.09 Pass Water Q9-1 3/2/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 3/2/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 3/2/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 3/30/2023 Gross Beta pCi/L 1.2 0.7
<2.03 Pass Water Q9-1 3/30/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 3/30/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 3/30/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 4/26/2023 Gross Beta pCi/L 1.1 0.6
<1.89 Pass Water Q9-1 4/26/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 4/26/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 4/26/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 6/1/2023 Gross Beta pCi/L 2.8 0.7 2.3 +/- 1.4 Pass Water Q9-1 6/1/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 6/1/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 6/1/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 6/29/2023 Gross Beta pCi/L 1.6 0.8
<2.39 Pass Water Q9-1 6/29/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 6/29/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 6/29/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 7/27/2023 Gross Beta pCi/L 2.0 0.7 2.9 +/- 1.6 Pass Water Q9-1 7/27/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 7/27/2023 Gamma pCi/L
<MDA
<MDA Pass
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Water Q9-1 7/27/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 8/31/2023 Gross Beta pCi/L 2.0 0.7 2.8 +/-1.5 Pass Water Q9-1 8/31/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 8/31/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 8/31/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 10/3/2023 Gross Beta pCi/L 2.1 0.8
<2.13 Pass Water Q9-1 10/3/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 10/3/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 10/3/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 11/2/2023 Gross Beta pCi/L 2.1 0.7 3.1 +/- 1.3 Pass Water Q9-1 11/2/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 11/2/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 11/2/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 12/9/2023 Gross Beta pCi/L 1.4 0.7
<2.05 Pass Water Q9-1 12/9/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 12/9/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 12/9/2023 Tritium pCi/L
<MDA
<MDA Pass Water Q9-1 12/28/2023 Gross Beta pCi/L 1.6 0.8 2.2 +/- 1.5 Pass Water Q9-1 12/28/2023 LLI pCi/L
<MDA
<MDA Pass Water Q9-1 12/28/2023 Gamma pCi/L
<MDA
<MDA Pass Water Q9-1 12/28/2023 Tritium pCi/L
<MDA
<MDA Pass Milk-G2-1 1/11/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 1/11/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 2/15/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 2/15/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 3/8/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 3/8/2023 LLI pCi/L
<MDA
<MDA Pass
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Milk-G2-1 3/22/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 3/22/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 4/6/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 4/6/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 4/20/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 4/20/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 5/3/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 5/3/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 5/17/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 5/17/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 5/31/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 5/31/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 6/14/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 6/14/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 6/28/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 6/28/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 7/12/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 7/12/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 7/26/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 7/26/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 8/9/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 8/9/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 8/23/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 8/23/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 9/6/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 9/6/2023 LLI pCi/L
