Text

2001 Radiological Environmental Monitoring Report
	ML021150208
Person / Time
Site:	Crane
Issue date:	04/17/2002
From:	George Gellrich; AmerGen Energy Co
To:	; Document Control Desk, NRC/FSME
References
	+sunsi/sispmjr=200604, -nr, -RFPFR, 5928-02-20107
	Download: ML021150208 (110)
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SAmerGen,...

AmerGen Energy Company, LLC Telephone: 717-944-7621 An Exelon/British Energy Company Three Mile Island Unit i Route 441 South, P.O. Box 48o Middletown, PA 17057 April 17, 2002 5928-02-20107 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 (TMI-1 & TMI-2)

OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR-73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT In accordance with TMI-1 Technical Specification 6.9.3.1 and TMI-2 Technical Specification 6.8.1.1, enclosed is the 2001 Radiological Environmental Monitoring Report for the Three Mile Island Nuclear Station.

Please contact Adam Miller of TMI-1 Regulatory Assurance at (717) 948-8128 if you have any questions regarding this submittal.

Sincerely, George H. Gellrich Plant Manager GHG/awm Enclosure cc:

Region I Administrator TMI-1 Senior Project Manager TMI-2 Project Manager TMI Senior Resident Inspector GPU Nuclear TMI-2 Cognizant Officer File 02011

Radiological Environmental Monitoring Report 2001 Prepared by Three Mile Island Rad, Health & Safety AmerGen.

An Exelon/British Energy Company

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE OF CONTENTS Page Title i

TABLE OF CONTENTS iii LIST OF TABLES iv LIST OF FIGURES v

LIST OF ABBREVIATIONS, SYMBOLS AND ACRONYMS 1

SUMMARY

AND CONCLUSIONS 5

RADIOLOGICAL ENVIRONMENTAL MONITORING 6

Environmental Exposure Pathways to Humans from Airborne and Liquid Effluents 6

Sampling 7

Analysis 8

Data Review 8

Quality Assurance Program 20 DIRECT RADIATION MONITORING 21 Sample Collection and Analysis 22 Direct Radiation Results 25 ATMOSPHERIC MONITORING 25 Sample Collection and Analysis 26 Air Particulate Results 27 Air Iodine Results 31 AQUATIC MONITORING 32 Sample Collection and Analysis 33 Water Results 37 Fish Results 37 Sediment Results 46 TERRESTRIAL MONITORING 47 Sample Collection and Analysis 48 Milk Results 49 Edible Terrestrial Vegetation Results 50 Deer Meat Results 50 Rodent Results 52 GROUNDWATER MONITORING 53 Sample Collection and Analysis 54 Groundwater Results 56 Storm Water and EDCB Sediment Results Page i M

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Page Title 58 RADIOLOGICAL IMPACT OF TMINS OPERATIONS 59 Determination of Radiation Doses to the Public 60 Results of Dose Calculations 65 REFERENCES APPENDIX A:

APPENDIX B:

APPENDIX C:

APPENDIX D:

APPENDIX E:

APPENDIX F:

APPENDIX G:

APPENDIX H:

2001 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions 2001 Lower Limit of Detection (LLD)

Exceptions 2001 REMP Changes 2001 Cross Check Program Results 2001 Land Use Census 2001 Data Reporting and Analysis 2001 Groundwater Monitoring Results 2001 TLD Quarterly Data I

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF TABLES Page Title 13 Table 1 Summary of Radionuclide Concentrations in 2001 Environmental Samples from Three Mile Island Nuclear Station 28 Table 2 2001 Average Gross Beta Concentrations in Airborne Particulates 39 Table 3 2001 Average Tritium Concentrations in Surface and Drinking Water 40 Table 4 2001 Average Gross Beta Concentrations in Drinking Water 62 Table 5 Calculated Maximum Hypothetical Doses to an Individual from 2001 TMI-1 and TMI-2 Liquid and Airborne Effluents 63 Table 6 Calculated Whole Body Doses to the Maximum Individual and the Population from 2001 TMI-1 and TMI-2 Liquid and Airborne Effluents Page iii

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF FIGURES Page Title 10 Figure 1 Locations of REMP Stations Within 1 Mile of T1INS I I Figure 2 Locations of REMP Stations I to 5 Miles from TMINS 12 Figure 3 Locations of REMP Stations Greater Than 5 Miles from TM1NS 24 Figure 4 Historical Gamma Exposure Rates 29 Figure 5 2001 Gross Beta Concentrations in Air Particulates 30 Figure 6 Historical Gross Beta Concentrations in Air Particulates 41 Figure 7 2001 Tritium Concentrations in Surface Water 42 Figure 8 Historical Tritium Concentrations in Surface Water 43 Figure 9 2001 Tritium Concentrations in Drinking Water 44 Figure 10 2001 Gross Beta Concentrations in Drinking Water 45 Figure 11 Historical Cs-137 Concentrations in Aquatic Sediments 51 Figure 12 Historical Strontium-90 Concentrations in Cow Milk 64 Figure 13 Exposure Pathways for Radionuclides Routinely Released from TMINS Page iv

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF ABBREVIATIONS, SYMBOLS AND ACRONYMS ABBREVIATIONS cubic feet per second..............................................

cfs cubic m eter(s).........................................................

m 3 curie(s)...............................................................

Ci curie(s) per year...........................................

Ci/yr east.......................................................................

E east-northeast...............................................

EN E east-southeast......................................................

ESE gram (s).................................................................

g hour(s).................................................................

h liter(s).................................................................

L m eter(s)....................................................................

m m icroroentgen(s) per hour..................................

gR/h m ile per hour........................................................

m ph m illirem (s).........................................................

m rem m illirem (s) per hour.......................................

m rem /h millirem(s) per standard m onth................................................

m rem /std m onth m illirem (s) per year.......................................

m rem/yr m illiroentgen(s).................................................

m R m illiroentgen(s) per hour................................... m R/h milliroentgen(s) per standard m onth....................................................

m R/std m onth north....................................................................

N northeast..........................................................

NE northw est........................................................

NW north-northeast...................................................

NN E north-northwest.................................................

NN W percent.....................................................................

picocurie(s)............................................................

pCi picocurie(s) per cubic m eter........................... pCi/m 3 picocurie(s) per gram.........................................

pCi/g picocurie(s) per liter..........................................

pCi/L reference(s)...............................................

Ref. (Refs.)

rem (s) per year.................................................

rem/yr Roentgen(s)........................................................

R Roentgen(s) equivalent m an................................

rem south....................................................................

S southeast...........................................................

SE southwest........................................................

SW south-southeast.....................................................

SSE south-southwest..................................................

SSW standard deviation............................................

std dev standard m onth...........................................

std m onth west....................................................................

W west-northwest..................................................

W N W west-southw est.................................................

W SW year(s)..................................................................

yr ELEMENT SYMBOLS actinium.............................................................

A c am ericium.........................................

Am antim ony.............................................................

Sb argon.............................

Ar barium...............................................................

Ba beryllium...........................................................

Be carbon.................................................................

C cesium...............................................................

Cs chrom ium..........................................................

Cr cobalt.................................................................

Co curium...............................................................

Cm hydrogen (tritium )................................................

H -3 iodine....................................................................

I iron....................................................................

Fe krypton...............................................................

K r lanthanum..........................................................

La m anganese........................................................

M n niobium.............................................................

N b nitrogen...............................................................

N oxygen.................................................................

0 plutonium...........................................................

Pu potassium.............................................................

K radium...............................................................

Ra radon.................................................................

Rn silver.................................................................

A g strontium.............................................................

Sr thorium................................................................

Th tritiated water vapor............................................

HTO uranium...............................................................

U xenon.................................................................

X e zinc....................................................................

Zn zirconium..........................................................

Zr Page v

L 2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ACRONYMS aboveground tank monitoring program...... ATMP accident generated water............................... AGW AmerGen Energy Company, LLC......... AmerGen American National Standards Institute........ ANSI annual land use census................... ALUC as low as reasonably achievable............... ALARA biological effects of atomic radiation.......... BEAR biological effects of ionizing radiation......... BEIR borated water storage tank.......................... BWST building 48........................................................

48S Department of Energy....................................

DOE east dike catch basin......................... EDCB Environmental Measurement Laboratory..... EML Environmental Radioactivity Laboratory....... ERL Federal Radiation Council.............................. FRC final safety analysis report...........................

FSAR G PU Inc..........................................................

G PU groundwater monitoring program................. GMP high efficiency particulate air...................... HEPA International Committee on Radiation Protection.......................................................

ICR P lower limit of detection................................... LLD maximum permissible concentration............ MPC m ean sea level...................................................

m sl Milton Hershey School.............................

MIHS minimum detectable concentration......MDC National Academy of Sciences...................... NAS National Council on Radiation Protection and Measurements...................... NCRP National Institute of Standards and Technology.....................................................

N IST National Voluntary Laboratory Accreditation Program..............................

NVLAP offsite dose calculation manual................. ODCM operations support facility..............................

OSF Pennsylvania State Bureau of Radiation Protection....................................

PaBRP Post Defueling Monitored Storage............. PDMS pressurized water reactor..................

PWR quality assurance.........................................

QA quality control.............................................

QC radiological environmental monitoring program.......................................................

REM P Red H ill Dam.................................................

RM Safe Harbor Dam.......................................

SHD simplified environmental effluent dosimetry system........................................

SEEDS Teledyne Brown Engineering.................. TBE thermoluminescent dosimeter........................ TLD Three Mile Island......................................

TMI Three Mile Island Environmental A ffairs........................................................

TM IEA Three Mile Island Nuclear Station.....

TMINS Three Mile Island - Unit 1........................... TMI-1 Three Mile Island - Unit 2...........................

TMI-2 Title 10 of the Code of Federal Regulations, Part 20..............................

10 CFR 20 Title 10 of the Code of Federal Regulations, Part 50, Appendix I.................... 10 CFR 50 App. I Title 40 of the Code of Federal Regulations, Part 190.......................... 40 CFR 190 United Nations Scientific Committee on the Effects of Atomic Radiation.................................

UNSCEAR United States Environmental Protection Agency.....................................

USEPA United States Nuclear Regulatory Com m ission..............................................

USNRC York Haven Generating Station............. YHGS York Haven Dam...........................................

YHD York Haven Pond...........................................

YHP Pare vi

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

AND CONCLUSIONS The radiological environmental monitoring performed in 2001 by AmerGen for the Three Mile Island Nuclear Station (TMINS) is discussed in this report. The environmental sample results and the doses calculated from measured effluents indicated that TMINS operations in 2001 had no adverse effect on the health of the public or the environment.

The operation of a nuclear power station results in the release of small amounts of radioactive materials to the environment. A radiological environmental monitoring program (REMP) has been established to monitor radiation and radioactive materials in the environment around TMINS. The results of environmental measurements are used to assess the impact of TMINS operations, to demonstrate compliance with the TMI-1 and TMI-2 Technical Specifications (Refs. 1 and 2) and applicable Federal and State regulations, and to verify the adequacy of containment and radioactive effluent control systems. The program also evaluates the estimated radiation doses to individuals due to radioactive effluents.

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Summaries and interpretations of the data are published annually in the Radiological Environmental Monitoring Report. Previous reports in this series are referenced at the end of the report (Refs. 3 through 30 and 41).

Additional information concerning releases of radioactive materials to the environment is contained in the Radiological Effluent Release Reports. These reports are submitted annually to the United States Nuclear Regulatory Commission (USNRC).

Many of the radioactive materials discussed in this report are typically present in the environment, either from natural processes or as a result of non-TMINS activities such as past atmospheric nuclear weapon tests and medical industry activities. To determine the impact of TMINS operations, if any, on the environment and the public, results from samples collected close to TMINS (indicator stations) are compared to results from samples obtained at distant sites (control or background stations). Comparisons with historical data also are performed, as appropriate.

During 2001, samples of air, surface, effluent, drinking and storm water, sediments, fruits, vegetables, grains, fish, groundwater and milk were collected. Direct radiation exposures also were measured in the vicinity of TMINS.

Samples were analyzed for gross beta radioactivity, tritium (H-3), strontium-89 (Sr-89) and strontium-90 (Sr-90), iodine-131 (1-131) and/or gamma-emitting radionuclides.

The results are discussed in the various sections of this report. Additionally, radiological impacts in terms of radiation dose as a result of TMINS radioactive releases were calculated and are discussed in this report (Radiological Impact of TMINS Operations).

The results provided in this report are summarized in the following highlights:

"* In 2001, 1059 samples were collected from the aquatic, atmospheric and terrestrial environments around TMINS.

There were 1291 analyses performed on these samples. Also, 2160 radiation exposure measurements were taken using thermoluminescent dosimeters (TLDs).

Finally, 93 groundwater samples were collected and 117 analyses were performed on these samples. The monitoring performed in 2001 met or exceeded the sample collection and analysis requirements of the TMI-1 and TMI-2 Technical Specifications.

"* In addition to natural radioactivity, low concentrations of radionuclides such as H-3, Sr-90, cesium-137 (Cs-137) and 1-131 were detected in some media and were attributed to either fallout from prior nuclear weapon tests, the medical industry or TMINS operations.

"* As a result of routine TMINS operations, the raw surface water collected downstream of the TMINS liquid discharge outfall occasionally had H-3 concentrations greater than those detected in control samples. This was expected because H-3 was released in liquid effluents and the samples were collected at a location where mixing of liquid effluents with Susquehanna River water was incomplete. All but one of the measured concentrations were below the Page 2 1

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT United States Environmental Protection Agency's (USEPA) Primary Drinking Water Standard of 20,000 picocuries per liter (pCi/L). The exception was biased as a result of using semiweekly grab samples (rather than hourly aliquots) to represent the collection period.

E Several indicator drinking water samples contained H-3 at concentrations above those detected in control samples. A portion of the H-3 measured in the indicator samples was attributed to routine operations at TMINS. The measured concentrations were a small fraction of the USEPA Primary Drinking Water Standard.

E Low concentrations of TMINS-related Cs-137 were detected in aquatic sediments collected proximal to or just downstream of the TMINS liquid discharge outfall. During 2001, as well as in previous years, this material was routinely released in TMINS liquid effluents. Additionally, Cs-137 is readily adsorbed by suspended particles in the water column and bottom sediments.

Since Cs-137 also was detected in the control samples, a portion of the Cs-137 measured in the indicator samples was attributed to fallout from prior nuclear weapon tests.

0 Groundwater samples collected from the onsite monitoring wells and the industrial wells contained H-3 above ambient concentrations as a result of current operations at TMI-1 and/or various non routine TMI-l and TMI-2 events. All H-3 concentrations detected in onsite groundwater were below the effluent concentration specified in USNRC 10 CFR 20 (Appendix B, Table 2).

0 Tritium was detected in onsite groundwater used for drinking. The presence of H-3 in these samples was attributed to current or past TMI-l operations and possibly past TMI-2 operations. All of the H-3 concentrations measured in onsite drinking water were a small fraction of the USEPA Primary Drinking Water Standard.

0 Gamma radiation exposure rates recorded at the offsite indicator TLD stations averaged 61 milliroentgens per year (mR/yr). Offsite controls were similar, averaging 66 mR/yr. The exposure rates were consistent with those presented by the National Council on Radiation Protection and Measurements (Ref. 31).

No significant increase in ambient gamma radiation levels was detected.

E During 2001, small amounts of radioactive materials were released in TMI-1 and TMI-2 liquid and gaseous effluents. Release amounts were minimized due to good fuel integrity, minimal leakage in the steam generators and improved efficiency of the waste processing systems.

E The calculated doses to the public from TMINS operations in 2001 were well below all applicable regulatory limits and significantly less than doses received from other common sources of radiation. The maximum hypothetical whole body dose received by an individual from 2001 Page 3

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.2 mrem. This dose is equivalent to 0.07 percent of the dose that an individual living in the TMI area receives each year from natural background radiation.

0 The maximum hypothetical whole body dose to the surrounding population from all 2001 liquid and airborne effluents was calculated to be 11 person-rem. This dose is equivalent to 0.002 percent of the dose that the total population living within 50 miles of TMI receives each year from natural background radiation.

In conclusion, 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 2001 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 significant 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 2001 did not have any adverse effects on the health of the public or on the environment.

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING Three Mile Island (TMI) is located about 2.5 miles south of Middletown in Londonderry Township, Dauphin County, Pennsylvania. Approximately 2.1 miles long and 0.3 miles wide, TMI is one of the largest of a group of several islands in the Susquehanna River. Three Mile Island Nuclear Station (TMINS) is situated on the northern one-half of TMI. The station consists of two pressurized water reactors (PWR), TMI-1 and TMI-2. Only TMI-1 is an operating reactor. The TMI-2 reactor was shut down in 1979. At the end of 1993, TMI-2 was placed in a condition called Post-Defueling Monitored Storage (PDMS). Both reactors are expected to be decommissioned when TMI-1 ceases operations.

Comprehensive radiological environmental monitoring is conducted by AmerGen at TMINS to measure levels of radiation and radioactive materials in the environment. The information obtained from the radiological environmental monitoring program (REMP) is then used to determine the effect of TMINS operations, if any, on the environment and the public.

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200U1 ADLIOJLOGICAL i'V VIRON'MLiViAL MONITORING REPORT The USNRC has established regulatory guides which contain acceptable monitoring practices. The TMINS REMP was designed on the basis of these regulatory guides along with the guidance provided by the USNRC Radiological Assessment Branch Technical Position for an acceptable radiological environmental monitoring program (Ref. 32).

The TMINS REMP meets or exceeds the monitoring requirements set forth by the USNRC.

The important objectives of the REMP are:

To assess dose impacts to the public from TMINS operations.

To verify inplant controls for the containment of radioactive materials.

To determine buildup of long-lived radionuclides in the environment and changes in background radiation levels.

To provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the environment.

To fulfill the requirements of the TMI-1 and TMI-2 Technical Specifications.

Environmental Exposure Pathways to Humans from Airborne and Liquid Effluents Small amounts of radioactive materials are released to the environment as a result of operating a commercial nuclear power station.

Once released, these materials move through the environment in a variety of ways and may eventually reach humans via breathing, drinking, eating and direct exposure. These routes of exposure are referred to as environmental exposure pathways. Figure 13 illustrates the important exposure pathways.

As can be seen from this figure, these exposure pathways are both numerous and varied. While some pathways are relatively simple, such as inhalation of airborne radioactive materials, others may be complex.

For example, radioactive airborne particulates may deposit on grass and when eaten by cows may be transferred into milk. The milk may then be consumed by humans. This route of exposure is referred to as the air-grass-cow-milk-human pathway.

Although radionuclides can reach humans by a number of pathways, some are more important than others. The critical pathway for a given radionuclide is the one that produces the greatest dose to a population, or to a specific segment of the population. This segment of the population is called the critical group, and may be defined by age, diet, or other cultural factors. The dose may be delivered to the whole body or confined to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ. This information was used to develop the TMINS REMP.