<MDA
<MDA Pass
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Milk-G2-1 9/20/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 9/20/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 10/4/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 10/4/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 10/18/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 10/18/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 11/1/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 11/1/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 11/15/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 11/15/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 11/29/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 11/29/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 12/14/2023 Gamma pCi/L
<MDA
<MDA Pass Milk-G2-1 12/14/2023 LLI pCi/L
<MDA
<MDA Pass Milk-G2-1 3/22/2023 Strontium 89 pCi/L
<MDA
<MDA Pass Milk-G2-1 3/22/2023 Strontium 90 pCi/L
<MDA
<MDA Pass Milk-G2-1 6/28/2023 Strontium 89 pCi/L
<MDA
<MDA Pass Milk-G2-1 6/28/2023 Strontium 90 pCi/L
<MDA
<MDA Pass Milk-G2-1 9/21/2023 Strontium 89 pCi/L
<MDA
<MDA Pass Milk-G2-1 9/21/2023 Strontium 90 pCi/L
<MDA
<MDA Pass Filter Composite E1-2 3/30/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite E1-2 6/29/2023 Gamma pCi/m3
<MDA
<MDA Pass
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Filter Composite E1-2 9/28/2023 Gamma pCi/m3
<MDA
<MDA Pass Filter Composite E1-2 12/28/2023 Gamma pCi/m3
<MDA
<MDA Pass Vegetation H1-2 6/14/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 7/12/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 8/16/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 9/20/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 6/14/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 7/12/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 8/16/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation H1-2 9/20/2023 Gamma pCi/Kg
<MDA
<MDA Pass Vegetation B10-2 8/16/2023 Gamma pCi/Kg
<MDA
<MDA Pass Fish INDP 10/4/2023 Gamma pCi/Kg
<MDA
<MDA Pass Fish INDP 10/4/2023 Strontium 90 pCi/Kg
<MDA
<MDA Pass Air Particulate Beta Split Sample Comparison Filter E1-2 /
E1-2Q Sample Date Beta 10-2 pCi/m3 E1-2
+/-2 E1-2Q
+/-2 Filter E1-2 /
E1-2Q 1/4/2023 Beta 10-2 pCi/m3 3.3 0.3 2.1 0.5 Filter E1-2 /
E1-2Q 1/11/2023 Beta 10-2 pCi/m3 2.4 0.2 1.7 0.4 Filter E1-2 /
E1-2Q 1/18/2023 Beta 10-2 pCi/m3 2.1 0.2 1.5 0.4 Filter E1-2 /
E1-2Q 1/26/2023 Beta 10-2 pCi/m3 1.6 0.2 1.0 0.3 Filter E1-2 /
E1-2Q 2/2/2023 Beta 10-2 pCi/m3 2.5 0.2 1.9 0.4 Filter E1-2 /
E1-2Q 2/8/2023 Beta 10-2 pCi/m3 2.8 0.3 2.1 0.5 Filter E1-2 /
E1-2Q 2/15/2023 Beta 10-2 pCi/m3 2.8 0.2 2.1 0.4 Filter E1-2 /
E1-2Q 2/23/2023 Beta 10-2 pCi/m3 2.3 0.2 1.7 0.4 Filter E1-2 /
E1-2Q 3/2/2023 Beta 10-2 pCi/m3 1.8 0.2 1.3 0.4
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Filter E1-2 /
E1-2Q 3/9/2023 Beta 10-2 pCi/m3 1.7 0.2 1.2 0.4 Filter E1-2 /
E1-2Q 3/16/2023 Beta 10-2 pCi/m3 1.1 0.2 1.1 0.4 Filter E1-2 /
E1-2Q 3/23/2023 Beta 10-2 pCi/m3 2.4 0.2 1.7 0.4 Filter E1-2 /
E1-2Q 3/30/2023 Beta 10-2 pCi/m3 2.5 0.2 1.6 0.4 Filter E1-2 /
E1-2Q 4/6/2023 Beta 10-2 pCi/m3 2.3 0.2 1.4 0.4 Filter E1-2 /
E1-2Q 4/13/2023 Beta 10-2 pCi/m3 2.8 0.3 2.2 0.4 Filter E1-2 /
E1-2Q 4/20/2023 Beta 10-2 pCi/m3 2.0 0.2 2.0 0.4 Filter E1-2 /
E1-2Q 4/26/2023 Beta 10-2 pCi/m3 1.9 0.2 1.6 0.5 Filter E1-2 /
E1-2Q 5/4/2023 Beta 10-2 pCi/m3 0.9 0.2 0.6 0.3 Filter E1-2 /
E1-2Q 5/11/2023 Beta 10-2 pCi/m3 1.4 0.2 1.0 0.3 Filter E1-2 /
E1-2Q 5/18/2023 Beta 10-2 pCi/m3 2.7 0.2 1.8 0.5 Filter E1-2 /
E1-2Q 5/25/2023 Beta 10-2 pCi/m3 1.7 0.2 1.2 0.4 Filter E1-2 /
E1-2Q 6/1/2023 Beta 10-2 pCi/m3 1.6 0.2 1.5 0.4 Filter E1-2 /
E1-2Q 6/8/2023 Beta 10-2 pCi/m3 2.2 0.2 1.3 0.4 Filter E1-2 /
E1-2Q 6/15/2023 Beta 10-2 pCi/m3 1.6 0.2 1.1 0.4 Filter E1-2 /
E1-2Q 6/22/2023 Beta 10-2 pCi/m3 1.6 0.2 1.5 0.4 Filter E1-2 /
E1-2Q 6/29/2023 Beta 10-2 pCi/m3 1.4 0.2 0.9 0.3 Filter E1-2 /
E1-2Q 7/5/2023 Beta 10-2 pCi/m3 2.5 0.3 1.7 0.5 Filter E1-2 /
E1-2Q 7/13/2023 Beta 10-2 pCi/m3 3.3 0.2 2.1 0.4 Filter E1-2 /
E1-2Q 7/20/2023 Beta 10-2 pCi/m3 2.8 0.3 2.3 0.5 Filter E1-2 /
E1-2Q 7/27/2023 Beta 10-2 pCi/m3 2.4 0.2 1.3 0.4 Filter E1-2 /
E1-2Q 8/3/2023 Beta 10-2 pCi/m3 2.6 0.2 1.5 0.4
Annual Radiological Environmental Operating Report YEAR: 2023 Page 73 of 88
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Filter E1-2 /
E1-2Q 8/9/2023 Beta 10-2 pCi/m3 2.4 0.3 1.1 0.5 Filter E1-2 /
E1-2Q 8/17/2023 Beta 10-2 pCi/m3 2.4 0.2 1.6 0.4 Filter E1-2 /
E1-2Q 8/24/2023 Beta 10-2 pCi/m3 2.3 0.2 1.3 0.4 Filter E1-2 /
E1-2Q 8/31/2023 Beta 10-2 pCi/m3 2.3 0.2 1.6 0.4 Filter E1-2 /
E1-2Q 9/7/2023 Beta 10-2 pCi/m3 3.7 0.3 2.4 0.5 Filter E1-2 /
E1-2Q 9/14/2023 Beta 10-2 pCi/m3 2.9 0.2 2.2 0.5 Filter E1-2 /
E1-2Q 9/21/2023 Beta 10-2 pCi/m3 2.4 0.2 1.6 0.4 Filter E1-2 /
E1-2Q 9/28/2023 Beta 10-2 pCi/m3 1.5 0.2 1.5 0.4 Filter E1-2 /
E1-2Q 10/4/2023 Beta 10-2 pCi/m3 2.4 0.3 2.1 0.5 Filter E1-2 /
E1-2Q 10/12/2023 Beta 10-2 pCi/m3 3.0 0.2 1.9 0.4 Filter E1-2 /
E1-2Q 10/18/2023 Beta 10-2 pCi/m3 1.4 0.2 0.9 0.5 Filter E1-2 /
E1-2Q 10/25/2023 Beta 10-2 pCi/m3 2.1 0.2 1.5 0.4 Filter E1-2 /
E1-2Q 11/2/2023 Beta 10-2 pCi/m3 2.8 0.2 1.9 0.4 Filter E1-2 /
E1-2Q 11/9/2023 Beta 10-2 pCi/m3 4.2 0.3 3.3 0.5 Filter E1-2 /
E1-2Q 11/16/2023 Beta 10-2 pCi/m3 3.0 0.3 2.0 0.5 Filter E1-2 /
E1-2Q 11/22/2023 Beta 10-2 pCi/m3 3.1 0.3 1.9 0.5 Filter E1-2 /
E1-2Q 11/29/2023 Beta 10-2 pCi/m3 2.3 0.2 1.4 0.4 Filter E1-2 /
E1-2Q 12/7/2023 Beta 10-2 pCi/m3 3.8 0.3 2.3 0.4 Filter E1-2 /
E1-2Q 12/14/2023 Beta 10-2 pCi/m3 2.9 0.3 2.0 0.4 Filter E1-2 /
E1-2Q 12/21/2023 Beta 10-2 pCi/m3 3.1 0.3 2.1 0.4 Filter E1-2 /
E1-2Q 12/28/2023 Beta 10-2 pCi/m3 2.2 0.2 1.5 0.4
Annual Radiological Environmental Operating Report YEAR: 2023 Page 74 of 88
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Air Iodine Split Sample Comparison Charcoal E1-2 /
E1-2Q Sample Date I-131 pCi/m3 E1-2 E1-2Q Charcoal E1-2 /
E1-2Q 01/04/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 1/11/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 1/18/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 1/26/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 2/2/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 2/8/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 2/15/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 2/23/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 3/2/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 3/9/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 3/16/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 3/23/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 3/30/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 4/6/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 4/13/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 4/20/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 4/26/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 5/4/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 5/11/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 5/18/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 5/25/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 6/1/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 6/8/2023 I-131 pCi/m3
<MDA
<MDA
Annual Radiological Environmental Operating Report YEAR: 2023 Page 75 of 88
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Charcoal E1-2 /
E1-2Q 6/15/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 6/22/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 6/29/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 7/5/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 7/13/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 7/20/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 7/27/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 8/3/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 8/9/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 8/17/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 8/24/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 8/31/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 9/7/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 9/14/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 9/21/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 9/28/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 10/4/2023 I-131 pCi/m3