Sampling The TMINS REMP consists of two phases -

the preoperational and the operational. Data gathered in the preoperational phase is used as a basis for evaluating radiation levels and radioactivity in the vicinity of the plant after the plant becomes operational. The P-xe 6 0

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT operational phase began in 1974 at the time TMI-1 became operational.

The program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and then interpreting the results. With emphasis on the critical exposure pathways to humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include, but are not limited to, air, water, sediment, fish, milk, fruits, vegetables and groundwater. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels.

The Offsite Dose Calculation Manual, ODCM, (Ref. 33) implements the TMI-1 and TMI-2 Technical Specifications and defines the sample types to be collected and the analyses to be performed. As appropriate, changes to the REMP are initiated by recommendations from staff scientists.

However, the minimum sampling and analysis requirements specified in the ODCM are maintained.

Sampling locations were established by considering topography, meteorology, population distribution, hydrology, areas of public interest and land use characteristics of the local area. The sampling locations are divided into two classes, indicator and control.

Indicator locations are those that are expected to show effects from TMINS operations, if any exist. These locations were selected primarily on the basis of where the highest predicted environmental concentrations would occur. The indicator locations are typically downstream or within a few miles of TMINS.

Control stations are located generally upstream or at distances greater than 10 miles from TMINS. The samples collected at these sites are expected to be unaffected by TMINS operations. Data from control locations provide a basis for evaluating indicator data relative to natural background radioactivity and fallout from prior nuclear weapon tests.

Figures 1, 2 and 3 show the current sampling locations around TMI. Table A-I in Appendix A describes the sampling locations by distance and azimuth along with the type(s) of samples collected at each sampling location.

Analysis In addition to specifying the media to be collected and the number of sampling locations, the ODCM also specifies the frequency of sample collection and the types and frequency of analyses to be performed.

Also specified are analytical sensitivities (detection limits) and reporting levels. Table A-2 in Appendix A provides a synopsis of the sample types, number of sampling locations, collection frequencies, number of samples collected, types and frequencies of analyses, and number of samples analyzed. Table A-3 in Appendix A lists samples which were not collected or analyzed per the requirements of the ODCM. Sample analyses which did not meet the required analytical sensitivities are presented in Appendix B. Changes in sample collection and analysis are described in Appendix C.

Measurement of low radionuclide concentrations in environmental media requires special analysis techniques.

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-1 7(1R I(AIIOLO(ICAL ENVIRONMENTAL MONITORING REPORT Analytical laboratories use state-of-the-art laboratory equipment designed to detect all three types of radiation emitted (alpha, beta, and gamma). This equipment must meet the analytical sensitivities required by the ODCM.

Examples of the specialized laboratory equipment used are germanium detectors with multichannel analyzers for determining specific gamma-emitting radionuclides, liquid scintillation counters for detecting H-3 and low level proportional counters for detecting gross beta radioactivity.

Calibrations of the counting equipment are performed by using standards traceable to the National Institute of Standards and Technology (NIST). Computer hardware and software used in conjunction with the counting equipment perform calculations and provide data management.

Data Review The analytical results are routinely reviewed by a staff scientist to assure that sensitivities have been achieved and that the proper analyses have been performed. Investigations are conducted when action levels or USNRC reporting levels are reached or when anomalous values are discovered. The action levels were established by staff scientists and are typically 10 percent of the USNRC reporting levels specified in the ODCM.

These levels are purposely set low so that corrective action can be initiated before a USNRC reporting level is reached.

Table 1 provides a summary of radionuclide concentrations detected in the environmental samples analyzed by the primary (main) laboratory. Statistical methods used to derive this table along with other statistical conclusions are detailed in Appendix F. The sample results from the quality control (QC) laboratory were used mainly to verify the sample results reported by the primary laboratories. Therefore, the QC results were excluded from Table 1 and the main text of this report to avoid biasing the results.

Quality Assurance Program A quality assurance (QA) program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs" (Ref. 34) and as required by the Technical Specifications. It is documented by written policies, procedures, and records.

These documents encompass all aspects of the REMP including sample collection, equipment calibration, laboratory analysis and data review.

The QA program is designed to identify possible deficiencies so that corrective action can be taken. It also provides a measure of confidence in the results of the monitoring program in order to assure the regulatory agencies and the public that the results are valid. The QA program for the measurement of radioactivity in environmental samples is implemented by:

Auditing all REMP-related activities including analytical laboratories.

Requiring analytical laboratories to participate in a cross check program(s).

Requiring analytical laboratories to split samples for separate analysis (recounts are performed when samples cannot be split).

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT N

Splitting samples, having the samples analyzed by independent laboratories, and then comparing the results for agreement.

0 Reviewing QC results of the analytical laboratories including spike and blank sample results and duplicate analysis results.

The cross-check program results for the primary laboratories are outlined in Appendix D.

The TLD readers are calibrated on a routine basis against recognized standards. Also, control TLDs are processed with each group of TLDs. The accuracy and variability of the control TLD results are examined to assure the reader is functioning properly. In addition, each element (TLD) has an individual correction factor based on its response to a known exposure. Other cross checks, calibrations, and certifications are in place to assure the accuracy of the TLD program. The environmental dosimeters were tested and qualified to the American National Standard Institutes (ANSI) publication N545-1975 and the USNRC Regulatory Guide 4.13 (Refs. 35 and 36). The results for some of these tests were published in the Health Physics Journal (Ref. 37).

In addition to the TMINS REMP, the Pennsylvania State Bureau of Radiation Protection (PdiBRP) also maintains a surveillance program in the TMI area. This program provides an independent assessment of radioactive releases and the radiological impact on the surrounding environment. The results from this program have compared favorably with those from the TMINS program.

Samples of the TMINS liquid discharge are collected and analyzed as a QC check for the inplant effluent monitoring program. For 2001, the results obtained by the REMP were consistent with those reported for the inplant effluent monitoring program.

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362 7.OE-02 ND 8 362 1.OE-02 2.2E-02 (311/311)

(8.7E 4.5E-02) 28 5.OE-02 6.5E-02 (24/24)

(4.8E 8.1E-02) 28 5.OE-02 ND 28 6.OE-02 ND 28 2.OE-02 1.4E-02 (1/24) 8 2.5E-02 8

1.0E-02 8

8 8

1.3E-01 1.3E-01 1.3E-01 1.5E-01 2.6E-01 Q15-1, 13.5 mi NW West Fairview H3-1, 2.3 mi SSE Falmouth M2-1, 1.3 mi WSW Goldsboro 2.2E-02 (51/51)

(9.7E 4.OE-02) 6.7E-02 (4/4)

(5.8E 7.8E-02) 1.4E-02 (1/4)

ND ND ND ND ND ND ND ND 2.2E-02 (51/51)

(9.7E 4.0E-02i 6.2E-02 (4/4)

(4.9E 7.2E-02)

ND ND ND ND ND ND ND ND ND ND 2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 1 Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station' Air Iodine (pCi/m3)

Air Particulates (pCi/m3)

Fish (pCi/g,wet)

Gamma Spec 1-131 Gross Beta Gamma Spec Be-7 Cs-134 Cs-1 37 K-40 Sr-89 Sr-90 Gamma Spec Co-58 Co-60 Cs-134 Cs-137 Fe-59 0

0 0

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 1 Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station1 Location with Highest Mean9, Station Name, Distance, Direction, and Description6 Control Locations Mean (F)4 (Range)

Mean (F) 4 (Range) 8 5.0E-01 2.7E+00 (4/4)

BKGP, Control Predators (2.4E+00 - 3.2E+00)

Above Discharge 8

1.3E-01 ND 8

2.6E-01 ND 2.9E+00 (2/2)

(2.7E+00 - 3.1E+00) 2.8E+00 (4/4)

(2.7E+00 - 3.1E+00)

ND ND Aquatic Sediments (pCi/g dry) 6 2.0E-01 1.2E+00 (4/4)

(8.OE 1.5E+00) 6 2.0E-01 1.3E+00 (2/4)

(5.3E 2.OE+00) 6 1.5E-01 ND 6

1.8E-01 1.5E-01 (4/4)

(1.4E 2.OE-01) 6 2.0E-01 1.2E+01 (4/4)

(7.7E+00 - 1.7E+01) 6 2.OE-01 1.9E+00 (4/4)

(1.3E+00 - 2.5E+00) 36 4.OE+00 2.7E+00 (24/24)

(1.6E+00 - 3.7E+00) 36 2.0E+03 2.8E+02 (4/24)

(1.8E+02 - 4.4E+02)

J2-1, 1.5 mi S Above York Haven Dam J2-1, 1.5 mi S Above York Haven Dam J2-1, 1.5 mi S Above York Haven Dam J2-1, 1.5 mi S Above York Haven Dam J2-1, 1.5 mi S Above York Haven Dam G15-2, 13.6 mi SE Wrightsville Water Supply, Wrightsville G15-3, 14.8 mi SE Lancaster Water Authority, Columbia 1.5E+00 (2/2)

(1.5E+00 - 1.5E+00) 2.OE+00 (1/2) 1.7E-01 (2/2)

(1.4E 2.OE-01) 1.6E+01 (2/2)

(1.4E+01 - 1.7E+01) 2.4E+00 (2/2)

(2.3E+00 - 2.5E+00) 1.1E+00 (2/2)

(1.OE+00 - 1.1E+00) 6.2E-01 (1/2)

ND 7.6E-02 (2/2)

(6.8E 8.4E-02) 1.OE+01 (2/2)

(9.8E+00 - 1.1E+01) 1.9E+00 (2/2)

(1.8E+00 - 1.9E+00) 3.OE+00 (12/12) 1.9E+00 (9/12)

(2.3E+00 - 3.7E+00) (1.4E+00 - 2.4E+00) 3.1E+02 (3/12)

(2.2E+02 - 4.4E+02)

ND 0

0 0

0 Page 14 Fish (pCi/g,wet)

K-40 Mn-54 Zn-65 Gamma Spec Ac-228 Number of Reportable Results 7

Be-7 Cs-134 Cs-137 K-40 Ra-226 0

0 0

Drinking Water (pCi/L)

Gross Beta Tritium

1-131 (low level) 36 1.0E+00 ND Gamma Spec Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Gamma Spec Cs-134 36 36 36 36 36 36 36 36 36 36 36 36 6.OE+01 1.5E+01 1.5E+01 1.5E+01 1.8E+01 3.0E+01 5.0E+01 1.5E+01 1.5E+01 1.5E+01 3.OE+01 3.0E+01 2

6.OE-02 ND ND ND ND ND ND 1.4E+02 (1/24)

G15-3, 14.8 mi SE Lancaster Water Authority, Columbia ND ND ND ND ND ND 2001 RADIOLOGICAL ENVIRONMEN TA L MONITORING REPORT TABLE 1 Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station1 Drinking Water (pCi/L)

ND ND ND ND ND ND ND 1.4E+02 (1/12) 1.4E+02 (1/12)

Fruits (pCi/g,wet) 0 0

0 0

0 ND ND ND ND ND ND 0

Page 15

Fruits Cs-137 2

8.OE-02 ND (pCi/gwet) 2 2

6.OE-02 ND 4.0E-01 2.7E+00 (1/1)

E1-2, 0.4 mi E TMI Visitors Center 2

2 2

2 6.OE-02 8.OE-02 6.0E-02 4.OE-01 ND ND ND 1 9E+00 (1/1) 2 2.5E-02 B10-2, 10.1 mi NNE Milton Hershey School, Hershey ND 2

1.0E-02 2.4E-03 (1/1) 2 2

2 6.OE-02 8.OE-02 6.0E-02 E1-2, 0.4 mi E TMI Visitors Center ND ND ND 2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE I Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station1 Location with Highest Mean 9, Station Name, Distance, Direction, and Description 6

1-131 K-40 Grains (pCi/gwet)

Broad Leaf Vegetables (pCi/gwet)

ND 2.7E+00 (1/1)

ND 2.1E+00 (1/1) 0 0

0 Gamma Spec Cs-134 Cs-137 1-131 K-40 Sr-89 Sr-90 Gamma Spec Cs-134 Cs-1 37 1-131 1.9E+00 (1/1)

ND ND ND 1 9E+00 (1/1) 0 0

0 0

ND 2.4E-03 (1/1).

0 1.5E-03 (1/1)

ND ND ND 0

0 0

0 Page 16

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE I Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station' Media or Pathway Sampled (Unit of Measurement)

Location with Highest Total Number Lower Limit Mean9, Station Name, of Analyses of Detection Indicator Locations Distance, Direction, and Analyses Performed2 (LLD)'

Mean (F)4 (Range)

Description6 K-40 2

4.OE-01 2.5E+00 (1/1)

Gamma Spec Cs-134 Cs-137 1-131 K-40 1-131 (low level) 2 2

2 2

6.OE-02 8.OE-02 6.OE-02 4.OE-01 ND ND ND 4.3E+00 (1/1) 100 1.OE+00 16 16 Gamma Spec Ba-140 Cs-1 34 Cs-1 37 K-40 La-140 100 100 100 100 E1-2, 0.4 mi E TMI Visitors Center E1-2, 0.4 mi E TMI Visitors Center 2.5E+00 (1/1) 4.3E+00 (1/1)

ND 5.OE+00 ND 2.OE+00 1.1E+00 (11/12)

(5.4E 2.OE+00) 6.OE+01 1.5E+01 1.8E+01 5.OE+01 100 1.5E+01 D2-1, 1.1 mi ENE Dairy Farm ND ND ND 1.4E+03 (75/75)

K15-3, 14.5 mi SSW (9.6E+02 - 1.6E+03) Dairy Farm ND 1.8E+00 (1/1)

ND ND ND 3.OE+00 (1/1)

ND ND 1.6E+00 (3/4) 1.3E+00 (3/4)

(1.2E+00 - 2.OE+00) (7.6E 2.2E+00)

ND ND ND 1.5E+03 (25125) 1.5E+03 (25/25)

(1.1E+03-1.7E+03) (1.1E+03-1.7E+03)

ND Broad Leaf Vegetables (pCi/gwet)

Vegetables (pCi/g,wet)

Milk (pCi/L) 0 Sr-89 Sr-90 0

0 0

0 Page 17

Tritium 24 2.0E+03 5.5E+03 (8/12)

J1-2, 0.5 mi S (5,4E+02 - 3.OE+04)

West Shore of TMI 1-131 (low level) 12 1.OE+00 A3-2, 2.5 mi N Swatara Creek, Middletown Gamma Spec Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Direct Radiation (mR/std month)

Gamma 24 24 24 24 24 24 24 24 24 24 24 24 21075 6.OE+01 1.5E+01 1.5E+01 1.5E+01 1.8E+01 3.OE+01 5.OE+01 1.5E+01 1.5E+01 1.5E+01 3.OE+01 3.OE+01 ND ND ND ND ND ND ND ND ND ND ND ND Q9-1, 8.5 mi NW Steelton Water Authority, Steelton 5.5E+03 (8/12)

ND (5.4E+02 - 3.OE+04) 6.7E-01 (4/12) 6.7E-01 (4/12)

(3.7E 9.8E-01)

ND ND ND ND ND ND 1.1 E+02 (3/12) 1.1 E+02 (3/12)

(6.5E+01 - 1.6E+02) (6.5E+01 - 1.6E+02)

ND ND ND ND ND 4.9E+00 (1843/1843) H8-1, 7.4 mi SSE (3.5E+00 - 8.1EE+00)

Saginaw Road, Starview 7.5E+00 (24/24) 5.5E+00 (264/264)

(6.7E+00 - 8.1E+00)

(4.2E+00 - 8.OE+00)

Page 18 L-P 1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE I Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station1 Location with Highest Mean9, Station Name, Distance, Direction, and Description 6

Surface Water10 (pCi/L) 0 0

0 0

0

1This table presents primary program results in exponential form (i.e., 1.2E-2 = 0.012) > minimum detectable concentration (MDC). It does not include duplicate analysis results or results from the quality control (QC) program, the rodent monitoring program or the groundwater monitoring program. Additionally, results from recounts supercede original results; reanalysis results supercede both original and/or recount results.

2The total number of analyses does not include duplicate analyses, recounts or reanalyses.

3The ODCM LLD (or MDC) is given when applicable. It should be noted that, in some cases, the TMINS REMP achieves LLDs that are lower than those required by the ODCM.

4(F) is the ratio of results > MDC to the number of samples analyzed. Means and ranges are based on results > MDC.

5The total number of elements (TLDs) that were used for data analysis.

SAil distances are measured from a point that is midway between the TMI-1 and TMI-2 reactor buildings.

7The total number of results that exceeded USNRC reporting levels as specified in the ODCM.

OND = Not Detected (i.e. all net sample concentrations were equal to or less than the MDC).

9The location with the highest mean was determined using more than two significant figure.

1°Sample results from Station K1-1 (TMINS liquid discharge) were used as a check for the inplant effluent sampling program and, therefore, were not included in this table.

"11This analysis was not performed on this medium.

Page 19 2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE I Summary of Radionuclide Concentrations in 2001 Environmental Samples Three Mile Island Nuclear Station1 i

i

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT DIRECT RADIATION MONITORING Radiation is a normal component of the environment resulting primarily from natural sources, such as cosmic radiation and naturally occurring radionuclides, and to a lesser extent from manmade sources, such as fallout from prior nuclear weapon tests. The cessation of atmospheric nuclear weapon tests and the decay of fallout products have resulted in a gradual decrease in environmental radiation levels. Direct radiation monitoring measures ionizing radiation primarily from cosmic and terrestrial sources.

Gamma radiation exposure rates near TMINS were measured using thermoluminescent dosimeters (TLDs). TLD stations were arranged in roughly concentric rings around TMINS, generally with one station in each of the 16 compass sectors, at the site boundary and 1, 2, 5, 8 and 10 or more miles from the site. Those TLD stations approximately 10 or more miles from the site were control (or background) stations while those less than 10 miles from the site were indicator stations. Indicator stations were located to detect any potential effect of TMINS operations on environmental radiation levels. Control stations were located at sites that should be unaffected by TMINS operations.

Page 20

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The TLDs were processed each calendar quarter. All gamma radiation exposure rates recorded during 2001 were within normal ranges and were consistent with previous results.

No relationship between TMINS operations and offsite exposure rates was indicated. The 2001 quarterly exposure rates for the individual TLD stations and a map showing onsite TLD station locations are contained in Appendix H. Offsite TLD stations are depicted on Figures 1, 2 and 3.

Sample Collection and Analysis A thermoluminescent dosimeter (TLD) is a crystal (phosphor) which absorbs and stores energy in traps when exposed to ionizing radiation. These traps are so stable that they do not decay appreciably over time. When heated, the crystal emits light proportional to the amount of radiation received, and the light is measured to determine the integrated exposure. This process is referred to as thermoluminescence. The reading process

'rezeros' (anneals) the TLD and prepares it for reuse. The TLDs in use for environmental monitoring at TMINS are capable of accurately measuring exposures between 1 mR (well below normal environmental exposures for the quarterly monitoring periods) and 200 R.

Each TLD station consists of 2 primary program TLD badges, each of which has 4 phosphors or elements. Since each TLD responds to radiation independently, this provides 8 independent detectors at each station. In addition, 10 stations have a vendor supplied quality control TLD badge which has 4 independent detectors, for a total of 12 detectors at each station. The quality control badges are used as an independent check on the accuracy of the primary program TLD results.

Of the 4 elements in the primary program's TLDs, 3 are composed of calcium sulfate and 1 is composed of lithium borate. The calcium sulfate elements are shielded with a thin layer of lead making the response to different energies of gamma radiation more linear. The lead also shields the elements from beta radiation, making them sensitive to gamma radiation only. The lithium borate element is shielded differently to permit the detection of beta radiation as well as gamma. The combination of different phosphor materials, shielding, and multiple phosphors per badge permit quantification of both gamma and beta radiation. Only the calcium sulfate phosphors are used for environmental monitoring; however, the lithium borate elements can be used to evaluate beta exposures or as a backup to the calcium sulfate elements should more data be required.

Data from the TLDs were evaluated by obtaining the average of the usable element results at each station, and comparing the result to historical averages and ranges for the period of TMINS shutdown between the first quarter of 1980 and the third quarter of 1985.

The averages and overall trends of the indicator and control stations were also compared with each other and with averages and trends obtained for the five-year shutdown period.

All TLD exposure rate data presented in this report were normalized to a standard month (std month) to adjust for variable field exposure periods. A std month is 30.4 days.

Several badges were used to quantify transit Paize 21 Page 21

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT exposure during storage and handling of TLDs.

Transit exposures were subtracted from gross field exposures to produce net field exposures.

Direct Radiation Results In 2001, the average annual exposure rate for offsite indicator stations, which excludes stations located on the TMINS site boundary fence, was 5.1 +/- 1.6 mR/std month. Quarterly exposure rates at offsite indicator stations ranged from 3.6 to 8.1 mR/std month. The average annual exposure rate for all control stations, those stations approximately 10 miles or more from TMINS, was 5.5 +/- 1.5 mR/std month. Quarterly exposure rates at control stations ranged from 4.2 to 8.0 mR/std month.

Similar exposure rates were measured in 2000 when offsite indicators and controls averaged 4.7 +/- 1.4 mR/std month and 5.1 +/- 1.4 mR/std month, respectively.

Typically, average exposure rates at control stations have been higher than those at offsite indicator stations. This is a result of variation in the natural radioactive characteristics of rock and soil near the stations. The historical average exposure rate (for the period from 1980 to 1985, when TMINS did not operate) was 5.2 mR/std month for indicator stations and 5.7 mR/std month for control stations.

Generally, exposure rates at both indicator and control stations have decreased gradually due to the cessation of atmospheric nuclear weapon testing and the decay of fallout products. This trend is depicted in Figure 4.

In 2001, the average annual exposure rate for all indicator stations, including those stations located on the TMINS site boundary fence, was 4.9 +/- 1.5 mR/std month. Quarterly average exposure rates ranged from 3.5 to 8.1 mR/std month. Similar exposure rates were measured in 2000 when all indicator stations averaged 4.6 +/- 1.7 mR/std month and ranged from 3.2 to 8.5 mR/std month.

Exposure rates at some indicator stations located on the site boundary fence were slightly elevated. This was not unexpected because these stations were located close to radioactive material transport routes or storage areas.

The average onsite exposure rates including those from stations located on the site boundary fence were typically lower than exposure rates for offsite stations. This is consistent with previous results and is a function of the differing characteristics of the land surface and geology in the immediate vicinity of the TLD stations. Many onsite stations are located on or above manmade surfaces or structures, which may shield the TLDs from terrestrial sources of radiation.

Exposure rates at stations on the site boundary fence vary with the movement and storage of onsite radioactive materials and with the number and placement of stations on the fence.

Occasionally, stations on the fence may be moved or added to ensure comprehensive coverage of some areas. For these reasons, year-to-year comparisons between stations on the site boundary fence and other indicator or control stations usually are not appropriate.

In 2001, the highest annual average exposure rate for an offsite location was 7.5 +/- 1.3 mR/std month at indicator Station H8-1. This annual average exposure rate is typical for Station H8-1, and is lower than the historical (1980-1985) exposure rate of 7.9 +/- 1.4 mR/std month for Station H8-1.

Page 22

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT During 2001, average quarterly exposure rates for offsite indicators and controls were slightly higher in the third and fourth quarters due to lower transit exposures. The average exposure rates observed at offsite indicator stations for the first, second, third and fourth quarters of 2001 were 4.7, 4.7, 5.6 and 5.3 mR/std month.

With slightly higher quarterly exposure rates, the controls trended similarly. Average exposure rates at control stations for the first, second, third and fourth quarters of 2001 were 5.2, 5.0, 6.0 and 5.9 mR/std month. The fact that both indicators and controls trended similarly suggested that TMINS operation did not change offsite exposure rates.

Figure 4 is a plot of gamma exposure rates (as measured by TLDs) in the vicinity of TMINS from 1974 through 2001. Data from stations located on the TMINS site boundary fence are excluded from the graph. Based on Figure 4,

{

the trends in exposure rates at indicator stations were similar to those of control stations with the exception of 1979. As a result of the TMI-2 accident, a transitory increase in exposure rates from the release of noble gases was observed. Increases also were I

observed in both indicator and control stations in 1976, 1977, and 1978 as a result of nuclear weapon tests.

No elevated exposure rates as a result of TMINS operations were observed at any offsite TLD station in 2001. The annual average gamma radiation exposure rate recorded at all offsite indicator TLD monitoring stations was 5.1 mR/std month.

This equates to an annual exposure rate of 61 mR/yr. An exposure of this magnitude is consistent with the annual average radiation dose a person receives from cosmic andI terrestrial sources (Ref. 31).

Page 23

Historical Gamma Exposure Rates mR per Standard Month by Quarter Indicator

- Control Significant Events Maior Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 STMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 TMI-1 Restart October 1985 December 1978 October 1980 Chernobyl April 1986

4-Figure 4 50 45-40--

35-301 25-I 20--

0 Eu E

15-I 10+-

5 n

i i

V i i

i 1

1 1 T 1

1 lr T r 0 r 1 I 11 1

I I w

I w

1 1

I w & N E w M V I

E F z I

I I

V-1 Co C

C CP Cot-C0 Co Co o

'COO C

Co Co Co Co Co C

Co ll Co CoI Co Co C

C Coa Quarter & Year I

Page 24

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ATMOSPHERIC MONITORING A potential exposure pathway to humans is inhalation of airborne radioactive materials. To monitor this exposure pathway, ambient air was sampled by a network of continuously operating samplers and then analyzed for radioactivity content. Based on the analytical results, no contribution to the general levels of airborne radioactivity was attributed to TMINS operations during 2001.

Sample Collection and Analysis The indicator air sampling stations were located primarily in the prevailing downwind directions to the east (TMINS Visitors Center, Station E 1-2),

the east-southeast (500 kV Substation, Station Fl 3), the southeast (dairy farm near Falmouth, Station G2-1), and the south-southeast (Falmouth, Station H3-1) of TMINS and in the nearby communities of Goldsboro (Station M2-1) and Middletown (Station A3-1). The control air sampling station was located in West Fairview (Station Q15-1), a community situated more than 13 miles from TMINS. This station provided background data for comparison.

Page 25 Pa*e 25

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Mechanical air samplers were used to continuously draw air through glass fiber filters and charcoal cartridges. To maintain a constant flow rate throughout the collection period, each sampler was equipped with an electronic mass flow controller. This device automatically adjusted the flow rate to compensate for dust loading and changes in atmospheric pressure and temperature.

Total air volumes were measured and recorded with dry gas meters. Air volumes were then adjusted based on vacuum readings over the collection period. All air samplers were calibrated semiannually and maintained by instrumentation technicians.

The glass fiber filters were used to collect airborne particulate matter. The filters were collected weekly and analyzed for gross beta radioactivity. The filters were then combined quarterly by individual station locations and analyzed for gamma-emitting radionuclides.

During the year, two glass fiber filters had sampling periods of less than two days.

These filters were not analyzed for gross beta radioactivity because the particulate matter collected was not representative of the weekly sampling period. The filters were, however, included in the quarterly composite samples that were analyzed for gamma-emitting radionuclides.

Cartridges containing activated charcoal were used for monitoring gaseous radioiodines.

These cartridges were placed downstream of the particulate filter at each of the air sampling stations. Charcoal cartridges were collected weekly and analyzed separately from the particulate filters for 1-131.

Two of the charcoal cartridges collected during 2001 had sampling periods of two days or less. These samples were not analyzed for gaseous radioiodines because they did not adequately represent the weekly collection period.

Air Particulate Results During 2001, more than 350 air particulate samples (filters) were collected weekly from seven locations and analyzed for gross beta radioactivity. The particulate matter (dust particles) collected on all indicator and control filters contained gross beta radioactivity above the minimum detectable concentration (MDC).

The gross beta concentrations measured on the filters collected from indicator sites ranged from 0.0087 + 0.0017 pCi/m3 to 0.045

+/- 0.003 pCi/m3 and averaged 0.022 + 0.013 pCi/m3. The air particulate samples collected from the control location had gross beta concentrations that ranged from 0.0097 +

0.0018 pCi/m3 to 0.040 + 0.003 pCi/m 3 and averaged 0.022 +/- 0.013 pCi/m3. For comparison, the 2000 average gross beta concentrations were 0.017 + 0.014 pCi/m3 and 0.017 +/- 0.014 pCi/m3 for indicators and controls, respectively.

The air sampling location with the highest annual average gross beta concentration (based on more than two significant figures) was control Station Q 15-1 (West Fairview).

The average gross beta concentration for airborne particulates collected at this station was 0.022 +/- 0.013 pCi/m3. This average concentration was well below the preoperational average concentration of Page 26 J:

L 1

ii

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 0.15 +/- 0.16 pCi/m3 and, as shown on Table 2, was similar to the annual average gross beta concentrations calculated for particulate samples collected at the other air sampling sites.

As depicted in Figure 5, average weekly gross beta concentrations at indicator and control air monitoring locations were somewhat variable, but trended similarly throughout the monitoring period. The weekly gross beta concentrations and trends at individual air sampling sites also were similar.

The similarity of indicator and control data suggested that gross beta radioactivity levels did not change in 2001 as a result of TMINS operations. Additionally, the gross beta radioactivity associated with airborne particulates was due primarily to naturally occurring radionuclides.

Historical trends of average quarterly gross beta concentrations associated with airborne particulates from 1972 to 2001 are depicted in Figure 6. Generally, the gross beta concentrations have decreased with time. The 2001 average gross beta concentration of 0.022 pCi/m 3, for indicators and controls combined, is approximately 15% of the 1974 preoperational average concentration (0.15 pCi/m3).

The overall diminution in gross beta concentrations is a direct result of the ban on atmospheric nuclear weapon tests and the radioactive decay of fallout products from previous detonations. Elevated concentrations at both indicator and control air monitoring stations were noted after each major nuclear weapon test, the TMI-2 accident, and the Chernobyl accident. The trends for indicator and control stations were similar for the entire TMINS operational period.

Gamma-emitting radionuclides related to TMINS operations were not detected on any of the quarterly composites that were analyzed in 2001. As expected, all of the quarterly composite samples contained naturally-occurring beryllium-7 (Be-7).

Concentrations detected on indicator samples were similar to those detected on control filters. Also, naturally-occurring potassium-40 (K-40) was detected on one sample.

Air Iodine Results During 2001, more than 350 charcoal cartridges were collected weekly and analyzed for 1-131. None of the weekly samples contained 1-131 (or any other isotope of iodine) above the MDC.

Page 27

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 2 2001 Average Gross Beta Concentrations in Airborne Particulates (pCi/m3 )

Station Description Averaiee +/- 2 std dev*

Middletown TMINS Visitors Center 500 kV Substation Dairy Farm (Near Falmouth)

Falmouth Goldsboro West Fairview 0.022 +/- 0.013 0.022 +/- 0.013 0.022 +/- 0.014 0.022 +/- 0.013 0.022 +/- 0.013 0.022 +/- 0.014 0.022 +/- 0.013

Averages and standard deviations are based on concentrations > MDC.

(I) = Indicator Station (C) = Control Station Page 28 A3-1(I)

E1-2(I)

F1-3 (I)

G2-1(I)

H3-1(I)

M2-1(I)

Q15-1(C) j L

I I

1 i-ii

2001 Gross Beta Concentrations in Air Particulates Picocuries per Cubic Meter by Week Indicator

-+- Control Month / Day of 2001 Figure 5 0.100 0.090 0.080

.0.070 a) o 0.060 S0.050 0.040 0.010 0.000 I

I Page 29

Historical Gross Beta Concentrations in Air Particulates Picocuries per Cubic Meter by Quarter Indicator 0.3+

Control

-I-Quarter & Year Figure 6 0.4 0.35-Significant Events Major Atm. Nuclear Weapon Tests TMI-I Critical June 1974 March 1972 June 1973 TM I-2 Critical M arch 1978 June 1974 Septem ber 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 TMI-I Restart October 1985 December 1978 October 1980

.. C hernobyl A pril 1986 L,

0.25 0.2

..)

~0.15 0

a.

0*.

0.15 "C.)

0.1 0.05 A3 I ----------

1 0

.÷ Page 30

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT AQUATIC MONITORING Since radioactive materials are released to the Susquehanna River from routine operations at TMINS and this watershed is used as a source for drinking water and recreational activities, the aquatic environment is monitored extensively for radionuclides of potential TMINS origin.

Recreational activities in the TMI reach of the Susquehanna River include fishing, boating, swimming and other water sports.

Monitoring of the aquatic environment in the vicinity of TMINS was accomplished by collecting and analyzing samples of surface water, drinking water, fish and river sediments. The indicator (downstream) sampling sites were chosen based on studies of travel time and mixing characteristics for the Susquehanna River.

Control samples were collected from locations which were not expected to be affected by TMINS operations. The impact of TMINS operations was assessed by comparing control sample concentrations to those measured in indicator samples. As applicable, comparisons with results from previous years also were performed.

Paae 31 Pape "41

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT During 2001, samples from the aquatic environment were found to contain low concentrations of radioactive materials attributable to routine TMINS operations.

They included Cs-137 in sediments and H-3 insurface water and drinking water. The concentrations found in these samples, however, were too low to adversely impact humans or the environment. Naturally occurring radionuclides and those attributed to the medical industry and to fallout from prior nuclear weapon tests also were identified in various aquatic media.

Sample Collection and Analysis Surface (raw/unfinished) and drinking (treated/finished) water samples were collected at six stations (three indicators and three controls) and analyzed during 2001.

Indicator samples were collected from locations along the Susquehanna River which were downstream of the TMINS liquid discharge outfall. Indicator surface water samples were collected at one location, Station J 1-2 (west shore of TMI). Indicator drinking water samples were collected at two water treatment facilities -- Station G 15-2 (Wrightsville Water Supply, Wrightsville, PA) and Station GI 5-3 (Lancaster Water Authority, Columbia, PA).

Control samples were collected from the Susquehanna River upstream of the TMINS liquid discharge outfall or from its tributaries.

Control surface water samples were collected from two locations -- Station A3-2 (Swatara Creek, Middletown, PA), and Station Q9-1 (Steelton Water Authority, Steelton, PA).

Control drinking water samples were obtained at one water treatment facility -- Station Q9-1 (Steelton Water Authority, Steelton, PA).

Samples of the TMINS liquid discharge (Station KI-1) also were collected and analyzed. The liquid discharge samples were collected from a location where the water was not yet mixed with the Susquehanna River.

As appropriate, data from the liquid discharge samples were compared with data obtained from samples collected as part of the TMINS Effluent Monitoring Program.

Water samples normally were obtained by an automatic water compositor. Grab samples were collected when sufficient sample volumes were not available. The compositors collected a measured volume of water (i.e.

aliquot) at a preset interval of time (30 or 60 minutes). These samplers were maintained and calibrated by instrumentation technicians.

The samples normally were retrieved biweekly (every two weeks). To verify that the compositors were operating properly, a surveillance was performed weekly.

Occasionally, samples were retrieved weekly to close out a calendar month or quarter. All water samples retrieved weekly and biweekly were then combined monthly by station.

The monthly samples from indicator drinking water Stations G15-3 and G15-2 along with those collected from control drinking water Station Q9-1 and control surface water Station A3-2 were analyzed for low-level 1-131 using a chemical separation (concentration) technique. Samples of the Page 32 I1 i

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TMINS liquid discharge also were analyzed for low-level 1-131 employing the same technique.

Except for those collected from control surface water Station A3-2, all monthly water samples were analyzed for H-3 and gamma emitting radionuclides, including 1-131.

Monthly gross beta analyses also were performed on all drinking water samples and the samples collected from Station K1-1.

Semiannual samples were prepared from monthly samples collected at Station KI-1 and analyzed for Sr-89 and Sr-90.

Electro-shocking equipment were used to collect fish samples in the spring (May and June) and fall (October and December) of 2001. To monitor the progression of radionuclides through the food chain, bottom feeding fish as well as predator species were collected. Indicator samples were collected from zones or areas immediately at or downstream of the TMINS liquid discharge outfall, while control specimens were gathered from locations greater than ten miles upstream of TMI. The edible portions were analyzed for Sr-89, Sr-90 and gamma emitting radionuclides.

As part of the routine REMP, river sediments from three locations (two indicators and one control) were collected in the spring (June) and fall (October) of 2001. Indicator sediment samples were collected at a site just downstream of the TMINS liquid discharge outfall (Station K1-3), and at the York Haven Dam, YHD, (Station J2-1). The control samples were obtained from the Susquehanna River just upstream of TMI (Station A1-3).

All sediment samples were collected using a dredge designed for this purpose. They were dried and then analyzed for gamma-emitting radionuclides.

Water Results Iodine-131 is produced during the fission process and may be a constituent of TMI-1 liquid effluents. This radionuclide also may be discharged to the Susquehanna River and its tributaries by medical facilities and their patients via the municipal sewage system.

Institutions such as hospitals utilize this material for diagnostic studies of the thyroid and thyroid therapy. Iodine-13 1 from medical facilities and their patients is commonly detected in REMP samples because the methods used to treat sewage do not remove this material.

During 2001, low-level 1-131 using the chemical separation/concentration technique was detected above the minimum detectable concentration (MDC) in 4 of 12 control surface water samples and in 4 of 12 samples collected from Station KI-1, the TMINS liquid discharge. Iodine-131 above the MDC was not detected in any of the indicator or control drinking water samples. Indicator surface water samples were not analyzed using the chemical separation/concentration technique.

The 1-131 concentrations measured in control surface water samples ranged from 0.37 4 0.21 pCi/L to 0.98 =L 0.22 pCi/L and averaged 0.67 +/- 0.50 pCi/L. For comparison, the average 1-131 concentration for 2000 control surface water samples was 1.5 +/- 2.5 pCi/L.

Page 33

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Four of twelve TMINS liquid discharge samples collected in 2001 contained 1-131 above the MDC. The 1-131 concentrations ranged from 0.35 +L 0.18 pCiIL to 1.4 +/- 0.2 pCi/L and averaged 0.81 +/- 0.95 pCi/L. The 2000 results were similar, ranging from 0.31

+/- 0.26 pCi/L to 2.1 +/- 0.2 pCi/L and averaging 1.0 +/- 1.2 pCi/L.