<MDA
<MDA Charcoal E1-2 /
E1-2Q 10/12/2023 I-131 pCi/m3
<MDA
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E1-2Q 11/2/2023 I-131 pCi/m3
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, Environmental Direct Radiation Dosimetry Results Monitoring Location Quarterly
- Baseline, BQ (mrem)
BQ +
MDDQ (mrem)
Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual
- Baseline, BA (mrem)
BA +
MDDA (mrem)
Annual Monitoring Data, MA (mrem)
Annual Facility Dose, FA=MA-BA (mrem, or ND if FA MDDA)
(mrem)
(mrem, or ND if FQ MDDQ) 1 2
3 4
1 2
3 4
TM-ID-A1-4 16.8 23.4 14.8 16.6 13.5 15.1 ND ND ND ND 67.1 82.3 60 ND TM-ID-A3-1 16.5 23.1 14.7 14.9 15.2 15.2 ND ND ND ND 66 81.2 60 ND TM-ID-A5-1 20.8 27.4 17.6 17.6 20.4 18.3 ND ND ND ND 83.2 98.4 73.9 ND TM-ID-A9-3 17.6 24.2 16.1 15.4 16.2 15.8 ND ND ND ND 70.6 85.8 63.5 ND TM-ID-B10-1 19.3 25.9 17.3 16.3 17.3 18.6 ND ND ND ND 77.4 92.6 69.5 ND TM-ID-B1-1 17.7 24.3 14.9 14.1 14.4 17.1 ND ND ND ND 70.8 86.0 60.5 ND TM-ID-B1-2 17.2 23.8 15.2 13 15.8 16.7 ND ND ND ND 68.7 83.9 60.7 ND TM-ID-B2-1 17.2 23.8 15.4 15.2 16.8 15.8 ND ND ND ND 69 84.2 63.2 ND TM-ID-B5-1 20 26.6 18.1 16.8 19.5 18.9 ND ND ND ND 79.8 95.0 73.3 ND TM-ID-C1-1 20.2 26.8 17.3 17.8 17.9 19.2 ND ND ND ND 80.8 96.0 72.2 ND TM-ID-C1-2 17 23.6 14.2 13.1 15.9 13.2 ND ND ND ND 67.9 83.1 56.4 ND TM-ID-C2-1 19.2 25.8 16.1 17.7 19.1 16.3 ND ND ND ND 76.9 92.1 69.2 ND TM-ID-C5-1 20.7 27.3 18 18.7 16.8 20.6 ND ND ND ND 82.7 97.9 74.1 ND TM-ID-C8-1 20.9 27.5 18.1 20.3 19.9 19.3 ND ND ND ND 83.4 98.6 77.6 ND TM-ID-D1-1 17.9 24.5 No data 15.7 13.4 17.9 No data ND ND ND 71.4 86.6 No data No data TM-ID-D1-2 18.8 25.4 15.5 18.7 16.1 17 ND ND ND ND 75.2 90.4 67.3 ND TM-ID-D15-1 19.8 26.4 17.4 18.8 17.2 19.7 ND ND ND ND 79.1 94.3 73.1 ND TM-ID-D2-2 23 29.6 20.1 21.8 21.4 19.9 ND ND ND ND 91.8 107.0 83.2 ND TM-ID-D6-1 22.3 28.9 19.5 21.7 21.7 22 ND ND ND ND 89.4 104.6 84.9 ND TM-ID-E1-2 17.8 24.4 15.3 19.2 17.5 16.9 ND ND ND ND 71.3 86.5 68.9 ND TM-ID-E1-4 18.1 24.7 15.2 16.8 17.2 17.4 ND ND ND ND 72.3 87.5 66.6 ND TM-ID-E2-3 21.5 28.1 18.3 21.1 21.7 20 ND ND ND ND 86 101.2 81.1 ND TM-ID-E5-1 21.9 28.5 19 19.3 21.4 21.6 ND ND ND ND 87.7 102.9 81.3 ND TM-ID-E7-1 20.3 26.9 17.3 18.2 18.6 17.1 ND ND ND ND 81.2 96.4 71.2 ND
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Monitoring Location Quarterly
- Baseline, BQ (mrem)
BQ +
MDDQ (mrem)
Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual
- Baseline, BA (mrem)
BA +
MDDA (mrem)
Annual Monitoring Data, MA (mrem)
Annual Facility Dose, FA=MA-BA (mrem, or ND if FA MDDA)
(mrem)
(mrem, or ND if FQ MDDQ) 1 2
3 4
1 2
3 4
TM-ID-F10-1 23.7 30.3 21.8 24.3 23 23.2 ND ND ND ND 94.6 109.8 92.3 ND TM-ID-F1-1 19.4 26.0 15.6 17.8 18.7 17.7 ND ND ND ND 77.5 92.7 69.8 ND TM-ID-F1-2 20.4 27.0 15.8 19.2 17.2 16.1 ND ND ND ND 81.5 96.7 68.3 ND TM-ID-F1-4 19 25.6 14.6 16.7 16.9 18.4 ND ND ND ND 75.8 91.0 66.6 ND TM-ID-F2-1 21.9 28.5 18.1 18.2 19.7 20.2 ND ND ND ND 87.6 102.8 76.2 ND TM-ID-F25-1 20.9 27.5 18.3 20.8 18.9 20.3 ND ND ND ND 83.6 98.8 78.3 ND TM-ID-F5-1 22.9 29.5 19.7 20.5 22.1 20.9 ND ND ND ND 91.5 106.7 83.2 ND TM-ID-G10-1 27.8 34.4 24.2 27.5 29 26.4 ND ND ND ND 111 126.2 107 ND TM-ID-G1-2 20.1 26.7 17.8 18.7 19.4 19.4 ND ND ND ND 80.4 95.6 75.3 ND TM-ID-G1-3 18 24.6 15.4 16.8 15.7 16.8 ND ND ND ND 71.9 87.1 64.7 ND TM-ID-G1-5 17.7 24.3 16.7 19.2 18.3 17.5 ND ND ND ND 70.6 85.8 71.7 ND TM-ID-G15-1 24.1 30.7 17 15.9 18.6 19.4 ND ND ND ND 96.3 111.5 70.9 ND TM-ID-G1-6 18.8 25.4 16.9 15.6 17.7 18 ND ND ND ND 75.3 90.5 68.2 ND TM-ID-G2-4 23.9 30.5 20 21.3 21.7 22.5 ND ND ND ND 95.6 110.8 85.5 ND TM-ID-G5-1 19.7 26.3 17.2 15.3 19.9 17.1 ND ND ND ND 78.9 94.1 69.5 ND TM-ID-H1-1 19.3 25.9 25 27.7 26.6 26.4 ND 8.38 7.32 7.11 77 92.2 106 28.7 TM-ID-H15-1 19.8 26.4 17.4 18.4 17.4 17.7 ND ND ND ND 79.2 94.4 70.9 ND TM-ID-H3-1 16.3 22.9 13.9 13.1 15.5 14.7 ND ND ND ND 65.3 80.5 57.2 ND TM-ID-H5-1 15.9 22.5 13.7 11.9 15.2 14.2 ND ND ND ND 63.7 78.9 55 ND TM-ID-H8-1 29.7 36.3 27.7 26.9 29.1 28.2 ND ND ND ND 119 134.2 112 ND TM-ID-J1-1 17.3 23.9 13.4 12.3 15.9 16.1 ND ND ND ND 69.3 84.5 57.7 ND TM-ID-J1-3 15.3 21.9 28.4 27.1 28.7 27.1 13.1 11.8 13.4 11.8 61.1 76.3 111 50.2 TM-ID-J15-1 23.2 29.8 20.2 22.9 20.1 ND ND ND ND 22.4 92.9 108.1 85.6 ND TM-ID-J3-1 19.5 26.1 16.5 17.4 17 ND ND ND ND 17 77.9 93.1 67.9 ND TM-ID-J5-1 21.4 28.0 19.8 24 20.4 ND ND ND ND 18.4 85.7 100.9 82.6 ND