For three of the four times 1-131 was detected in a liquid discharge sample, a similar concentration of this material was measured in a control sample. On one occasion, however, 1-131 was not detected concurrently in a control sample. This may have been caused by the process used to cool water at TMINS.

Water is continually withdrawn from the Susquehanna River for cooling. During one of the cooling processes, a large amount of water is evaporated. The suspended and dissolved materials remain in the water and, therefore, are concentrated. One of these materials may be medically-related 1-131 (i.e.

1-131 released by upstream medical facilities and/or their patients). To prevent a buildup of these concentrated materials, some of the water is diluted and then returned or discharged to the Susquehanna River. It is possible that the dilution water also contains medically-related 1-131.

The similarity of the control and discharge results along with the possibility that 1-131 may be concentrated during the cooling process suggested that medical facilities and their patients, and not TMINS, was the source of the 1-131 detected in both the control surface water and the liquid discharge samples. The absence of 1-131 in 2001 liquid effluent samples supported this conclusion.

In 2001, H-3 above the MDC was measured in 8 of 12 monthly indicator surface water samples. This material was not detected in control surface water. Table 3 lists the annual average H-3 concentrations and the ranges for the samples collected at each surface water station. Also included in the table are the annual average concentrations and ranges based on actual sample concentrations, whether positive, negative or zero.

As expected, H-3, a major component of 2001 TMINS liquid effluents, was detected above the MDC in 67% of the monthly surface water samples collected at indicator Station JI-2. This station is located just downstream of the TMINS liquid discharge outfall where mixing of liquid effluents with river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam (YHD).

The annual average H-3 concentration for the samples collected at Station J1-2 was 5000 +/-

20000 pCi/L. The results ranged from 540 +/-

100 pCiiL to 30000 +/- 500 pCi/L. Some of the monthly concentrations as well as the annual average concentration were biased by missed aliquots or by using grabs. Missed aliquots were caused by sampler malfunctions, AC power failures or freezing temperatures. Grabs were taken and used when sufficient sample volumes were not available.

For comparison, H-3 was detected in 5 of 12 2000 monthly samples collected at Station Page 34 P 3

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT J1-2. The concentrations ranged from 83 +/-

50 pCi/L to 1400 +/- 100 pCi/L and averaged 400 +/- 1100 pCi/L. Like some of the 2001 H-3 concentrations, some of the 2000 concentrations were biased when the sampler was inoperable.

A higher average concentration was expected in 2001 because a higher amount of H-3 was released in 2001 liquid effluents.

Approximately 490 Ci of H-3 were released in liquid effluents in 2001, whereas, about 280 Ci were released in 2000. Higher amounts of H-3 were released in 2001 because more wastewater was processed in preparation for the refueling of TMI-1. The TMI-1 refueling outage began in October and ended in December.

Figure 7 depicts the 2001 monthly trends of H-3 concentrations in surface water samples collected at Station J1-2. Actual concentrations (whether positive, negative or zero) were plotted. For comparison, the actual monthly H-3 concentrations measured in the TMINS liquid discharge samples also are depicted in Figure 7. This figure shows that the H-3 concentrations measured in the samples obtained from Station J1-2 were directly related to those detected in the TMINS liquid discharge samples (Station K1 1). Historical trends of H-3 concentrations in surface water are shown in Figure 8.

A dose estimate was not performed for H-3 insurface water because this medium normally is not consumed by humans. All but one of the H-3 concentrations measured in surface water during 2001 were below the USEPA Primary Drinking Water Standard of 20,000 pCi/L. The lone exception was biased high by collecting and using grab samples to represent the monthly period. Grab samples provide only a snapshot of the collection period; they do not adequately represent the entire collection period.

In 2001, H-3 above the MDC was measured in 4 indicator drinking water samples. This material was not detected in any of the control drinking water samples. Table 3 lists the annual average H-3 concentrations for the samples collected at each drinking water station. Also included are the annual average concentrations based on actual sample concentrations, whether positive, negative or zero.

One monthly drinking water sample from indicator Station G15-2 (Wrightsville Water Supply, Wrightsville, PA) and three monthly drinking water samples from indicator Station G15-3 (Lancaster Water Authority, Columbia, PA) contained H-3 above the MDC. The H-3 concentrations averaged 280

+/- 230 pCi/L and ranged from 180 +/- 80 pCi/L to 440 +/- 110 pCi/L.

The H-3 concentrations measured in the 2001 indicator drinking water samples were similar to those measured in 2000, when 4 samples contained H-3 above the MDC. The measured concentrations averaged 180 +/- 180 pCi/L and ranged from 91 +/- 55 pCi/L to 290

+/- 100 pCi/L. The 2001 results also were consistent with those measured in other years.

Figure 9 (upper) displays the average monthly H-3 concentrations measured in the 2001 indicator and control drinking water samples.

Instead of only using concentrations above the MDC, actual concentrations (whether Page 35 Pa*e *5

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT positive, negative or zero) were used for the graph. This method eliminated biases in the data and missing data points. For comparison, the actual H-3 concentrations obtained from samples collected at Station KI -1 also were included in Figure 9 (lower).

Generally, Figure 9 shows that the highest average indicator concentrations occurred when the highest amounts of H-3 were released in TMINS liquid effluents. The concentrations measured in the indicator samples were consistent with data gathered from travel time and mixing studies. There were a number of months when the indicator average was similar to or less than the control sample concentration. This indicated that the H-3 measured in both indicator and control drinking water samples was most likely due to fallout from prior nuclear weapon tests or natural production of this material in the atmosphere.

To put the 2001 H-3 results into perspective, the highest monthly indicator concentration of 440 +/- 110 pCi/L represented only slightly more than 2% of the USEPA Primary Drinking Water Standard (20,000 pCi/L).

Furthermore, if an individual drank water at this concentration for an entire year, the maximum hypothetical whole body dose would be 0.05 mrem. This calculated dose is equivalent to less than 0.02% of the whole body dose that an individual living in the TMI area receives each year from natural background radiation (300 mrem).

Generally, the H-3 concentrations detected in samples collected at Station K1-l (TMINS liquid discharge) agreed well with those obtained from the TMINS Effluent Monitoring Program.

The monthly composites of all drinking water samples were analyzed for gross beta activity.

Table 4 lists, by station, the annual averages and ranges for gross beta concentrations above the MDC. Averages and ranges based on actual concentrations are included for comparison. The monthly (composite)

TMINS liquid discharge samples from Station KI-I also were analyzed for gross beta.

Most of the drinking water samples collected in 2001 contained gross beta radioactivity concentrations above the MDC. Indicator results ranged from 1.6 +/- 0.8 pCiIL to 3.7 _

0.7 pCi/L and averaged 2.7 +/- 1.1 pCi/L.

Similarly, the controls ranged from 1.4 +/- 0.8 pCi/L to 2.4 +/- 1.0 pCi/L and averaged 1.9 +/-

0.7 pCi/L. The 2001 averages were consistent with the 2000 averages of 2.2 + 1.2 pCi/L and 2.1 +/- 1.1 pCi/L for indicators and controls, respectively.

The monthly gross beta averages for indicator and control drinking water are plotted in Figure 10. Actual concentrations were used for this graph. Generally, indicator and control sample concentrations trended similarly throughout the year. Minor differences were evident, but expected.

The variability in the gross beta concentrations was directly related to the type of treatment and the overall contaminant removal efficiency of each water treatment facility. For example, suspended solids with adsorbed man-made or naturally-occurring Page 36 I

I Ji ii ii

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT radioactive materials are removed from raw river water by common treatment processes such as filtration and sedimentation. The amount removed by these processes will vary as a function of the individual system design and operation.

All of the drinking water results for 2001 were well below the Federal and State Primary Drinking Water Standard of 50 pCi/L for gross beta radioactivity. The results indicated that gross beta radioactivity detected in all drinking water samples was attributed to naturally-occurring radioactive materials.

In 2001, all of the monthly composite samples from Station KI-1 (TMINS liquid discharge) had gross beta radioactivity concentrations above the MDC. The gross beta concentrations ranged from 2.0 +/- 0.9 pCi/L to 8.8 +/- 1.3 pCi/L and averaged 4.3 +

4.4 pCi/L. The 2001 results were consistent with those reported in previous years for Station KI -1 samples. All TMINS liquid discharge samples, like drinking water samples, had gross beta concentrations well below the Federal and State Primary Drinking Water Standard of 50 pCiJL.

Monthly composite samples of surface and drinking water were analyzed for the presence of gamma-emitting radionuclides. None of the samples collected in 2001 contained detectable levels of reactor-produced, gamma-emitting radionuclides. Naturally occurring K-40 was detected in 5 samples.

Semiannual composite samples were prepared from the monthly TMINS liquid discharge samples and then analyzed for the presence of Sr-89 and Sr-90. None of the 2001 semiannual composites contained Sr-89 or Sr-90 above the MDC.

Fish Results During 2001, fish samples were collected at one indicator and one control location in the spring (May and June) and fall (October and December). They included recreationally important predators (smallmouth and largemouth bass) and bottom feeders (carp).

All samples were analyzed for gamma emitting radionuclides, Sr-89, and Sr-90.

None of the fish samples collected in 2001 contained detectable levels of reactor produced, gamma-emitting radionuclides. As expected, naturally-occurring K-40 was detected in all fish samples. Indicator concentrations were similar to those measured in the controls.

All fish samples were analyzed for Sr-89 and Sr-90. Neither of these radioactive materials was detected above the MDC in any of the 2001 fish samples.

Sediment Results In June and October of 2001, routine REMP sediment samples were collected from three sites in the Susquehanna River. Control samples were collected from a location upstream of the TMINS liquid discharge outfall. Indicators were collected from two sites in the York Haven Pond (YHP) between TMINS liquid discharge outfall and the York Haven Dam (YHD). All samples were analyzed for gamma-emitting radionuclides.

Papge 37 Pa*e 37

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Naturally-occurring K-40, Ra-226 and Actinium-228 (Ac-228) as well as fallout and/or reactor-produced Cs-137 were identified in all indicator and control samples.

Additionally, the samples collected in June contained naturally-occurring Be-7. No other reactor-produced, gamma-emitting radionuclides were detected above the MDC.

Indicator Cs-137 concentrations ranged from 0.14 + 0.04 pCi/g (dry) to 0.20 +/- 0.06 pCi/g (dry) and averaged 0.15 +/- 0.06 pCi/g (dry).

Control sample concentrations were slightly lower, ranging from 0.068 + 0.025 pCi/g (dry) to 0.084 + 0.046 pCi/g (dry) and averaging 0.076 +/- 0.022 pCi/g (dry). For comparison, 2000 average Cs-137 concentrations were 0.17 +/- 0.08 pCi/g (dry) and 0.099 +/- 0.061 pCi/g (dry), for indicators and controls, respectively.

The sediment samples collected from Indicator Station J2-1, a location just upstream of the York Haven Dam, had the highest annual average Cs-137 concentration.

The concentrations ranged from 0.14 +/- 0.04 pCi/g (dry) to 0.20 +/- 0.06 pCi/g (dry) and averaged 0.17 +/- 0.09 pCi/g (dry).

As mentioned previously, Cs-137 is a fallout product of weapons testing as well as a constituent of TMINS liquid effluents. Since indicator sample concentrations were generally higher than those measured in 2001 control samples, it is reasonable to conclude that an increment of the Cs-137 detected in the indicator samples was due to TMINS operations. The presence of this material in the control samples indicated that a portion of the Cs-137 detected in the indicator samples also was due to fallout from prior atmospheric nuclear weapon tests.

Figure 11 depicts Cs-137 concentrations in river sediments from 1984 through 2001. As shown in this figure, no discernible buildup of Cs-137 occurred at indicator locations prior to and after 1995. This was primarily due to periodic scouring or removal of bottom sediments during high river flows.

A temporary buildup of Cs-137 in sediments was noted in 1995. This was caused by lower than normal river flows during the year and especially in the spring months when most scouring occurs. In 1996, the average Cs-137 concentrations in indicator samples trended downward. The reduction was due to releasing lower amounts of Cs-137 and having higher than average river flows which increase dilution of liquid effluents and promote scouring.

Based on the annual average concentration of Cs-137 in samples collected from Station J2-1, an estimate of the shoreline whole body dose to the maximally exposed individual was calculated. For this calculation, the annual average Cs-137 control concentration was subtracted to account for fallout Cs-137. The calculated whole body dose (0.0002 mrem/yr) was insignificant and a small percentage (0.00007%) of the whole body dose received by an individual from natural background radiation (300 mrem/yr).

Page 38 II ii

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 3 2001 Average Tritium Concentrations in Surface and Drinking Water (pCi/L)

Sample Concentrations > MDC (I Actual Sample Concentrations (2)

Station Description Average +/- 2 std dev Range Average +/- 2 std dev Range Surface Water Q9-1 (C)

Steelton Water Authority (Steelton, PA) 50 +/- 100

(-44) - 130 JI-2 (1)

West Shore of TMI 5000 +/- 20000 540 - 30000 4000 +/- 17000 10 - 30000 Drinking Water Q9-1 (C)

Steelton Water Authority (Steelton, PA) 20 + 100

(-75) - 100 G 15-2 (I)

Wrightsville Water Supply (Wrightsville, PA) 180 80 = 110

(-20)- 180 G15-3 (I)

Lancaster Water Authority (Columbia, PA) 310 +/- 230 220 -440 130 +/- 260

(-14) - 440 (1)

Averages and ranges are based on sample results above the minimum detectable concentration (MDC). Duplicate analysis results and quality control sample results are not included.

(2)

Averages and ranges are based on actual sample concentrations (whether positive, negative or zero). Negative sample concentrations are enclosed in parentheses.

Using actual sample concentrations (sample count rate minus background or blank count rate) to calculate annual averages eliminates biases such as those caused by averaging only sample concentrations above the MDC. Negative sample concentrations are important to the overall average, but have no physical significance.

Duplicate analysis results and quality control sample results are not included.

(I) = Indicator Station (C) = Control Station Page 39

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 4 2001 Average Gross Beta Concentrations in Drinking Water (pCi/L)

Sample Concentrations > MDC (

Actual Sample Concentrations (2)

Station Description Average +/- 2 std dev Range Average +/- 2 std dev Range Q9-1 (C)

Steelton Water Authority (Steelton, PA) 1.9 +/- 0.7 1.4 - 2.4 1.7 +/- 0.9 0.96 - 2.4 G15-2 (I)

Wrightsville Water Supply (Wrightsville, PA) 3.0 +/- 0.9 2.3 -3.7 3.0 +/- 0.9 2.3 -3.7 G15-3 (I)

Lancaster Water Authority (Columbia, PA) 2.5 + 1.1 1.6 - 3.4 2.5 +/- 1.1 1.6 - 3.4

"(

Averages and ranges are based on sample results above the minimum detectable concentration (MDC). Duplicate analysis results and quality control sample results are not included.

(2)

Averages and ranges are based on actual sample concentrations (whether positive, negative or zero). Negative sample concentrations are enclosed in parentheses.

Using actual sample concentrations (sample count rate minus background or blank count rate) to calculate annual averages eliminates biases such as those caused by averaging only sample concentrations above the MDC. Negative sample concentrations are important to the overall average, but have no physical significance. Duplicate analysis results and quality control sample results are not included.

(1) = Indicator Station (C) = Control Station Page 40

2001 Tritium Concentrations in Surface Water Picocuries per Liter by Month NOTE: Actual sample concentrations (positive, negative, zero) were plotted.

100000....

10000 1000 100 0 Station JA-2 (Downstream of Discharge)

Jul Aug Month of 2001 NOTE: Actual sample concentrations (positive, negative, zero) were plotted.

100000

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Page 41

Historical Tritium Concentrations in Surface Water Picocuries per Liter by Quarter Indicator Samples

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I 0 0 Co Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 June 1974 September 1974 TMI-2 Critical March 1978 September 1976 November 1976 TM I-2 Accident M arch 1979 September 1977 M arch 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 TMI-1 Restart October 1985 Chernobyl April 1986 NOTE: Prior to 1996, only sample concentrations > MDC were plotted. Beginning in 1996, actual sample concentrations (positive, negative, zero) were plotted.

I

-*--44T_~

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4000 3000 2000 1000-0 I Page 42

2001 Tritium Concentrations in Drinking Water Picocuries per Liter by Month NOTE: Actual sample concentrations (positive, negative, zero) were plotted.

QUU 400 300 200 100 0

-100 El Indicator Samples Tl Control Samples Jun Jul Month of 2001 NOTE: Actual sample concentrations (positive, negative, zero) were plotted.

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Jan Feb Mar Apr May Jun Jul Month of 2001 Aug Sep 0

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Jan Feb Mar Apr May Aug Sep Oct Nov

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2001 Gross Beta Concentrations in Drinking Water Picocuries per Liter by Month Ei Indicator Samples M, Control Samples 10 NOTE: Actual sample concentrations (positive, negative, zero) were plotted.

. 9 4

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-Mar Apr Jun Jul Aug N v D

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0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month of 2001 Figure 10 Page 44

Historical Cesium-137 Concentrations in Aquatic Sediments Picocuries per Gram (dry)

Figure 11 Page 45

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TERRESTRIAL MONITORING Radionuclides released to the atmosphere may deposit on soil and vegetation. They may eventually be incorporated into milk, meat, fruits, vegetables, or other food products. To assess the impact of TMINS operations to humans from the ingestion pathway, primary food product samples such as green leafy vegetables, root vegetables, fruits, grains and milk were collected and analyzed during 2001. The ingestion pathway also is normally assessed by collecting and analyzing deer meat samples. However, none were available in 2001.

In addition to edible products, rodent carcasses are normally analyzed as part of the TMI-2 Post Defueling Monitored Storage (PDMS) Rodent Collection and Analysis Program. The purpose of this program is to determine if radioactive materials have been transported by the movement of animals from radiologically-controlled areas to unrestricted areas. No rodent carcasses were available for analysis in 2001.

Page 46

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The radiological contribution of TMINS operations was determined by comparing the results of samples collected in prevalent downwind locations, primarily to the south and east of the site, with control samples collected from distant or generally upwind directions. Comparisons with results from previous years also were performed, as applicable.

The analytical results of samples collected during 2001 indicated that there was no discernible TMINS contribution to radioactivity levels in locally-produced food products. As expected, Sr-90 was found in milk and broad leaf vegetables. The concentrations observed in samples collected near TMINS (indicators) were similar to levels observed in samples collected from the distant sites (controls) and consistent with data from prior years. The presence of Sr-90 in both indicator and control samples was attributed to fallout from prior atmospheric nuclear weapon tests.

As part of the REMP, a surveillance was performed to identify relevant changes in the use of land (unrestricted areas) around TMI.

This land use surveillance consisted of a dairy census and a residence census. Sampling of broad leaf vegetation was performed in lieu of a garden census.