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Monitoring Location Quarterly
- Baseline, BQ (mrem)
BQ +
MDDQ (mrem)
Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual
- Baseline, BA (mrem)
BA +
MDDA (mrem)
Annual Monitoring Data, MA (mrem)
Annual Facility Dose, FA=MA-BA (mrem, or ND if FA MDDA)
(mrem)
(mrem, or ND if FQ MDDQ) 1 2
3 4
1 2
3 4
TM-ID-J7-1 22.8 29.4 21 21 21.6 21.3 ND ND ND ND 91.1 106.3 84.9 ND TM-ID-K1-4 17.4 24.0 15.9 16.1 17.1 16.9 ND ND ND ND 69.6 84.8 66 ND TM-ID-K15-1 19.1 25.7 16.5 18.3 18.3 17.4 ND ND ND ND 76.5 91.7 70.5 ND TM-ID-K2-1 21.5 28.1 20.2 21.1 19.9 19.7 ND ND ND ND 86.2 101.4 80.9 ND TM-ID-K3-1 17.4 24.0 14.3 13.9 18.4 17 ND ND ND ND 69.7 84.9 63.6 ND TM-ID-K5-1 21.2 27.8 18.9 20.5 24.5 19.3 ND ND ND ND 84.6 99.8 83.2 ND TM-ID-K8-1 20.5 27.1 17.7 15.6 17 20.8 ND ND ND ND 81.8 97.0 71.1 ND TM-ID-L1-1 18.7 25.3 15.6 18 18.5 18.5 ND ND ND ND 74.7 89.9 70.6 ND TM-ID-L1-2 17.6 24.2 13.3 13.8 16.2 14.1 ND ND ND ND 70.3 85.5 57.4 ND TM-ID-L15-1 19.6 26.2 17.9 18 20.8 20.3 ND ND ND ND 78.5 93.7 77 ND TM-ID-L2-1 19.4 26.0 16.5 18.7 18.2 18.7 ND ND ND ND 77.4 92.6 72.1 ND TM-ID-L5-1 17.6 24.2 16.3 16.2 17.2 15.7 ND ND ND ND 70.5 85.7 65.4 ND TM-ID-L8-1 19.6 26.2 17.6 19.6 18.2 16.3 ND ND ND ND 78.4 93.6 71.7 ND TM-ID-M1-1 17 23.6 17 15.3 17.2 15.8 ND ND ND ND 67.9 83.1 65.3 ND TM-ID-M1-2 19 25.6 16.1 19.3 18.2 17.4 ND ND ND ND 76.1 91.3 71 ND TM-ID-M2-1 17.4 24.0 15.2 16 17.3 16.9 ND ND ND ND 69.6 84.8 65.4 ND TM-ID-M5-1 19.2 25.8 16.7 16.8 19.5 17.9 ND ND ND ND 76.9 92.1 70.9 ND TM-ID-M9-1 23.5 30.1 21 20.5 22.4 21.2 ND ND ND ND 93.8 109.0 85.1 ND TM-ID-N1-1 18.5 25.1 17.6 14.4 18.4 18.1 ND ND ND ND 73.9 89.1 68.5 ND TM-ID-N1-3 18.8 25.4 17.3 18.5 17.1 17.7 ND ND ND ND 75.2 90.4 70.6 ND TM-ID-N15-2 21.6 28.2 19.4 20.1 22.6 19.7 ND ND ND ND 86.4 101.6 81.8 ND TM-ID-N2-1 20 26.6 19.5 16.7 19.2 19.4 ND ND ND ND 80.1 95.3 74.8 ND TM-ID-N5-1 16.9 23.5 15.8 13.4 16.7 16.4 ND ND ND ND 67.7 82.9 62.3 ND TM-ID-N8-1 20.3 26.9 19.5 17.4 20 19.8 ND ND ND ND 81.2 96.4 76.7 ND TM-ID-P1-1 18.3 24.9 15 14.3 17.2 17 ND ND ND ND 73 88.2 63.5 ND
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Monitoring Location Quarterly
- Baseline, BQ (mrem)
BQ +
MDDQ (mrem)
Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual
- Baseline, BA (mrem)
BA +
MDDA (mrem)
Annual Monitoring Data, MA (mrem)
Annual Facility Dose, FA=MA-BA (mrem, or ND if FA MDDA)
(mrem)
(mrem, or ND if FQ MDDQ) 1 2
3 4
1 2
3 4
TM-ID-P1-2 18.4 25.0 20.1 19.1 20.6 22.6 ND ND ND ND 73.7 88.9 82.4 ND TM-ID-P2-1 22.3 28.9 21 No data 22.4 21.7 ND No data ND ND 89.2 104.4 No data No data TM-ID-P5-1 19.4 26.0 17.3 20.7 17.3 19.8 ND ND ND ND 77.6 92.8 75.1 ND TM-ID-P8-1 17.1 23.7 15.8 15.3 15.9 14.5 ND ND ND ND 68.5 83.7 61.5 ND TM-ID-Q1-1 18.7 25.3 15.6 16 16.9 17.5 ND ND ND ND 74.7 89.9 66 ND TM-ID-Q1-2 15.8 22.4 14 12.8 16.7 16.9 ND ND ND ND 63.2 78.4 60.4 ND TM-ID-Q15-1 21.5 28.1 19.9 19.8 21.3 19.8 ND ND ND ND 86.2 101.4 80.8 ND TM-ID-Q2-1 17.7 24.3 14.2 15.9 16.5 15.2 ND ND ND ND 70.7 85.9 61.8 ND TM-ID-Q5-1 18.1 24.7 16.9 16 18.1 16 ND ND ND ND 72.6 87.8 67 ND TM-ID-Q9-1 18.9 25.5 17 18 17.3 17.2 ND ND ND ND 75.4 90.6 69.5 ND TM-ID-R1-1 16.8 23.4 15.3 14.5 16.5 17.6 ND ND ND ND 67.1 82.3 63.9 ND TM-ID-R1-2 16.9 23.5 13.1 13.3 14.1 14 ND ND ND ND 67.8 83.0 54.5 ND TM-ID-R15-1 19 25.6 15.6 17.9 17.9 16.2 ND ND ND ND 76 91.2 67.6 ND TM-ID-R3-1 21.9 28.5 19.9 17.2 22.9 20.5 ND ND ND ND 87.6 102.8 80.5 ND TM-ID-R5-1 21.1 27.7 19.4 18.5 21.5 20.4 ND ND ND ND 84.5 99.7 79.8 ND TM-ID-R9-1 21.2 27.8 19.7 18.2 20.3 19.4 ND ND ND ND 84.8 100.0 77.6 ND MDDQ = Quarterly Minimum Differential Dose = 6.63 mrem MDDA = Annual Minimum Differential Dose = 15.15 mrem ND = Not Detected, where MQ (BQ+MDDQ) or MA (BA+MDDA)
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, Annual Radiological Groundwater Protection Program 1.0 Summary and Conclusions In 2006, Constellation (formerly Exelon) instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station.
This report covers groundwater, surface water, storm water, and precipitation samples collected from the environment, both on and off station property in 2023.
Overall, groundwater tritium concentrations at the Station were less than 2,000 pCi/L.
Hard-to-detects (Fe-55 and Ni-63) and Sr-89 and Sr-90 were not detected at concentrations greater than their respective LLDs in any of the groundwater samples collected in 2023.
Tritium present in precipitation recapture can potentially affect groundwater quality in the area of the turbine and reactor buildings.
There does not appear to be an active source of tritium to groundwater.
The wells sampled effectively monitored groundwater conditions at the facility.
In assessing all the data gathered for this report, it was concluded that the operation of Three Mile Island Nuclear Station had no adverse radiological impact on the environment.
1.1 Current RGPP Summary Three Mile Island Generating Station has a total of 49 wells (one Background well, seven Long-Term Shutdown wells, twelve Mid-Field wells, sixteen Perimeter wells, and thirteen Source wells) that are sampled as part of the Station RGPP (EN-TM-408-4160 Revision 4). Figure 1a shows surface water and overburden RGPP monitoring locations; Figure 1b shows upper bedrock aquifer RGPP monitoring locations; and Figure 1c shows lower bedrock aquifer RGPP monitoring locations.
RGPP sampling at the Station is performed by Constellation Generation Service, under contract to Constellation. Laboratory testing is performed by Teledyne Brown Engineering. The laboratory data, field data, and depth to water readings are uploaded to the RACER website, which is a data repository for the RGPP sampling rounds.
Gross-Alpha Alert Level Gross-alpha (suspended) was detected in the sample collected from MS-20 at 3.61 pCi/L. The sample was re-analyzed with a reported detection of 3.32 pCi/L. Both the original result and re-analysis result exceeded the Alert Level of 1.92 pCi/L. However, the sample was sediment laden. The Station re-sampled MW-20 during the 3rd quarter 2022 and the result for gross-alpha (suspended) was less than the laboratory detection limit.
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All Long-Term Shutdown and Source designated wells were most recently sampled in 2022 and will have gross-alpha analysis performed again in 2024 in accordance with a two-year frequency required.
Gamma-Radionuclides Gamma-radionuclide analysis has been performed on RGPP samples (quarterly to annually) at Three Mile Island Generating Station since 2006. This extensive sampling and analysis produced over 15,700 data records for the Station. Gamma-radionuclides have not been detected at concentrations greater than their respective LLDs, in RGPP samples submitted to the vendor laboratory since 2006. Therefore, in the 2020 RGPP, gamma-radionuclide analysis frequency was reduced from annual to every two years.
Gamma-radionuclide analysis was most recently performed during the 2nd quarter 2022 RGPP sampling round. Gamma radionuclides were not detected at concentrations exceeding their respective LLDs in 2022.
All wells will be analyzed for gamma-radionuclides in 2024.
Select Transuranics Select transuranics analysis is procedurally required annually for RGPP sample locations that were identified as Elevated designated wells in the historic EN-TM-408-4160 revisions and continued additional evaluation is warranted. Note that Three Mile Island Generating Station did not have Elevated designated RGPP sample locations in previous revisions of the RGPP. Additionally, as part of the current EN-TM-408-4160 (Revision 4), select transuranics analysis is also warranted if a gross alpha concentration exceeds the Alert Level in a particular well. Samples collected from the RGPP well network were not analyzed for select transuranics in 2023.
Hard-to-Detects (Fe-55 and Ni-63)
Hard-to-detect analysis (Fe-55 and Ni-63) is procedurally required annually for RGPP sample locations that were identified as Elevated designated wells in the historic EN-TMI-408-4160 revisions and continued additional evaluation is warranted as well as Long-Term Shutdown designated wells.
Note that Three Mile Island Generating Station did not have Elevated designated RGPP sample locations in previous revisions of the RGPP.
Additionally, as part of the current EN-TM-408-4160 (Revision 4), hard-to-detect analysis is warranted on samples collected from Source designated wells once every 5 years, starting in 2021.