The dairy and residence censuses were performed to determine the location of the nearest milk animal and residence within five miles of TMINS in each of the sixteen meteorological sectors. The results of the 2001 dairy and residence censuses are listed in Tables E-1 and E-2 of Appendix E, respectively.

The results of these censuses provide a basis for modifying the radiological environmental monitoring program (REMP) and the model used for calculating offsite doses. Based on the 2001 land use surveillance, no changes to the REMP or the dose model were required.

Broad leaf vegetation sampling was performed in lieu of conducting a garden census. This sampling was performed in accordance with the requirements of the ODCM and in addition to collecting and analyzing edible terrestrial vegetation - fruits and vegetables.

Specifically, three different kinds of tree leaves were collected near the site boundary in the southeast (SE) and east-southeast (ESE) meteorological sectors and then analyzed for gamma-emitting radionuclides and Sr-90. These locations were sampled because they have the highest potential for impact. A control sample also was collected and analyzed.

None of the samples contained reactor produced gamma-emitting radionuclides above the minimum detectable concentrations (MDCs). Strontium-90 was detected in the control sample and in all but two indicator samples. Its presence was due to fallout from prior weapon tests because the control sample yielded a similar or higher Sr-90 concentration. The analysis results are listed in Table E-3 of Appendix E.

Sample Collection and Analysis During 2001, samples of raw cow milk were collected biweekly (January - November) and Page 47 I

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT monthly (December) from local farmers at one control and three indicator locations.

Indicator samples were collected at locations that have a high potential for impact by TMINS operations. These locations generally were proximate to TMINS and in dominant wind directions. Conversely, the control station was located greater than 10 miles from TMINS in a non-prevalent wind direction.

The samples collected at these sites should be unaffected by operations at TMINS.

A gamma isotopic analysis and a low-level 1-131 analysis were performed on each milk sample. The biweekly and monthly milk samples were then composited quarterly by station and analyzed for Sr-89 and Sr-90.

Edible terrestrial vegetation - fruits, grains, root vegetables and leafy vegetables - were collected when ripe from one indicator and one control garden. Maintained by environmental support personnel, the indicator garden was located at the TMINS Visitors Center (Station El-2). The control garden was located at Milton Hershey School (MHS). This garden was maintained by MHS students in cooperation with AmerGen.

Like indicator milk samples, indicator edible terrestrial vegetation samples were collected at a location having a high potential for impact by operations at TMINS. Controls samples were obtained from a distant site where they should be unaffected by TMINS operations.

Tomatoes, cabbages, red beets and sweet corn were collected in 2001. All samples were analyzed for gamma-emitting radionuclides, including 1-131. Cabbage samples also were analyzed for Sr-89 and Sr-90.

Deer meat samples are normally obtained and analyzed as part of the routine REMP.

However, none were available for analysis in 2001.

When available, a limited number of rodent carcasses are analyzed as part of the non routine REMP. During 2001, no carcasses were available for analysis.

Milk Results During 2001, 100 milk samples were collected and analyzed. Iodine-131 was not detected above the minimum detectable concentration (MDC) in any of the samples.

Gamma isotopic analyses yielded only naturally-occurring potassium-40 (K-40).

Potassium-40 was detected in all 2001 milk samples; the concentrations measured in the indicator samples were similar to those measured in the controls.

Strontium analyses were performed on 16 quarterly composite samples. None of the samples contained Sr-89 above the MDC. As expected, Sr-90 was measured in most of the milk samples. Eleven of twelve indicator samples (92%) and three of four control samples (75%) contained Sr-90 above the MDC.

Strontium-90 concentrations in the indicator samples ranged from 0.54 +/- 0.29 pCi/L to 2.0

+/- 0.5 pCi/L and averaged 1.1 +/- 0.9 pCi/L.

Similarly, the concentrations measured in the control samples ranged from 0.76 +/- 0.36 pCi/L to 2.2 +/- 0.5 pCi/L and averaged 1.3 +/-

Page 48

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1.5 pCi/L. The Sr-90 concentrations measured in 2001 milk samples were consistent with those measured in 2000 when indicator and control sample concentrations averaged 1.2 +/- 0.4 pCi/L and 1.2 +/- 0.2 pCiIL, respectively.

The milk collected from Indicator Station D2-1, the dairy farm located 1.1 miles east northeast of TMINS, contained the highest annual average Sr-90 concentration.

Strontium-90 above the MDC was detected in three of the four quarterly composite samples.

The average Sr-90 concentration was 1.6 +/-

0.9 pCi/L. Milk samples collected in 2001 from the other farms had similar Sr-90 concentrations. Additionally, the milk samples collected in previous years from this and other dairy farms contained similar Sr-90 concentrations.

The results indicated that the Sr-90 measured in the 2001 milk samples was unrelated to operations at TMINS. Its presence in this medium was primarily due to the transfer of this long-lived fallout product from soil to animal feed (fresh or stored) to cow to milk.

Figure 12 depicts the trends of Sr-90 concentrations in indicator and control cow milk samples since 1979. The data plotted for 1996 through 2001 were based on actual sample concentrations because some of the results were below the MDC. Using actual concentrations eliminates biases in the data and missing data points on graphs.

As shown on Figure 12, the Sr-90 concentrations have trended downward. This decrease is directly related to the cessation of atmospheric nuclear weapon testing and the radioactive decay and depletion of both atmospheric and terrestrial Sr-90 associated with prior weapon testing.

Edible Terrestrial Vegetation Results A total of eight edible terrestrial vegetation samples - leafy vegetables (cabbages), root vegetables (red beets), fruits (tomatoes) and grains (sweet corn) - were collected and analyzed in 2001. Naturally-occurring K-40 was measured in all edible terrestrial vegetation samples. Indicator concentrations were similar to controls. No gamma-emitting radionuclides (including 1-131) attributable to TMINS operations were detected above the MDC.

Strontium may be incorporated into plants by either uptake from soil or direct deposition on foliar surfaces. In 2001, none of the leafy vegetables (cabbages) contained Sr-89 above the MDC. Low-level Sr-90 was detected above the MDC in both the indicator sample and the control sample. The measured concentrations were 0.0024 +/- 0.0012 pCi/g (wet) and 0.0015 +/- 0.0008 pCi/g (wet),

respectively. Similar Sr-90 concentrations were detected in previous years. For example, the 2000 indicator cabbage sample contained Sr-90 at a concentration of 0.0046

+/- 0.00 19 pCi/g (wet). This radionuclide also was measured in the 2000 control sample at a concentration of 0.0049 +/- 0.0019 pCi/g (wet).

As in previous years, the data indicated that the Sr-90 measured in the 2001 cabbage samples was attributed to fallout from prior nuclear weapon tests and, therefore, was Page 49

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT unrelated to operations at TMINS. The detection of Sr-90 was not unexpected because measurable amounts of this long lived fallout product are still present in the terrestrial environment. Additionally, cabbages have a tendency to absorb Sr-90 residing in the soil.

Deer Meat Results Deer meat samples are normally obtained via local hunters and/or road-kills and analyzed as part of the routine REMP. During 2001, however, no deer meat samples were available for analysis.

Rodent Results No rodent carcasses were available for analysis in 2001. Previous data suggest that rodents are not transporting radioactive materials to unrestricted areas.

A pest control program is in place at TMINS.

This program minimizes the potential for rodents to transport radioactive materials to unrestricted areas.

Page 50

Historical Strontium-90 Concentrations in Cow Milk Picocuries per Liter by Quarter Indicator Samples

--- Control Samples Quarter & Year Figure 12 Page 51 10 9

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2 1

0

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT GROUNDWATER MONITORING Three Mile Island (TMI) is located in the Triassic lowland of Pennsylvania, a region often referred to as the Gettysburg Basin. The Island was formed as a result of fluvial deposition by the Susquehanna River.

It is composed of sub-rounded to rounded sand and gravel, containing varying amounts of silt and clay.

Soil depths on TMI vary from approximately six feet at the south end to about 30 feet at the center. The site is underlain by Gettysburg shale that lies at an elevation of approximately 277 feet (Refs. 38 and 39).

The Island has two different water-bearing zones.

One is composed of the soils overlying the Gettysburg shale (bedrock). The other is the bedrock. Relative to the natural soils, the movement of groundwater is much quicker in the bedrock. Groundwater from TML migrates to the Susquehanna River, but does not impact onshore groundwater supplies. The migration of TMI groundwater to onshore supplies is prevented by the higher levels and the opposing flows of groundwater that exist beneath the surrounding terrain on the opposite sides of the Susquehanna River. The estimated travel time for groundwater to reach the river from the central portion of TMI is approximately 12 years (Ref. 40).

Page 52

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT A groundwater monitoring program (GMP) was initiated in 1980 to detect leakage of water, if any, from the TMI-2 Reactor and Auxiliary Buildings and outside storage tanks. Since 1980, the TMINS GMP has been expanded and now monitors activities associated with both TMI-1 and TMI-2.

During 2001, most of the onsite groundwater samples contained H-3 above the minimum detectable concentration (MDC). The presence of H-3 in these samples was attributed primarily to routine TMI-1 operations and previous TMI-2 operations.

Additionally, pipe leaks that were previously identified and repaired contributed to elevated levels of H-3 in certain onsite wells. The pipes continue to be monitored.

Tritium above the MDC was not detected in any of the offsite groundwater samples.

However, H-3 was detected in all onsite storm water samples (4 of 4). Its presence was due primarily routine TMI-1 operations and, to a lesser extent, natural production in the atmosphere and fallout from prior nuclear weapon tests.

All H-3 concentrations measured in the groundwater collected from the onsite stations were below the USNRC 10 CFR 20 effluent concentration limit. Additionally, the onsite groundwater used for drinking contained H-3 at concentrations that were well below the USEPA Primary Drinking Water Standard of 20,000 pCi/L.

None of the groundwater samples collected in 2001 contained gamma-emitting radionuclides related to TMINS operations.

The same can be said for storm water and sediment collected from Station EDCB.

Additionally, Sr-90 was not identified in any of the groundwater samples collected in 2001.

The 2001 TMINS GMP results indicated that the concentrations of radioactive materials measured in onsite and offsite groundwater were too low to have a significant adverse impact on humans or the environment.

As part of the TMINS Groundwater Protection Plan, an aboveground tank monitoring program (ATMP) was established in 1997. The purpose of the program is to detect tank or component leakage at an early stage so that impacts to the local environment, such as soil and groundwater, can be minimized.

In 2001, three aboveground tanks were monitored. Monitoring was performed by collecting and analyzing groundwater samples from wells proximal to the tanks. No discernible tank or component leakage was identified in 2001.

Sample Collection and Analysis Only one minor change was made to the TMINS GMP in 2001. The change is discussed in Appendix C.

Groundwater from 20 onsite and 2 offsite stations were sampled in 2001. Of the 20 onsite, groundwater stations, 14 were monitoring wells (MS-1, MS-2, MS-4, MS-5, MS-7, MS-8, MS-19, MS-20, MS-21, MS-22, OS-14, OS-18 and RW-1 and RW-2), 2 were drinking water wells (OSF and 48S) and 3 were industrial wells (NW-A, NW-B and NW-C).

Page 53 L

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The other onsite, groundwater station was the TMINS Pretreatment Building clearwell (NW-CW). Added in 1997, the clearwell is a holding tank for the water pumped from the three industrial wells.

Both offsite stations (El-2 and N2-1) were drinking water wells. Storm water and sediment were sampled in 2001 from one onsite station (EDCB).

The locations of the onsite groundwater stations sampled in 2001 are shown on Figures G-1 and G-2 (Appendix G). Figure G-2 also shows the location of Station EDCB.

The offsite groundwater stations are depicted on Figures 1 and 2 (Radiological Environmental Monitoring).

All groundwater samples were collected using standard plumbing, a dedicated, in-well pumping system or a bailing device. The groundwater stations were sampled weekly, monthly, quarterly, semiannually or annually.

Storm water and sediment from Station EDCB were collected monthly and annually, respectively.

All groundwater samples collected in 2001 were analyzed for H-3. Some of these samples were analyzed individually for gamma-emitting radionuclides and some were combined into annual composites and analyzed for gamma-emitting radionuclides and/or Sr-90.

The monthly storm water samples collected from Station EDCB were combined into quarterly samples and analyzed for H-3 and gamma-emitting radionuclides. The annual sediment sample collected from this station was analyzed for gamma-emitting radionuclides.

Groundwater Results During 2001, H-3 was the only radionuclide detected in samples collected from the onsite monitoring wells, the industrial wells and the clearwell. The results are summarized in Table G-1 of Appendix G. For comparison, Table G-1 also includes 2000 station averages. The presence of H-3 in the samples was attributed primarily to routine operations at TMI-1 and past operations at TMI-2.

Additionally, pipe leaks previously identified and repaired were the source of H-3 in a few of the onsite groundwater samples. The pipes continue to be monitored and, to date, results indicate that repairs were successful.

Generally, the H-3 concentrations measured in most onsite monitoring well samples remained the same or trended downward in 2001. The highest H-3 concentrations were measured in the onsite groundwater samples collected from Stations OS-18, NW-A, NW-B, NW-C, NW-CW, MS-2, MS-4, MS-19, MS-21 and RW-2.

In August of 1998, Station OS-18 was added to the TMINS GMP to monitor the integrity of two nearby pipes that transport water containing radioactive materials, including H-3. The 1998 and 1999 OS-18 H-3 concentrations were higher than expected and, consequently, a test to determine the integrity of the pipes was initiated. In 1999, one of the pipes was found to be leaking and was repaired. The pipe was returned to service following repairs.

Page 54 Pa*e 54

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The 2001 OS-18 H-3 concentrations averaged 730 +/- 730 pCi/L and ranged from 270 to 1,800 pCi/L. For comparison, the 2000 0S-18 H-3 concentrations averaged 4,000 +/-

14,000 pCi/L and ranged from 280 to 31,000 pCi/L. The decrease in H-3 concentrations from 2000 to 2001 indicated that the 1999 pipe repair was successful. Also, the 2001 data indicated that there were no leaks in the two nearby pipes.

Industrial Wells NW-A, NW-B and NW-C were installed in the latter part of 1995.

Sampling of these wells was initiated in 1996.

Beginning in June of 1997, water from the industrial wells was used to supply water to various TMI-1 systems. Prior to this period, the water used in these systems was obtained from the Susquehanna River.

The 2001 H-3 concentrations in water collected from NW-A averaged 1,000 + 500 pCi/L and ranged from 850 to 1,200 pCi/L.

Slightly higher, the 2000 concentrations averaged 1, 300 + 100 pCi/L and ranged from 1,300 to 1,400 pCi/L.

During 2001, the H-3 concentrations for NW-B were somewhat higher than NW-A, averaging 2,100 + 2,100 pCi/L and ranging from 1,400 to 2,900 pCi/L. For comparison, the 2000 NW-B concentrations averaged 2,900 + 1,600 pCi/L and ranged from 2,400 to 3,500 pCi/L.

The 2001 NW-C H-3 concentrations averaged 14,000 + 4,000 pCi/L and ranged from 12,000 to 15,000 pCi/L. For comparison, the 2000 H-3 concentrations averaged 18,000 +/- 4,000 pCi/L and ranged from 17,000 to 20,000 pCi/L.

The presence of H-3 in the water collected from the industrial wells was expected because the wells are located in an area that can be impacted by past TMI-2 operations.

A portion of the H-3 detected in the samples also was due to routine TMI-1 operations.

The magnitude of the H-3 concentrations measured in NW-C water, however, was higher than expected. The higher than expected results in NW-C suggested an additional source of H-3. This source is likely the pipe leak that affected OS-18 (discussed above).

The lower H-3 concentrations measured in 2001 industrial well water supported this hypothesis. Furthermore, the lower H-3 concentrations measured in 2001 industrial well water also supported the conclusion that the pipe was successfully repaired.

The H-3 concentrations measured in the samples collected from Stations MS-2, MS-4, MS-19, MS-21, RW-2 ranged from 190 pCi/L to 2400 pCi/L. The presence of H-3 in these samples was most likely due to past pipe leaks, routine airborne releases and/or routine maintenance of the fire service system which is supplied in part by the industrial wells.

All of the H-3 concentrations found in water collected from the onsite monitoring wells, the industrial wells and the clearwell were well below the USNRC 10 CFR 20 (Appendix B, Table 2) effluent concentration of 1,000,000 pCi/L.

Tritium also was measured in the water collected from the two onsite drinking water wells, Stations 48S and OSF. In 1997, the Page 55 V

I ii

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT well at Station 48S was established as the primary source for drinking water on TMINS.

To a lesser extent, water from the OSF well was used for drinking and occasionally was used to supply water for various TMI-1 plant systems.

In 2001, 4 of 4 samples collected from Station 48S contained H-3 above the minimum detectable concentration (MDC). The concentrations averaged 200 +/- 80 pCi/L and ranged from 160 to 240 pCi/L. The 2001 concentrations were consistent with those measured in 2000 (Table G-l).

The 2001 OSF H-3 concentrations (4 of 4) averaged 490 +/- 90 pCi/L and ranged from 420 to 520 pCi/L. As shown on Table G-1, the 2001 OSF concentrations were similar to those reported in 2000.

The H-3 detected in the 2001 onsite drinking water samples was attributed primarily to routine operations at TMI-I (e.g. routine airborne releases) and possibly past operations at TMI-2 (e.g. prior airborne releases from the TMI-2 Evaporator). A small portion of the H-3 detected in the onsite well water was attributed to natural production in the atmosphere and fallout from prior nuclear weapon tests. All of the H-3 concentrations detected in the onsite drinking water were a small fraction of the USEPA Primary Drinking Water Standard of 20,000 pCi/L.

A conservative dose estimate was performed assuming that a TMINS employee drank OSF water at the 2001 average H-3 concentration for one working year. The maximum hypothetical whole body dose was 0.009 mrem. This calculated dose is equivalent to 0.003% of the whole body dose that an individual living in the TMI area receives each year from natural background radiation (300 mrem).

Offsite groundwater samples were collected annually from two locations. Neither sample contained H-3 above the MDC.

Some of the 2000 groundwater samples (individual or composite) were analyzed for Sr-90 and/or gamma-emitting radionuclides.

None were found to contain detectable Sr-90 or gamma-emitting radionuclides related to TMINS operations.

Storm Water and EDCB Sediment Results Storm water from Station EDCB, an onsite collection basin, was collected monthly. The monthly samples were then combined into quarterly samples and analyzed for H-3 and gamma-emitting radionuclides.

No gamma-emitting radionuclides were detected. All samples contained H-3 above the MDC. The concentrations averaged 280 +/-

230 pCi/L and ranged from 200 to 450 pCi/L.

Similar H-3 concentrations were measured in 2000 (Table G-1). Since these concentrations were higher than those typically measured in control surface water, a portion of the H-3 detected in the 2000 storm water was attributed to routine operations at TMI-1 (e.g.

routine airborne releases). To a lesser extent, a portion of the H-3 was due to natural production in the atmosphere and fallout from prior nuclear weapon tests.