In 2021, samples collected from the Long-Term Shutdown and Source designated wells were analyzed for hard-to-detects (Fe-55 and Ni-63). Hard to detects (Fe-55 and Ni-63) were not detected at concentrations greater than their respective LLDs in the samples collected in 2021. In 2023, samples collected from the Long-Term Shutdown designated wells were analyzed for hard-to-detects (Fe-55 and Ni-63). Hard to detects (Fe-55 and Ni-63) were not detected at concentrations greater than their respective LLDs in the samples collected in 2023. Long-Term Shutdown designated wells will be analyzed for hard to detects (Fe-55 and Ni-63) in 2024 and Source designated well samples will be analyzed for hard-to-detects (Fe-55 and Ni-63) again in 2026.
Sr-89 and Sr-90 Sr-89 and Sr-90 have been an annual procedurally required analysis on Detection, Long-Term Shutdown, and Elevated designated wells since sample point designations became part of the RGPP in 2010. EN-TM-408-4160 (Revision 4) states that Sr-89 and 90 analyses should be performed annually for Source and Long-Term Shutdown designated sample locations. If a positive result is reported, samples collected from wells with the Sr-89 and Sr-90 detections, will be analyzed quarterly to evaluate the activity in the area of the well.
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In 2023, samples collected from the Long-Term Shutdown and Source designated sample locations were analyzed for Sr-89 and Sr-90. Sr-89 and Sr-90 were not detected in the samples collected in 2023.
Precipitation Recapture Three Mile Island Generating Station (TMI) is a Pressurized Water Reactor (PWR) generating station.
However, in 2019, the Station ceased production of electricity and started decommissioning activities. In 2020, the RGPP was modified to increase the minimum number of samples to eight and to focus sample locations in areas close to atmospheric release points or areas that could receive atmospheric recapture.
The 2020 RGPP modification states that a minimum of eight samples should be collected from within the protected area in a manner that surrounds the Turbine Building and Reactor Building as well as ancillary structures that could vent tritiated vapor to the atmosphere.
The Station collected precipitation recapture samples quarterly in 2023. Tritium was only detected in the samples collected from TM-PR-MW-22S during the 3rd and 4th quarter precipitation sampling rounds in 2023. The 3rd quarter 2023 tritium concentration was 310 pCi/L and the 4th quarter 2023 tritium concentration was 1,860 pCi/L. A summary of 2023 precipitation recapture results is presented in Table 3.
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1.2 Summary of 2023 RGPP Sampling Rounds February 2023 RGPP Sampling Round Activities (1st Quarter 2023)
Data Summary Groundwater samples were collected from seven Long Term Shutdown and thirteen Source designated wells during the 1st quarter 2023 sampling round. All samples were analyzed for tritium. Tritium was detected in groundwater samples collected from five overburden aquifer wells with a maximum concentration of 301 pCi/L (MW-TM-22S). Tritium was detected in groundwater samples collected from five upper bedrock aquifer wells with a maximum concentration of 392 pCi/L (MS-22). Tritium was not detected in groundwater samples collected from the lower bedrock aquifer wells.
Based on the 1st quarter 2023 data, AMO concluded that there does not appear to be an active source of tritium to groundwater at the Station.
Water Elevations All sample locations had depth to water measurements collected during the 1st quarter 2023 sampling round. The 1st quarter 2023 groundwater elevation data was compared to the 1st quarter 2022 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Thus, the wells sampled effectively monitored groundwater conditions at the facility.
May/June 2023 RGPP Sampling Round Activities (2nd Quarter 2023)
Groundwater samples were collected from one Background well, six Long-Term Shutdown wells, twelve Mid-Field wells, fifteen Perimeter wells, and thirteen Source wells during the 2nd quarter 2023 sampling round. A sample could not be collected from Long Term Shutdown well OS-16 and Perimeter well MW-TMI-9S due to insufficient water in the wells. All samples were analyzed for tritium. Long-Term Shutdown and Source designated wells were also analyzed for Sr-89 and Sr-90. Long-Term Shutdown designated wells were also analyzed for hard-to-detects (Fe-55 and Ni-63).
Tritium was detected at concentrations greater than 200 pCi/L in groundwater samples collected from three overburden aquifer wells with a maximum concentration of 236 pCi/L (MW-TMI-10S and MW-TMI-22S).
Tritium was detected at concentrations greater than 200 pCi/L in groundwater samples collected from eleven upper bedrock aquifer wells with a maximum concentration of 1,660 pCi/L (MW-TMI-22D). Tritium was detected in the groundwater sample collected from lower bedrock aquifer wells NW-A and NW-C at 231 pCi/L and 466 pCi/L, respectively.
Hard-to-detects (Fe-55 and Ni-63) and Sr-89/90 were not detected at concentrations greater than their respective LLDs in the samples collected in 2023.
Based on the 2nd quarter 2023 data, AMO concluded that there does not appear to be an active source of tritium to groundwater at the Station.
Water Elevations All groundwater sample locations had depth to water measurements collected during the 2nd quarter 2023 sampling round. The 2nd quarter 2023 groundwater elevation data was compared to the 2nd quarter 2022 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect
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on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Thus, the wells sampled effectively monitored groundwater conditions at the facility.
September 2023 RGPP Sampling Round Activities (3rd Quarter 2023)
Data Summary Groundwater samples were collected from seven Long-Term Shutdown wells and thirteen Source wells during the 3rd quarter 2023 sampling round. All samples were analyzed for tritium. Tritium was not detected at concentrations greater than 200 pCi/L in groundwater in samples collected from overburden aquifer and lower bedrock aquifer during the 3rd quarter 2023 RGPP sampling round. Tritium was detected in the sample collected from upper bedrock aquifer well MW-TMI-6I at 289 pCi/L.