Page 56

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT A sediment sample from Station EDCB was collected in the fall and analyzed for gamma emitting radionuclides. Naturally-occurring K-40, Ra-226 and Ac-228 as well as fallout and/or reactor-produced Cs-137 were identified. No other reactor-produced, gamma-emitting radionuclides were detected above the MDC.

The Cs-137 concentration was 0.25 +/- 0.05 pCi/g (dry). Since control sediment samples have contained similar concentrations, the Cs-137 measured in the sample collected from Station EDCB was most likely due to fallout from previous weapon tests and not TMINS operations.

Page 57

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT RADIOLOGICAL IMPACT OF TMINS OPERATIONS An assessment of potential radiological impact indicated that radiation doses to the public from 2001 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2001 whole body dose potentially received by an assumed maximum exposed individual from TMI-1 and TMI-2 liquid and airborne effluents was conservatively calculated to be 0.2 mrem. This dose is equivalent to 0.07% of the dose that an individual living in the TMI area receives each year from natural background radiation.

The 2001 whole body dose to the surrounding population from TMI-1 and TMI-2 liquid and airborne effluents was calculated to be 11 person-rem. This is equivalent to 0.002% of the dose that the total population living within 50 miles of TML receives each year from natural background radiation.

Page 58

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Determination of Radiation Doses to the Public Dose assessments can be performed by using either effluent data and an environmental transport model or environmental sample data.

To the extent possible, doses to the public are based on the direct measurement of dose rates from external sources and the measurement of radionuclide concentrations in environmental media which may contribute to an internal dose of radiation. Thermoluminescent dosimeters (TLDs) positioned in the environment around TMINS provide measurements to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses.

The quantity of radioactive materials released during normal operations are typically too small to be measured once distributed in the offsite environment. Therefore, the potential offsite doses are more effectively calculated for TMINS operations using a computerized model that predicts concentrations of radioactive materials in the environment and subsequent radiation doses based on measured effluents. Another reason for using effluent data and a transport model is that environmental sampling data cannot provide enough information to calculate population doses.

Doses are calculated using an advanced "class A" dispersion model. This model incorporates the guidelines and methodology set forth by the USNRC in Regulatory Guide 1.109. Due to the conservative assumptions that are used in the model, the calculated doses are generally higher than the doses based on actual environmental sample concentrations.

Therefore, the model predicts doses that are higher than actual doses received by people.

The type and amount of radioactivity released from TMINS is calculated using measurements from effluent radiation instruments and effluent sample analyses. Once released, the dispersion of radionuclides in the environment is readily determined by computer modeling.

Airborne releases are diluted and carried away from the site by atmospheric diffusion which continuously acts to disperse radioactivity.

Variables that affect atmospheric dispersion include wind speed, temperature at different elevations, terrain, and shift in wind direction.

A weather station on the north end of TMI is linked to a computer terminal that permanently records the meteorological data.

Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Susquehanna River. Actual monthly Susquehanna River flows are obtained from FirstEnergy Corp. at the York Haven Hydroelectric Station.

The human exposure pathways also are included in the model and are depicted in Figure 13. The exposure pathways that are considered for the discharge of TMINS liquid effluents are consumption of drinking water and fish, and shoreline exposure. The exposure pathways considered for the discharge of TMINS airborne effluents are plume exposure, inhalation, cow milk consumption, goat milk consumption, fruit and vegetable consumption, meat consumption and land deposition.

Numerous data files are used in the calculations that describe the area around TMI Page 59

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT in terms of population distribution and foodstuffs production. Data files include such information as the distance from the plant stack to the site boundary in each sector, the population groupings, milk cows, milk goats, gardens of more than 500 square feet, meat animals, downstream drinking water users, and crop yields.

When determining the dose to humans, it is necessary to consider all applicable pathways and all exposed tissues, summing the dose from each to provide the total dose for each organ as well as the whole body from a given radionuclide. Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted and half-life. The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and GI tract).

Doses are calculated for what is termed the "maximum hypothetical individual". This individual is assumed to be affected by the combined maximum environmental concentrations wherever they occur.

For liquid releases, the maximum hypothetical individual would consume 193 gallons of Susquehanna River water per year from the first downstream drinking water supplier, eat 46 pounds of fish each year that reside in the plant discharge area and stand 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year on the shoreline influenced by the plant discharge.

For airborne releases, the maximum hypothetical individual would live at the location of highest radionuclide concentration for inhalation and direct plume exposure.

Additionally, this individual each year would consume 106 gallons of cow milk, 141 pounds of leafy vegetables, 1389 pounds of non-leafy vegetables and fruits and 243 pounds of meat produced at the locations with the highest predicted radionuclide concentrations.

Consumption of goat milk is not included, since this exposure pathway does not currently exist.

Doses to the population within 50 miles of TMI for airborne effluents and the entire population using Susquehanna River water downstream of the plant also are calculated.

Results of Dose Calculations The maximum hypothetical doses due to 2001 TMI-1 and TMI-2 liquid and airborne effluents are summarized in Tables 5 and 6. Table 5 compares the calculated maximum hypothetical individual doses to the USNRC 10 CFR 50 App. I guidelines. This table also compares the calculated doses (to an individual of the public) from effluents and direct radiation to USEPA 40 CFR 190 dose limits.

Table 6 presents the maximum hypothetical whole body doses to an individual and the total population from 2001 TMINS effluents (i.e.

TMI-1 and TMI-2 liquid and airborne effluents combined). For airborne releases, population doses are calculated for all people living within Page 60

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 50 miles of TMINS. For liquid releases, population doses are calculated for all people using Susquehanna River water downstream of TMINS. The maximum individual and population whole body doses presented in Table 6 are compared to the doses received from natural background radiation.

As shown in Table 5, the doses calculated for 2001 operations at TMINS were well below the Federal dose limits (USEPA 40 CFR 190) and the guidelines of USNRC 10 CFR 50 App. 1. This conclusion was supported by radionuclide concentrations detected in actual environmental samples.

Doses from natural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents. Natural background radiation from cosmic, terrestrial and natural radionuclides in the human body (not including radon),

averages about 100 mrem/yr (Ref. 31).

Additionally, the average individual living in the United States receives an annual dose of about 2,400 mrem to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole (or total) body dose of 200 mrem (Ref. 31). Therefore, the average person in the United States receives a whole body dose of about 300 mrem/yr from natural background radiation sources.

As shown on Table 6, the maximum hypothetical whole body dose received by an individual from 2001 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.2 mrem.

This dose is equivalent to 0.07 percent of the dose that an individual living in the TMI area receives each year from natural background radiation (300 mrem).

The maximum hypothetical whole body dose to the surrounding population from all 2001 TMI-1 and TMI-2 liquid and airborne effluents was calculated to be 11 person-rem. This dose is equivalent to 0.002 percent of the whole body dose that the total population in the TMI area receives each year from natural background radiation.

The low doses calculated for 2001 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, 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 2001 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, TMI-NS operations in 2001 did not have any adverse effects on the health of the public or on the environment.

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 5 Calculated Maximum Hypothetical Doses to an Individual from 2001 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Guidelines (mrem/yr)

Calculated Dose (mrem/yr)

TMI-1 TMI-2 From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases)

From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ 0.2 0.2

< 0.01

<0.01

<0.01 0*

0.01

<0.01

No noble gases were released from TMI-2.

USEPA 40 CFR 190 Limits (mrem/yr) 75 thyroid 25 total body or other organs Total from Site Calculated Dose (mrem/yr)

TMI-1 and TMI-2 Combined**

0.3

,0.5

*This sums together TMI-1 and TMI-2 maximum doses regardless of age group for different pathways.

The combined doses include those due to radioactive effluents and direct radiation from TMINS. The direct radiation dose is calculated from environmental TLD data. For this calculation, exposure is assumed to be equal to dose.

The direct radiation dose from 2001 TMINS operations was 0.2 mrem. This dose was based on a maximum net fence-line exposure rate of 3 mR/std month and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-1 and TMI-2 effluents (0.3 mrem) and the dose from direct radiation (0.2 mrem) yielded a maximum hypothetical dose of 0.5 mrem.

Paae 62 Pa*e g9

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 6 Calculated Whole Body Doses to the Maximum Individual and the Population from 2001 T.-4I-1 and TMI-2 Liquid and Airborne Effluents From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases)

From Radionuclides In Airborne Releases (lodines, Tritium and Particulates)

No noble gases were released from TMI-2.

Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-1 TMI-2 0.2

< 0.01

<0.01 0*

0.01

< 0.01 Individual Whole Body Dose Due to TMI-I and TMI-2 Operations:

0.2 mrem/yr Individual Whole Body Dose Due to Natural Background Radiation:

300 mrem/yr From Radionuclides In Liquid Releases (Downstream Susquehanna River Water Users)

From Radionuclides In Airborne Releases (Population within 50 Mile Radius of TMINS)

Calculated Population Whole Body Dose (person-rem/yr)

TMI-1 TMI-2 10

<0.1 0.5

<0.1 IJ Population Whole Body Dose Due to TMI-1 and TMI-2 Operations:

11 person-rem/yr Population Whole Body Dose Due to Natural Background Radiation: 660,000 person-rem/yr Page 63

Figure 13 Exposure Pathways For Radionuclides Routinely Released From TMINS PREDOMINANT RADIONUCLIDES NOBLE GASES (Xe,Kr)

Plume exposure RADIOIODINES (1-131, 1-133)

Inhalation and consumption of milk, water, fruits, and vegetables RADIOSTRONTIUMS (Sr-89, Sr-90)

Consumption of milk, meat, fruits, and vegetables ACTIVATION PRODUCTS (Co-60, Mn-54)

Shoreline exposure RADIOCESIUMS (Cs-134, Cs-137)

Shoreline exposure and consumption of milk, meat, fish, water, fruits, and vegetables TRITIUM (H-3)

Inhalation and consumption of water, milk, fruits, and vegetables Page 64

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT REFERENCES

1. Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.

2. Three Mile Island Nuclear Station, Unit 2, PDMS Technical Specifications, DPR 73.

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RMC-TR-75-17, January 1975.

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2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

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Teledyne Isotopes. "Metropolitan Edison Company, Radiological Environmental Monitoring Report, 1978 Annual Report." IWL-5590-443.

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May 2000.

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31. National Council on Radiation Protection and Measurements. Report No. 93. "Ionizing Radiation Exposure of the Population of the United States."

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McBride. "Performance Testing of the Environmental TLD System for the Three Mile Island Nuclear Station." Health Physics Vol. 46, No. 5 (May), pp. 1013 - 1020, 1984.

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May 2000.

Page 67 Page 67

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX A 2001 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions Page Al

2001 RADIOLOGILAL ENVIRONMENTAL MONITORING REPORT TABLE A-1 TMINS Radiological Environmental Monitoring Program Sample Locations - 2001 Sample Medium AQS ID AP,AI,ID SW ID ID ID ID ID ID ID FP ID ID ID ID ID AQF GAD ID ID M

ID ID ID AP,AI,ID,GW,FP ID M

ID ID ID ID Station Code Al-3 Ai-4 A3-1 A3-2 A5-1 A9-3 BI-1 BI-2 B2-1 B5-1 BI0-1 BIQ-2 Cl-I C1-2 C2-1 C5-1 C8-I Control Control DI-1 DI-2 D2-l D2-2 D6-l DI5-1 El-2 El-4 E2-2 E2-3 E5-1 E7-1 Fl-1 Map Number 16 113 39 40 44 127 2

114 132 45 61 1

17 116 43 46 62 3

18 29 133 47 80 19 117 109 134 48 64 20 Distance*

Azimuth 0.5 mi 0.3 2.6 2.5 4.3 8.1 0.6 0.4 1.9 4.8 9.4 10.1 0.7 0.3 1.6 4.5 7.2 0.2 0.6 1.1 1.7 5.2 10.9 0.4 0.2 1.1 1.9 4.6 6.8 0.5

0.

5 358 355 3

3 25 26 16 18 21 28 35 54 48 42 48 74 60 65 73 65 63 95 98 93 96 81 86 117 Description "N

of site offnorth tip of TMI in Susquehanna River "N

of Reactor Building on W fence adjacent to North Weather Station, TMI "N

of site at Mill Street Substation "N

of site at Swatara Creek, Middletown "N

of site on Vine Street Exit off Route 283 "N

of site at Duke Street Pumping Station, Hummelstown NNE of site on light pole in middle of North Bridge, TMI NNE of Reactor Building on top of dike, TMI NNE of site on Sunset Dr. (offHillsdale Rd.)

NNE of site at intersection of School House and Miller Roads NNE of site at intersection of West Areba Avenue and Mill Street, Hershey NNE of site at Milton Hershey School, Hershey NE of site along Route 441 N NE of Reactor Building on top of dike, TMI NE of site at Middletown Junction NE of site on Kennedy Lane NE of site at Schenk's Church on School House Road All locations where finfish are collected upstream of the TMiNS liquid discharge outfall (above Dock St. Dam, Harrisburg) are grouped together and referred to as "control" All locations greater than 10 miles from TMINS ENE of Reactor Building on top of dike, TM!

ENE of site on Laurel Road ENE of site at farm on Gingrich Road ENE of site along Hillsdale Rd. (S of Zion Rd.)

ENE of site offBeagle Road ENE of site along Route 241, Lawn, PA E of site at TMI Visitor's Center E of Reactor Building on top of dike, TMI E of site at farm on Pecks Road E of site along Hillsdale Rd. (N of Creek Rd.)

E of site at intersection of North Market Street (Route 230) and Zeager Road E of site along Hummelstown Street, Elizabethtown ESE of site near entrance to 500 kV Substation Page A2 K-

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-1 (Continued)

TMINS Radiological Environmental Monitoring Program Sample Locations - 2001 Sample Station Map Medium Code Number Distance*

Azimuth Description ID F1-2 118 0.2 mi 109° ESE of Reactor Building on top of dike midway within Interim Solid Waste Staging Facility, TMI AP,AI FI-3 149 0.6 105 ESE'ofsite in 500 kV Substation ID F1-4 154 0.3 115 ESE ofReactor Building on top ofdike, TMI ID F2-1 135 1.2 120 ESE of site along Engle Road ID F5-1 49 4.7 107 ESE of site along Amosite Road ID F10-1 66 9.4 112 ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 82 21.1 113 ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 22 0.6 143 SE ofsite along Route 441 S ID G1-3 119 0.3 129 SE of Reactor Building on top of dike, TMI ID GI-5 139 0.3 144 SE of Reactor Building on top of dike, TMI ID GI-6 140 0.3 141 SE of Reactor Building on top of dike, TMI AI,AP,M G2-1 104 1.4 125 SE of site at farm on Becker Road ID G2-4 136 1.7 135 SE of site on Becker Road ID G5-1 50 4.8 131 SE of site at intersection of Bainbridge and Risser Roads ID G10-I 67 9.8 127 SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 84 14.4 124 SE of site at Columbia Water Treatment Plant SW G15-2 85 13.6 128 SE of site at Wrightsville Water Treatment Plant SW G15-3 86 14.8 124 SE of site at Lancaster Water Treatment Plant ID HI-I 5

0.5 167 SSE of site, TMI AP,AI,ID H3-1 41 2.3 159 SSE of site in Falmouth-Collins Substation ID H5-1 52 4.1 157 SSE of site by Guard Shack at Brunner Island Steam Electric Station ID H8-1 68 7.4 163 SSE of site along Saginaw Road, Starview ID H15-1 87 13.2 157 SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills AQF Indicator All locations where finfish are collected downstream of the TMINS liquid discharge outfall are grouped together and referred to as "indicator" GAD Indicator All locations within ten miles of TMINS ROD Indicator All locations where rodents are collected within the owner controlled area, TMI ID Jl-I 6

0.8 184 S of site, TMI SW J1-2 23 0.5 188 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River ID J1-3 121 0.3 189 S of Reactor Building on wooden post of Building 221, just S of Unit 2 Admin. Building, TMI AQS J2-1 31 1.5 182 S of site in Susquehanna River just upstream of the York Haven Dam ID J3-1 141 2.7 178 S ofsite at York Haven/Cly ID J5-1 53 4.9 182 S of site along Canal Road, Conewago Heights Page A3

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-1 (Continued)

TMINS Radiological Environmental Monitoring Program Sample Locations - 2001 Sample Station Map Medium Code Number Distance*

Azimuth Description ID J7-1 69 6.5 mi 1770 S of site off of Maple Street, Manchester ID J15-1 88 12.6 180 S of site in Met-Ed York Load Dispatch Station EW KI-I 7

0.2 209 On site at RML-7 Main Station Discharge Building AQS Ki-3 24 0.3 202 SSW of site in Susquehanna River ID KI-4 123 0.2 208 SSW of Reactor Building on top of dike behind Warehouse 2, TMI ID K2-1 32 1.1 200 SSW of site on S Shelley Island ID K3-1 142 2.1 202 SSW of site along Rt. 262, N of Cly ID K5-1 54 5.0 200 SSW of site along Conewago Creek Road, Strinestown ID K8-1 70 7.4 196 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View ID K15-1 90 12.7 204 SSW of site on the Bird's Nest Child Care Center Building, Weiglestown M

KI5-3 151 14.5 205 SSW of site at farm along S Salem Church Rd, Dover ID LI-I 9

0.1 235 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI ID LI-2 26 0.5 221 SW of site on Beech Island ID L2-1 33 1.9 227 SW of site along Route 262 ID L5-I 55 4.1 228 SW of site at intersection of Stevens and Wilson Roads ID L8-1 71 8.0 225 SW of site along Rohlers Church Rd., Andersontown ID L15-1 91 11.7 225 SW of site on W side of Route 74, rear of church, Mt. Royal ID MI-i 129 0.1 249 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI ID MI-2 143 0.5 241 WSW of site on W side of unnamed island between N tip of Beech Island and Shelley Island AP,AI,ID M2-1 34 1.3 253 WSW of site adjacent to Fishing Creek, Goldsboro ID M5-1 56 4.3 249 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown ID M9-1 72 8.6 242 WSW of site along Alpine Road, Maytown ID NI-i 10 0.7 270 W of site on Shelley Island ID NI-3 124 0.1 270 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI ID,GW N2-1 35 1.2 262 W of site at Goldsboro Marina ID N5-1 57 4.9 268 W of site off of Old York Road along Robin Hood Drive ID N8-1 73 7.8 260 W of site along Route 382, 1/2 mile north of Lewisberry ID NI 5-2 95 10.4 274 W of site at intersection of Lisbum Road and Main Street, Lisburn ID PI-i 12 0.4 293 WNW of site on Shelley Island ID P1-2 38 0.2 290 WNW of Reactor Building on fence N of Unit I Screenhouse, TMI ID P2-I 36 1.9 283 WNW of site along Route 262 ID P5-1 58 4.9 285 WNW of site at intersection of Valley Road (Route 262) and Beinhower Road Page A4

I I

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-1 (Continued)

TMINS Radiological Environmental Monitoring Program Sample Locations - 2001 Sample Station Map Medium Code Number Distance*

Azimuth Description ID P8-1 74 8.0 292 WNW of site along Evergreen Road, Reesers Summit ID Q1-1 13 0.5 317 NW of site on Shelley Island ID QI-2 125 0.2 3i8 NW of Reactor Building on fence W of Warehouse 1, TMI ID Q2-1 37 1.8 310 NW of site along access road along river ID Q5-1 59 5.0 318 NW of site along Lumber Street, Highspire SW,ID Q9-1 76 8.5 308 NW of site at the Steelton Water Company AP,AI,ID Q15-1 97 13.5 305 NW of site behind West Fairview Fire Dept. Social Hall ID RI-I 14 0.2 335 NNW of Reactor Building along W fence, TMI ID R1-2 27 0.7 332 NNW of site on Henry Island ID R3-1 107 2.6 338 NNW of site at Crawford Station, Middletown ID R5-1 60 4.9 339 NNW of site at interstection of Spring Garden Drive and Route 441 ID R9-1 77 8.1 340 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights ID R15-1 99 11.2 330 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY ID = Immersion Dose (TLD)

GW

= Ground Water (offsite)

AQF = Finfish SW = Surface Water AQS

= Aquatic Sediment AT

= Air Iodine M

= Milk (Cow)

EW

= Effluent Water FP

= Food Products (Green Leafy Vegetation, Fruits, Vegetables)

AP = Air Particulate GAD = Meat (Game)

ROD = Rodents

All distances are measured from a point that is midway between the reactor buildings of TMI-I and TMI-2.