Based on the 3rd quarter 2023 data, AMO concluded that there does not appear to be an active source of tritium to groundwater at the Station.
Water Elevations All groundwater sample locations had depth to water measurements collected during the 3rd quarter 2023 sampling round. The 3rd quarter 2023 groundwater elevation data was compared to the 3rd quarter 2022 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Thus, the wells sampled effectively monitored groundwater conditions at the facility.
December 2023 RGPP Sampling Round Activities (4th Quarter 2023)
Data Summary Groundwater samples were collected from seven Long Term Shutdown, twelve Midfield, and thirteen Source designated wells during the 4th quarter 2023 sampling round. All samples were analyzed for tritium.
Tritium was detected in the groundwater sample collected from overburden aquifer well MW-TMI-10S at 204 pCi/L. Tritium was detected in groundwater samples collected from six upper bedrock aquifer wells with a maximum concentration of 1,180 pCi/L (MW-TMI-21D). Tritium was detected in the groundwater samples collected from four lower bedrock aquifer wells with a maximum concentration of 549 pCi/L (NW-C).
Based on the 4th quarter 2023 data, AMO concluded that there does not appear to be an active source of tritium to groundwater at the Station.
Water Elevations All sample locations had depth to water measurements collected during the 4th quarter 2023 sampling round. Groundwater elevations and groundwater flow direction for the overburden aquifer are provided on Figure 2a; groundwater elevations and groundwater flow direction for the intermediate upper bedrock aquifer are provided on Figure 2b; and the groundwater elevations and groundwater flow direction for the deep upper bedrock aquifer are provided on Figure 2c.
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2024 RGPP Sample Locations The 2023 RGPP sample locations effectively monitored Systems, Structures, and Components of the Station. Therefore, RGPP sample locations identified in Attachment 1 of EN-TM-408-4160 (Revision 4) should continue to be sampled in accordance with Attachment 2 of EN-TM-408-4160 (Revision 4).
Summary of 2023 RGPP Conformance The Station conformed with its RGPP in 2023 with respect to sampling protocol with the exception of not analyzing the sample collected from OS-16 for hard-to-detects (Fe-55 and Ni-63) and Sr-89/90 in 2023.
Note that OS-16 was dry at the time the 2nd quarter 2023 RGPP sampling round was completed and all other wells were analyzed for radionuclides other than tritium.
Conclusions Based on the review of the data collected during the 2023 RGPP sampling rounds AMO concludes:
Overall, groundwater tritium concentrations at the Station were less than 2,000 pCi/L.
Hard-to-detects (Fe-55 and Ni-63) and Sr-89 and Sr-90 were not detected at concentrations greater than their respective LLDs in any of the groundwater samples collected in 2023.
Tritium present in precipitation recapture can potentially affect groundwater quality in the area of the turbine and reactor buildings.
There does not appear to be an active source of tritium to groundwater.
The wells sampled effectively monitored groundwater conditions at the facility.
Annual Radiological Environmental Operating Report YEAR: 2023 Page 87 of 88
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Summary of 2023 Precipitation Results Date Directional Sector Tritium Result Qual TM-PR-EDCB 3/28/2023 SE 180 U
TM-PR-EDCB 6/29/2023 SE 198 U
TM-PR-EDCB 9/13/2023 SE 190 U
TM-PR-EDCB 12/5/2023 SE 185 U
TM-PR-ESE 2/21/2023 ESE 187 U
TM-PR-ESE 5/23/2023 ESE 199 U
TM-PR-ESE 8/31/2023 ESE 197 U
TM-PR-ESE 11/16/2023 ESE 191 U
TM-PR-MS-1 2/21/2023 NNE 192 U
TM-PR-MS-1 5/23/2023 NNE 199 U
TM-PR-MS-1 8/31/2023 NNE 194 U
TM-PR-MS-1 11/16/2023 NNE 193 U
TM-PR-MS-2 2/21/2023 SE 188 U
TM-PR-MS-2 5/23/2023 SE 196 U
TM-PR-MS-2 8/31/2023 SE 194 U
TM-PR-MS-2 11/16/2023 SE 195 U
TM-PR-MS-4 2/21/2023 SSE 189 U
TM-PR-MS-4 5/23/2023 SSE 195 U
TM-PR-MS-4 8/31/2023 SSE 191 U
TM-PR-MS-4 11/16/2023 SSE 191 U
TM-PR-MS-8 2/21/2023 SW 179 U
TM-PR-MS-8 5/23/2023 SW 196 U
TM-PR-MS-8 8/31/2023 SW 193 U
TM-PR-MS-8 11/16/2023 SW 188 U
TM-PR-MW-22S 2/21/2023 NNW 196 U
TM-PR-MW-22S 5/23/2023 NNW 199 U
TM-PR-MW-22S 8/31/2023 NNW 310
+
TM-PR-MW-22S 11/16/2023 NNW 1860
+
TM-PR-PW-1 5/23/2023 NE 197 U
TM-PR-RW-1 2/21/2023 NE 181 U
TM-PR-RW-1 8/31/2023 NE 195 U
TM-PR-RW-1 11/16/2023 NE 187 U
Explanation:
+ - Result detected at a concentration greater than the laboratory detection limit.
U - Result not detected at a concentration greater than the laboratory detection limit.
- All results presented in pico-curies per liter (pCi/L)
Annual Radiological Environmental Operating Report YEAR: 2023 Page 88 of 88
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