Page A5

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-2 Synopsis of the 2001 TMINS REMP(')

Discharge Water Fruits Grains Broad Leaf Vegetables Vegetables Groundwater Dosimeters (TLD)(4) 2 2

2 2

3 11 7

90 Weekly Weekly Semiannually 3

Semiannually 1 (6)

Annually Weekly Biweekly Annually Annually Annually Annually Weekly Quarterly Semiannually Annually Quarterly Milk 4

Biweekly Monthly Type of Analysis 364 1-131 364 Gr-Beta Gamma 8

Gamma Sr-89 Sr-90 6

Gamma I

Gamma 4

Gamma 24 Gr-Beta H-3 1-131 Sr-89 Sr-90 2

Gamma 2

Gamma Sr-89 Sr-90 2

Gamma 52 12 22 7

H-3 H-3 H-3 H-3 Gamma Gamma Sr-90 2160 Immersion Dose 96 Gamma 4

Gamma 1-131 1-131 Sr-89 Sr-90 Number of Collection Samples Frequency*

Collected Number of Sampling Locations 7

7 2

Sample Type Air Iodine Air Particulate Fish Aquatic Sediment Analysis Frequency(2 )

Weekly Weekly Quarterly Semiannually Semiannually Semiannually Semiannually Annually Monthly Monthly Monthly Monthly Semiannually Semiannually Annually Annually Annually Annually Annually Annually Weekly Quarterly Semiannually Annually Quarterly Annually Annually Quarterly Number of Samples Analyzedo 3

362 362 28 8

8 8

6 1 12 12 12 12 2

2 2

2 52 12 22 7

8 10 6

2107(5)

Biweekly Monthly Biweekly Monthly Quarterly Quarterly 96 4

96 4

16 16 Page A6

- I j

I j

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-2 Synopsis of the 2001 TMINS REMV) 1*

Number of Collection Samples Frequency(')

Collected Storm Water Surface/Drinking Water Deer Meat Monthly Weekly Biweekly 6

2 Rodent (1)

(2)

(3)

(4)

(5)

(6)

When Available When Available 12 Gamma H-3 24 Gamma 144 Gr-Beta H-3 1-131 0

Gamma 0

Radiological Frisk or Gamma Quarterly Quarterly Monthly Monthly Monthly Monthly 4

4 60 36 60 48 When Available When Available 0

0 This table presents a synopsis of the primary program only. It does not include the quality control (QC) program.

Weekly means once per week, biweekly means once every two weeks, monthly means once per month, quarterly means once per three months, semiannually means once every six months and annually means once per year.

The total number of analyses does not include duplicate analyses, recounts, or reanalyses.

A thermoluminescent dosimeter (TLD) is considered to be an element.

This is the total number of elements (TLDs) used for data analysis.

This is the sample collected from Station EDCB.

P~vye~ A7 Sample Type Number of Sampling Locations Type of Analysis Analysis Frequencyt 2)

Number of Samples AnalyzedO)

Pa-A7 I

I 2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-3 Sampling and Analysis Exceptions 2001*

Period of Deviation 12/27/00 - 01/10/01 01/10/01 - 01/24/01 01/31/01 - 02/14/01 02/14/01 - 02/28/01 02/28/01 - 03/14/01 08/08/01 - 08/22/01 08/29/01 - 09/12/01 Description of Deviation and Corrective Action Hourly aliquots were not collected by the automatic sampler at surface water station J1 -2 (West Shore of TMI) due to a frozen sample line.

Grab samples were obtained on 12/29/00, 1/3/01, 1/5/01 and 1/10/01 to represent the collection period.

For the period of 01/10/01 - 01/17/01, hourly aliquots were not collected by the automatic sampler at surface water station J 1-2 (West Shore of TMI) due to a frozen sample line. Grab samples were obtained on 01/12/01 and 01/17/01 and combined with the 01/17/01 01/24/01 composite (sample) to represent the collection period.

Several hourly aliquots were not collected by the automatic sampler at surface water station J1 -2 (West Shore of TMI) due most likely to a frozen sample line. A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Several hourly aliquots were not collected by the automatic sampler at surface water station J1-2 (West Shore of TMI) due most likely to a frozen sample line. A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Several hourly aliquots were not collected by the automatic sampler at surface water station J 1-2 (West Shore of TMJ) due most likely to a frozen sample line. A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Numerous hourly aliquots were not collected by the automatic sampler at surface water station Q9-1 (Steelton Water Authority) because the sampler was inadvertently turned off. A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

An undetermined number of hourly aliquots were not collected by the automatic sampler at drinking water station Q9-1 (Steelton Water Authority) because the "pump jammed". A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Page A8 1.

1.

i I

I

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-3 (Continued)

Sampling and Analysis Exceptions 2001*

Period of Deviation 09/26/01 - 10/10/01 10/10/01 - 10/24/01 10/24/01 - 10/31/01 10/31/01 - 11/14/01 Description of Deviation and Corrective Action Numerous hourly aliquots were not collected by the automatic sampler at drinking water station Q9-1 (Steelton Water Authority) because the "pump jammed". A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Numerous hourly aliquots were not collected by the automatic sampler at drinking water station Q9-1 (Steelton Water Authority) because the "pump jammed". A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Numerous hourly aliquots were not collected by the automatic sampler at surface water station J1-2 (West Shore of TMI) due to strong winds which created waves and exposed the sample line. A grab sample was not collected because the sampler collected a sufficient amount of water for analysis.

Numerous hourly aliquots were not collected by the automatic sampler at drinking water station Q9-1 (Steelton Water Authority) because the "pump jammed". A grab sample was not collected because the sampler collected a sufficient amount of water for analysis. The sampler was replaced on 11/19/01.

The exceptions described in this table are those that are considered to be deviations from the monitoring requirements listed in the Technical Specifications and the ODCM. Other sampling and analysis deviations occurred during the year. They were not included in this table because the minimum number of samples were collected and analyzed. Reports describing all sampling and analysis exceptions are on file.

Page A9

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT "APPENDIX B 2001 Lower Limit of Detection (LLD)

Exceptions Paize Bi Pa*e B1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE B Analytical Results Which Failed to Meet the USNRC Required LLD During 2001*

During 2001, all analysis results achieved the lower limits of detection (LLDs) required by the USNRC. The USNRC-required LLDs are listed in the TMINS ODCM.

This table only includes USNRC-required results from the primary (base) program.

Page B2

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT "APPENDIX C 2001 REMIP Changes Page C I

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE C 2001 TMINS REMP Changes The following changes to the TMINS REMP were effective January 1, 2001:

The collection of air particulate and air iodine samples at Station B 1-4 was discontinued. During 2001, air particulate and air iodine samples were collected at seven locations, three more than required by the NRC.

The collection of milk samples at Station P7-1 was discontinued. As required by the NRC, milk samples were collected at four locations in 2001.

As permitted by the NRC, beginning in December and continuing through February 2002, the collection and analysis frequency for milk was reduced from biweekly to monthly. Biweekly collections and analyses will begin again in March 2002.

The collection of unfinished (raw) surface water samples at Station F 15-1 was discontinued.

j During 2001, unfinished (raw) surface water samples were collected at three locations, one more than required by the NRC.

The frequency for analyzing finished and unfinished surface water for low-level 1-131 was reduced from biweekly to monthly, the frequency required by the NRC for finished surface water.

The unfinished surface water samples collected from Station Q9-1 were no longer analyzed for low-level 1-131. The NRC does not require unfinished surface water samples to be analyzed for low-level 1-131.

The unfinished surface water samples collected from Station A3-2 were no longer analyzed for gamma-emitting radionuclides and H-3. As required by the NRC, samples from two unfinished surface water locations (Stations J1-2 and Q9-1) were analyzed for gamma-emitting radionuclides and H-3.

Fish samples were no longer analyzed for H-3. The NRC does not require fish samples to be analyzed for H-3.

The collection of aquatic sediment samples at Station J1-2 was discontinued. During 2001, aquatic sediment samples were collected at three locations, one more than required by the NRC.

The frequency for collecting groundwater at Station NW-CW and analyzing the samples for H-3 was reduced from weekly to semiannually.

Page C2

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT "APPENDIX D 2001 Cross Check Program Results Page D1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE D-1 Environmental, Inc.

2001 DOE EML Cross Check Program Results(A)

Environmental, Inc.

DOE EML Collection Value Uncertainty Value

[Min Ma Agemn Date Media Nuclide (B & E)

(C & E)

(D & E)

Ratio Ratio (F) 3/2001 Air Filter Co-60 20.110 0.160 19.440 0.79 1.30 YES Cs-134 2.710 0.150 2.830 0.74 1.21 YES Cs-137 9.860 0.230 8.760 0.78 1.35 YES Mn-54 7.250 0.220 6.520 0.80 1.36 YES Sr-90 7.410 0.150 7.100 0.55 2.05 YES Gr Beta 2.300 0.020 2.580 0.76 1.52 YES 3/2001 Soil Ac-228 45.600 4.000 42.700 0.80 1.50 YES Bi-212 53.200 3.100 42.000 0.45 1.23 NO (G)

Bi-214 42.100 7.700 32.600 0.78 1.50 YES Cs-137 1772.600 79.800 1740.000 0.80 1.29 YES K-40 583.800 52.600 468.000 0.80 1.37 YES Pb-212 46.600 8.500 41.500 0.74 1.36 YES Pb-214 45.300 8.600 34.300 0.76 1.53 YES Sr-90 55.600 2.200 69.000 0.61 3.91 YES 3/2001 Vegetation Co-60 28.500 2.100 30.400 0.75 1.51 YES Cs-137 795.500 76.400 842.000 0.80 1.37 YES K-40 592.600 42.500 603.000 0.78 1.43 YES Sr-90 1239.600 130.000 1330.000 0.52 1.23 YES 3/2001 Water Co-60 97.000 0.800 98.200 0.80 1.20 YES Cs-137 70.100 4.000 73.000 0.80 1.24 YES H-3 76.500 5.500 79.300 0.74 2.29 YES Sr-90 3.850 0.130 4.400 0.64 1.50 YES Gr Beta 1246.400 31.100 1297.000 0.56 1.50 YES 9/2001 Soil Ac-228 68.100 1.400 59.570 0.80 1.50 YES Bi-212 65.100 1.600 62.067 0.45 1.23 YES Bi-214 47.300 4.700 36.900 0.78 1.50 YES Cs-137 659.200 10.800 612.330 0.80 1.29 YES K-40 737.700 16.600 623.330 0.80 1.37 YES Pb-212 64.700 3.800 58.330 0.74 1.36 YES Pb-214 53.700 7.700 39.670 0.76 1.53 YES Sr-90 27.400 6.300 30.596 0.61 3.91 YES Page D2

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE D-1 Environmental, Inc.

2001 DOE EML Cross Check Program Results(A)

Environmental, Inc.

DOE EML Collection Value j

Uncertainty Value Min Max Agreement Date Media Nuclide (B & E)

(C & E)

(D & E)

I Ratio Ratio (F) 9/2001 Water Co-60 206.700 4.700 209.000 0.80 1.20 YES Cs-137 46.600 0.800 45.133 0.80 1.24 YES H-3 254.100 3.600 207.000 0.74 2.29 YES Sr-90 4.100 0.300 3.729 0.64 1.50 YES Gr Beta 8461.000 206.000 7970.000 0.56 1.50 YES 9/2001 Air Filter Co-60 16.900 0.300 17.500 0.79 1.30 YES Cs-134 11.800 0.200 12.950 0.74 1.21 YES Cs-137 18.300 0.300 17.100 0.78 1.35 YES Mn-54 85.400 1.300 81.150 0.80 1.36 YES Sr-90 3.110 0.060 3.481 0.55 2.05 YES Gr Beta 13.800 0.100 12.770 0.76 1.52 YES 9/2001 Vegetation Co-60 40.200 0.900 35.300 0.75 1.51 YES Cs-137 1184.000 2.800 1030.000 0.80 1.37 YES K-40 1023.000 44.100 898.670 0.78 1.43 YES Sr-90 1364.000 18.400 1612.800 0.52 1.23 YES A.

Only analyses performed routinely for the REMP are included on this table.

B.

The Environmental, Inc. value is the mean of I or 3 measurements/determinations.

C.

The Environmental, Inc. uncertainty is the 2-sigma counting uncertainty for one determination and one standard deviation for three determinations.

D.

The DOE EML value is the mean of replicate determinations for each radionuclide.

E.

Reporting units are Bq/L for water, Bqikg (dry) for soil, Bq/kg (wet) for vegetation and total Bq for air filters.

F.

The control limits (min ratio and max ratio) are established by DOE EML. Acceptable agreement is achieved if the ratio of the Environmental, Inc. value divided by the DOE EML value falls within the control limits.

G.

This naturally-occurring radionuclide is present in the shield background. No follow-up actions were performed because all of the other gamma scan results were acceptable and the subject result was just outside of the upper control limit.

The control limit concept was established from percentiles of historic data distributions (1982 - 1992). The evaluation of this historic data and the development of the control limits are presented in DOE report EML-564. The control limits listed in this table were developed from percentiles of data distributions for the years 1993 - 1999.

Page D3

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table D-2 Environmental, Inc.

2001 ERA Statistical Summary Proficiency Testing Program(A)

ERA ERA Exp.

ERA Env., Inc.

Known Dev. from Control Result Value Known Limits Performance Date Media Nuclide (pCiiL)

(pCi/L)

Evaluation (B)

(C)

(D)

(E) 1/2001 Water Gr Beta 25.3 16.7 5.0 8.0-25.4 A

2/2001 Water 1-131 27.2 28.3 3.0 23.1-33.5 A

3/2001 Water H-3 17,400 17,800 1780.0 14,700.0-A 20,900.0 4/2001 Water Co-60 27.9 26.4 5.0 17.7-35.1 A

4/2001 Water Cs-134 16.0 16.9 5.0 8.2-25.6 A

4/2001 Water Cs-137 195.4 186.0 9.3 170.0-202.0 A

4/2001 Water Gr Beta 343.0 340.0 51.0 252.0-428.0 A

4/2001 Water Sr-89 62.8 64.1 5.0 55.5-72.8 A

4/2001 Water Sr-90 34.2 33.8 5.0 25.1-42.5 A

6/2001 Water Ba-133 37.8 36.0 5.0 27.3-44.7 A

6/2001 Water Co-60 49.9 46.8 5.0 38.1-55.5 A

6/2001 Water Cs-134 16.0 15.9 5.0 7.2-24.6 A

Page D4

l'll

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table D-2 Environmental, Inc.

2001 ERA Statistical Summary Proficiency Testing Program(A)

ERA ERA Exp.

ERA Env., Inc.

Known Dev. from Control Result Value Known Limits Performance Date Media Nuclide (pCi/L)

(pCi/L)

(pCiiL)

Evaluation (B)

(C)

(D)

(E) 6/2001 Water Cs-137 208.0 197.0 9.9 180.0-214.0 A

6/2001 Water Zn-65 37.8 36.2 5.0 27.5-44.9 A

7/2001 Water Sr-89 19.8 31.2 5.0 22.5-39.9 NA(F) 7/2001 Water Sr-90 26.3 25.9 5.0 17.2-34.6 A

7/2001 Water Gr Beta 48.5 53.0 10.0 35.7-70.3 A

8/2001 Water H-3 2,680.0 2,730.0 356.0 2,110.0-A 3,350.0 10/2001 Water 1-131 7.7 7.7 2.0 4.2-11.2 A

10/2001 Water Co-60 82.4 78.4 5.0 69.7-87.1 A

10/2001 Water Cs-134 52.2 54.1 5.0 45.4-62.8 A

10/2001 Water Cs-137 39.4 37.9 5.0 26.3-43.7 A

10/2001 Water Gr Beta 166.0 192.0 28.8 142.0-242.0 A

10/2001 Water Sr-89 12.8 16.7 5.0 8.0-25.4 A

10/2001 Water Sr-90 6.8 7.7 5.0

-1.0-16.4 A

Page D5

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table D-2 Environmental, Inc.

2001 ERA Statistical Summary Proficiency Testing Program(A)

ERA ERA Exp.

ERA Env., Inc.

Known Dev. from Control Result Value Known Limits Performance Date Media Nuclide (pCi/L)

(pCi/L)

Evaluation (B)

(C)

(D)

(E) 10/2001 Water Gr Beta 26.0 21.5 5.0 12.8-30.2 A

11/2001 Water Ba-133 66.7 69.3 6.9 57.5-81.1 A

11/2001 Water Co-60 59.3 59.7 5.0 51.0-68.4 A

11/2001 Water Cs-134 86.7 93.9 5.0 85.2-103.0 A

11/2001 Water Cs-137 45.0 42.0 5.0 33.3-50.7 A

11/2001 Water Zn-65 80.7 77.3 7.7 63.9-90.7 A

Only analyses performed routinely for the REMP are included on this table.

The Environmental, Inc. result is the mean for three measurements/determinations.

The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

Established per the guidelines contained in the EPA's National Standards for Water Proficiency Testing Criteria Document, December 1998, as applicable.

A= Acceptable - Reported Result falls within the Control Limits.

NA = Not Acceptable - Reported Result falls outside of the Control Limits.

A reanalysis was performed; the result was 35.3 +/- 4.4 pCi/L which was within the established control limits.

Page D6 A.

B.

C.

D.

E.

F.

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT "APPENDIX E 2001 Land Use Census Page El

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE E-1 2001 ANNUAL DAIRY CENSUS(')

Azimuth Name(z),

Distance Address No.

No.

Sector

& Phone Cows Goats Direction Code Number Breed No. Cows Milked No. Goats Milked Dairy Used Grazing Period 3.3km (2.1 mi) 30 Cows, goats, sheep and horses are periodically kept for quarantine from a few days to a few weeks.

Animals graze for short periods of time N

A Animals are then shipped interstate or to foreign countries. If milked, milk is used as animal feed.

prior to exportation. Animals also receive prepared feed.

6.6km (4. lmi) 350 Holstein 150 Cows 150 Land 0 Lakes and Own Use Milk cows receive homegrown feed.

NE C

25 Heifers Heifers graze from June to October.

1.7km (1. Imi) 650 (3)

Holstein 110 Cows 96 Mt. Joy Co-op Animals graze from May I to ENE D

75 Heifers November 1. Animals also fed hay and com.

1.8km (I.lmi) 930 (3)

Holstein 180 Cows 180 Mt.Joy Co-op Dry cows graze from April to E

E 120 Heifers &

November and also receive homegrown Calves feed. Milking cows receive homegrown feed; they do not graze on pasture.

5.2km (3.2mi) 1040 Holstein 115 Cows 100 Mt.Joy Co-op Animals are only on pasture during dry ESE F

10 Heifers periods. Milk animals fed stored silage and hay.

2.3km (1.4mi) 1300 (3)

Holstein 65 Cows 50 National Farmers Organization Animals graze from April to November.

SE G

30 Heifers and Own Use During the winter, animals receive silage, hay and high moisture corn, if available.

7.8km (4.9 mi) 2000 Holstein 70 Cows 65 Land 0 Lakes and Own Use Animals graze from April 15 to October SSW K

30 Heifers

15. Otherwise, animals are fed silage Holstein 6and baled hay.

23.3km (14.5mi) 205' (3)

Holstein 60 Cows 50 Land 0 Lakes and Own Use Animals do not graze; they are put in an SSW K

40 Heifers exercise pen. Animals receive stored 24 Calves feed.

6.0km (3.7mi) 2950 Holstein 80 Cows 50 12 Nannies 0

Land 0 Lakes Animals graze from May to October.

WNW P

Otherwise, animals receive homegrown feed.

,' l nis table includes tme closest dairy farm in each of the 1i meteorological sectors within

"(2)Names and addresses are on file.

(')These are the regularly sampled milk farms.

a distance of five miles of 1 MIN*S (it one exists) plus the regularly sampled milk farms.

Page E2

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE E-2 2001 Annual Residence Census0)

(,)Census identifies nearest residence in each of the sixteen meteorological sectors.

2*)Names and addresses are on file.

Page E3 Azimuth Azimuth Distance and Name(2), Address Distance and Name2), Address and Sector and Sector Direction Code Telephone No.

Direction Code Telephone No.

6,000 ft.

50 12,000 ft.

1860 (1,839m)

A (3,658 m)

J N

S 3,800 ft.

280 3,400 ft.

213.70 (1,158m)

B (1,036 m)

K NNE SSW 2,800 ft.

480 2,850 ft.

2260 (853 m)

C (869 m)

L NE SW 2,450 ft.

67.50 2,500 ft.

2500 (747 m)

D (777 m)

M ENE WSW 2,300 ft.

800 1,850 ft.

2720 (700 m)

E (564 m)

N E

W 5,800 ft.

1230 1,900 ft.

2930 (1,770 m)

F (579 m)

P ESE WNW 3,750 ft.

1450 2,150 ft.

3060 (1,143 m)

G (655 m)

Q SE NW 3,750 ft.

1520 3,500 ft.

337.50 (1,143 m)

H (1,067m)

R SSE NNW

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE E-3 2001 Broad Leaf Vegetation Sampling Results°')

Collection Sample Location Vegetation Gamma Sr-90 Date Type Result Result (pCi/g, wet)

(pCi/g, wet) 09/19/01 TM-FPL-ESE1 Grape Leaves Be-7: 0.62 +/- 0.14 0.016 +/- 0.004 K-40:1.3 +/- 0.2 0.014 +/- 0.0020) 09/19/01 TM-FPL-ESE2 Sumac Leaves Be-7: 0.62 +/- 0.13 0.026 +/- 0.005 K-40: 5.5 +/- 0.3 0.025 + 0.002(3) 09/19/01 TM-FPL-ESE3 Johnny Smoker Leaves Be-7: 0.48 +/- 0.13 0.018 +/- 0.005 K-40: 1.6 +/- 0.2 0.013 +/- 0.003(')

09/19/01 TM-FPL-SEI Sycamore Leaves Be-7: 1.1 +/- 0.2

< 0.005 K-40: 1.5 +/- 0.3

< 0.0053) 09/19/01 TM-FPL-SE2 Beech Sp. Leaves Be-7: 0.69 +/- 0.21 0.0059 +/- 0.0030 K-40: 3.4 +/- 0.4 0.0091 +/- 0.0017()

09/19/01 TM-FPL-SE3 Grape Leaves Be-7: 0.41 +/- 0.12

< 0.010 K-40:1.8 +/- 0.2

< 0.00403) 09/20/01 TM-FPL-B 10-2(2)

Sycamore, Maple and Oak Be-7: 0.98 +/- 0.15 0.032 +/- 0.006 Leaves K-40: 3.5 +/- 0.3 0.033 +/- 0.0030)

"('tCollection and analysis of broad leaf vegetation was performed in lieu of a garden census.

(')Control Sample (3)Reanalysis Result Page E4 I

I I

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX F 2001 Data Reporting and Analysis Page F1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Environmental samples frequently contain very little, if any, radioactivity. Even when very sensitive, state-of-the-art counting equipment is used, many of the sample count rates can not be differentiated from the background count rate or the count rate of the blank sample. When this occurs, the sample is said to have a radioactivity level or concentration at or below the sensitivity of the analysis method. In this case, the analysis result is reported as less than a numerical value that corresponds to the sensitivity of the analysis method. Sensitivities are influenced by parameters such as sample volume, background or blank sample count rate and efficiency of the counting device.

The terms used to describe the sensitivity are the lower limit of detection (LLD) and minimum detectable concentration (MDC). For this report, these two terms are considered to be synonymous. They are defined as:

LLD (MDC) =

4.66 Sb E

V

2.22

Y

exp (4-At) where:

Sb the standard deviation of the background counting rate or the counting rate of a blank sample, as counts per minute, E

=

the counting efficiency of the equipment, as counts per disintegration, V

=

the volume or mass of the sample, such as L, g or m3, 2.22

=

the number of disintegrations per minute per picocurie, Y

=

the chemical yield, if applicable, 21

=

the radioactive decay constant for the particular radionuclide and At

=

the elapsed time between sample collection (or end of sample collection period) and counting.

The applicable LLD or MDC for each radionuclide and analysis is listed in Table 1. A large percentage of the 2001 sample results were reported as less than the LLD or MDC. Unless noted otherwise, the results that were reported as less than the LLD or MDC were not included in the calculations of averages, standard deviations and ranges (by station or group) in the text and tables of this report.

The data from samples that contained concentrations above the LLD or MDC were used in the calculations (averages, standard deviations and ranges) contained in this report. The individual sample results were generally reported to two significant figures. Each result also included a two-sigma counting uncertainty (95% confidence interval) to the same decimal place. The counting uncertainties were not used in any statistical calculations in this report.

Page F2

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The data used in a few tables and all annual graphs were actual sample concentrations. For historical graphs, actual sample concentrations were used for 1996 - 2001 data points only. The actual concentration is calculated by subtracting the background count rate or the count rate of a blank sample from the count rate of the sample. The net count rate is then converted to a net sample concentration which is either positive, negative or zero.

There are several advantages of using actual sample concentrations. Biases in the data (averages, ranges, etc.), such as those caused by averaging only sample concentrations above the MDC, are eliminated. Missing data points on graphs also are eliminated. It should be noted that negative sample concentrations are important to the overall averages and trends in the data, but they have no physical significance. A negative sample concentration simply means that the background or blank sample count rate is greater than the sample.

The data were grouped by station, time period and by control and indicator status. Minimum, maximum and average values were calculated for each of these groups as well as standard deviations (2ay, 95% confidence interval).

Quality control results (inter-laboratory and intra-laboratory) were not statistically analyzed with other data. Including quality control data would introduce a bias at selected stations while providing little additional interpretive information.

1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT "APPENDIX G

2001 Groundwater Monitoring Results Page G1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE G-1 2001 Tritium Concentrations in Onsite Groundwater and Storm water (pCi/L) 2000 Average 2001 Average Station (Well Type)

+/- 2 std dev*

= 2 std dev*

2001 Range*

MS-1 (Monitoring) 160 250 MS-2 (Monitoring) 260 +/- 50 600 + 1,100 190 - 960 MS-4 (Monitoring) 1,900 1,300 MS-5 (Monitoring) 190 +/- 160 290 + 30 280 - 300 MS-7 (Monitoring) 180

< 180 MS-8 (Monitoring) 360 +/- 280 260 +/- 90 230 - 290 MS-19 (Monitoring) 540 910 MS-20 (Monitoring) 360 +/- 400 350 +/- 150 300 - 410 MS-21 (Monitoring) 190 1000 MS-22 (Monitoring) 640 +/- 530 480 + 150 390 - 560 OS-14 (Monitoring) 170 230 OS-18 (Monitoring) 4,000 + 14;000 730 +/- 730 270- 1,800 RW-1 (Monitoring) 2,700 + 2,800 350 +/- 410 200 - 490 RW-2 (Monitoring) 500 1,400 +/- 2,900 340 - 2,400 NW-A (Service Water) 1,300 + 100 1,000 +/- 500 850 - 1,200 NW-B (Service Water) 2,900 + 1,600 2,100 +/- 2,100 1,400 - 2,900 NW-C (Service Water) 18,000 : 4,000 14,000 + 4,000 12,000 - 15,000 NW-CW (Clearwell) 5,800 + 3,100 1,700 + 1,200 1,300 - 2,100 OSF (Drinking Water) 430 + 390 490 +/- 90 420 - 520 48S (Drinking Water) 220 +/- 40 200 +/- 80 160 - 240 EDCB (Storm water) 340 +/- 210 280 +/- 230 200 - 450

=

Averages, standard deviations and ranges were based on concentrations > the minimum detectable concentration (MDC).

=

Only one concentration in 2001 was > MDC or only one sample was collected in 2001.

< MDC

=

Measured concentration(s) was equal to or below the MDC.

NS

=

Station was not sampled and, therefore, no data were available.

(Refer to Figures G-1 and G-2 for locations of onsite groundwater and storm water stations).

Page G2

-L

-11

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Page G3 TABLE G-2 2001 Tritium Concentrations in Offsite Groundwater (pCi/L) 2000 2001 Station (Location)

Concentration Concentration El-2 (TMINS Visitors Center)

< MDC

< MDC N2-1 (Goldsboro Marina)

< MDC

< MDC = Measured concentration was < the minimum detectable concentration (MDC).

(Refer to Table A-I and Figures 1 and 2 for locations of the offsite stations).

Figure G-1 TMINS REMP Groundwater Stations Inside the Protected Area V_

EPICOR I-m

ý=LEGEND L Monitoring Well RW-1 50 MS-21 I,

I:

NO SCALE (3/200 1)

Page G4 I1

Figure G-2 TMINS REMP Groundwater Stations Outside the Protected Area*

LEGEND L

Monitoring Well SDrinking Water Well G Clearwell A Industrial Well

The offsite groundwater wells are located at the TMI Visitors Center (EI-2) and the Goldsboro Marina (N2-1). The locations of these wells are shown on Figures 1 and 2.

Page G5 NO SCALE (3/2 01 )

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT "APPENDIX H 2001 TLD Quarterly Data Page H1

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE H-1 2001 TLD Quarterly Data (mR/std month)

Station Historical 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Yearly Avg 2 std dev Al-4 4.3 3.7 4.0 4.8 4.6 4.3 1.0 A3-1 4.3 3.8 3.6 4.6 4.6 4.2 1.1 AS-1 5.5 5.2 4.8 5.9 5.5 5.4 0.9 A9-3 4.1 4.1 4.9 4.9 4.5 0.9 B1-1 4.4 3.9 4.0 4.9 4.6 4.4 1.0 BI-2 4.3 4.1 4.0 4.9 4.9 4.5 1.0 B2-1 4.2 4.1 5.1 4.7 4.5 0.9 B5-1 5.3 4.9 5.0 5.7 5.5 5.3 0.8 B10-1 5.1 4.6 4.4 5.5 5.1 4.9 1.0 Cl-1 5.2 4.5 5.1 5.7 5.5 5.2 1.1 C1-2 4.3 4.2 4.0 4.8 4.8 4.5 0.8 C2-1 4.4 4.5 5.4 5.1 4.9 1.0 C5-1 5.1 4.8 4.8 5.9 5.5 5.3 1.1 C8-1 5.9 5.2 5.1 5.9 5.6 5.5 0.7 DI-!

4.6 4.2 4.1 5.0 4.8 4.5 0.9 D1-2 5.4 4.6 4.7 5.6 5.1 5.0 0.9 D2-2 5.4 5.5 6.4 6.3 5.9 1.0 D6-1 6.4 5.4 5.3 6.4 6.5 5.9 1.3 D15-1 5.7 4.8 4.7 5.9 5.6 5.3 1.2 EI-2 4.9 4.4 4.5 5.3 4.9 4.8 0.8 EI-4 5.7 4.0 4.0 4.6 4.7 4.3 0.8 E2-3 4.9 5.4 6.0 6.0 5.6 1.1 E5-1 5.3 4.7 5.1 5.9 5.8 5.4 1.1 E7-1 5.2 4.8 4.8 5.8 5.3 5.2 1.0 FI-1 5.0 4.4 4.8 5.6 4.9 1.2 FI-2 4.4 4.5 5.2 5.1 4.8 0.8 Fl-4 4.1 4.1 5.2 5.1 4.6 1.2 F2-1 5.2 5.1 6.0 6.3 5.7 1.2 F5-1 6.0 5.3 5.2 6.1 6.1 5.7 1.0 F10-1 6.3 5.5 5.9 6.6 6.6 6.2 1.1 F25-1 5.6 4.9 4.8 6.1 5.6 5.4 1.2 GI-2 4.9 4.7 4.6 5.7 5.8 5.2 1.3 G1-3 6.9 3.8 4.0 4.6 4.9 4.3 1.0 G1-5 4.0 4.2 4.8 5.3 4.6 1.2 G1-6 4.2 4.1 5.1 5.4 4.7 1.3 G2-4 5.8 5.4 6.6 6.5 6.1 1.1 G5-1 5.1 4.4 4.4 5.4 4.9 4.8 1.0 G10-1 7.6 6.7 6.6 7.5 8.0 7.2 1.3 GI-15 6.4 5.0 5.0 5.7 5.8 5.4 0.9 HI-1 5.3 4.6 4.5 5.5 5.2 5.0 1.0 H3-1 4.1 37 3.6 4.9 4.1 4.1 1.2 H5-1 4.1 3.7 3.7 4.7 4.2 4.1 1.0 H8-1 7.9 6.7 7.2 8.0 8.1 7.5 1.3 HI5-1 5.8 5.2 5.2 6.2 6.3 5.7 1.2 JIl-1 5.3 3.9 4.1 5.0 4.6 4.4 1.0 JI-3 3.7 3.5 3.8 4.3 4.5 4.0 0.9 J3-1 4.2 4.4 5.6 5.3 4.9 1.4 Pa.ge H2

2001 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE H-1 2001 TLD Quarterly Data (mR/std month)

Station Historical 1 st Quarter 2nd Quarter 3rd Quarter 4th Quarter Yearly Avg 2 std dev 15-1 5.7 5.1 5.1 6.1 6.1 5.6 1.2 17-1 4.7 5.3 5.2 6.1 6.3 5.7 1.1 J15-1 6.1 5.3 5.2 6.1 6.1 5.7 1.0 KI-4 4.7 3.9 4.0 5.0 4.7 4.4 1.1 K2-1 5.8 5.2 6.1 5.8 5.7 0.9 K3-1 3.9 4.1 5.2 4.5 4.4 1.1 K5-1 6.9 5.3 5.2 6.1 6.1 5.7 1.0 K8-1 5.4 5.0 5.2 5.7 5.7 5.4 0.7 K15-1 4.8 4.7 4.4 5.6 5.3 5.0 1.1 LI-i 5.1 4.2 4.4 5.1 5.2 4.7 1.0 LI-2 4.3 4.1 5.2 4.6 4.6 1.1 L2-1 5.5 4.8 4.5 5.6 5.1 5.0 0.9 L5-1 4.5 4.1 4.1 5.1 4.8 4.5 1.0 L8-1 5.0 4.7 4.7 5.6 5.3 5.1 0.9 LI5-1 5.2 4.9 4.6 5.7 5.4 5.2 1.0 MI-1 4.1 3.8 4.6 4.8 4.3 0.9 M 1-2 4.3 4.9 5.0 4.7 0.8 M2-1 4.3 3.8 3.7 4.7 4.7 4.2 1.1 M5-1 5.2 4.3 4.3 5.3 5.1 4.8 1.1 M9-1 6.5 5.4 5.7 6.6 6.2 6.0 1.1 NI-1 4.8 4.1 5.2 5.0 4.8 1.2 NI-3 4.6 3.7 3.8 5.1 4.9 4.4 1.5 N2-1 5.3 3.8 4.0 4.9 4.5 4.3 1.0 N5-1 5.3 3.8 3.9 4.6 4.2 4.1 0.7 N8-1 5.4 4.9 4.9 5.8 5.4 5.3 0.9 N15-2 5.9 5.2 5.3 6.1 5.7 5.6 0.8 PI-i 4.7 4.2 5.3 5.0 4.8 1.1 P1-2 3.7 4.0 5.0 6.1 4.7 2.2 P2-1 5.4 5.1 5.4 6.2 5.9 5.7 1.0 P5-1 4.8 4.6 4.6 5.3 5.1 4.9 0.7 P8-1 4.7 3.9 4.1 4.4 4.3 4.2 0.4 QI-I 4.6 4.6 5.3 5.0 5.0 0.7 QI-2 4.4 3.7 3.6 4.5 4.6 4.1 1.0 Q2-1 5.4 4.2 4.3 5.3 4.8 4.7 1.0 Q5-1 4.9 4.2 4.0 4.9 4.7 4.5 0.8 Q9-1 5.3 4.4 4.4 5.3 5.1 4.8 0.9 QI5-1 5.9 4.8 5.1 6.0 5.9 5.5 1.2 RI-1 4.8 4.1 4.0 4.8 4.9 4.5 0.9 RI-2 4.2 3.9 4.9 4.3 4.4 1.0 R3-1 6.3 5.3 6.1 6.0 5.9 0.9 R5-1 5.1 5.9 4.8 5.6 5.4 5.4 0.9 R9-1 5.2 5.9 4.8 5.7 5.4 5.5 1.0 R15-1 4.4 5.3 4.2 5.3 4.8 4.9

1.0 NOTES

1) Missing data indicates no data

2) Some newer stations have no historical data Page H3

Figure H-1 Onsite TLD Station Locations at TMINS

-

(h)

D E

F Stations HI-I and JI-I are located off the map to the south.

NO SCALE Page H4 (3/200 1)

ML021150208

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