Text

2003 Annual Radiological Environmental Operating Report
	ML041410069
Person / Time
Site:	Monticello
Issue date:	05/14/2004
From:	Thomas J. Palmisano; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-MT-04-030
	Download: ML041410069 (60)
	v • d • e

Commilted toft NcarExcellen~

Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC May 14, 2004 L-MT-04-030 Technical Specification 6.7.C.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 2003 Annual Radiological Environmental Operating Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 6.7.C.1, the Nuclear Management Company, LLC is submitting the Annual Radiological Environmental Operating Report for the year 2003.

This letter contains no new NRC commitments, nor does it modify any prior commitments.

Please contact John Fields at (763) 295-1663 with any questions or comments.

Thomas J. Palmisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc:

Administrator, Region IlIl, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce

, i'- z' 5

L-1"'e:;

2807 West County Road 75

Monticello, Minnesota 55362-9637 Telephone: 763-295-5151

Fax: 763-295-1454

ENCLOSURE 1 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31,2003 58 pages follow

Environmental, Inc.

Midwest Laboratory an Akyx u

Tedlogfes Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-07C0

fax (847) 5644517

- XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO-THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2003 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

L na ara A a M.S.

\\:rao tanager

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Nuclear Management Company, LLC for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

ii

TABLE OF CONTENTS No.

Pge Preface.....................................................

ii List of Tables....................................................

iv List of Figures......................................................

v

1.0 INTRODUCTION

1 2.0

SUMMARY

2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)...................... 3 3.1 Program Design and Data Interpretation............................

3 3.2 Program Description............................

4 3.3 Program Execution............................

5 3.4 Laboratory Procedures............................

6 3.5 Program Modifications............................

6 3.6 Land Use Census............................

6 4.0 RESULTS AND DISCUSSION...............................................

7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.................................... 7 4.2 Summary of Preoperational Data...............................................

7 4.3 Program Findings...............................................

8 5.0 FIGURES AND TABLES..............................................

12

6.0 REFERENCES

24 APPENDICES A

Interlaboratory Comparison Program Results................................................ A-1 B

Data Reporting Conventions................................................ B-1 C

Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background In Unrestricted Area..................................... C-1 D

Sampling Location Maps.....................................

D-1 Iiii

No.

5.1 5.2 5.3 5.4 LIST OF TABLES Title Paqe Sample Collection and Analysis Program.......................................

13 Sampling Locations.14 Missed Collections and Analyses.16 Radiation Environmental Monitoring Program Summary.19 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results...................................

Al -1 A-2 Thermoluminescent dosimeters (TLDs).A2-1 A-3 In-house Spiked Samples.A3-1 A-4 In-house "Blank" Samples.A4-1 A-5 In-house "Duplicate" Samples.A5-1 A-6 Department of Energy MAPEP comparison results.

A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results.A7-1 Attachment A: Acceptance criteria for spiked samples.

A2 Appendix C C-I Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas.

C-2 iv

LIST OF FIGURES No.

Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations.......................................... 17 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (M-2, 3, 4, 5) versus control location (M-1)

.18 Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring.......

D-2 D-2 Sample collection and analysis program: TLD locations, Outer Ring.

D-3 D-3 Sample collection and analysis program: TLD locations, Controls................................................................................................................................... D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sampling locations.D-5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations.D-6 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2003.

This Program monitors the levels of radioactivity In the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on Its surroundings.

Tabulation of the individual analyses made during the year are not included in this report.

These data are included In a reference document (Environmental, Inc., Midwest Laboratory, 2004a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 620 MWe. It is located on the Mississippi River in Wright County, Minnesota, and operated by Nuclear Management Company, LLC. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.

I

2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant is described. Results for the year 2003 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

No effect on the environment due to the operation of the Monticello Nuclear Generating Plant is Indicated.

2

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impact of the Plant on its environment.

For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content.

In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLD's).

Sources of environmental radiation Include the following:

(1)

Natural background radiation arising from cosmic rays and primordial radionuclides; (2)

Fallout from atmospheric nuclear detonations; (3)

Releases from nuclear power plants; (4)

Industrial and medical radioactive waste; and (5)

Fallout from nuclear accidents.

In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello Plant which Is based on the Indicator-control concept. Most types of samples are collected both at Indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique Involves analyses for specific radionuclides present in environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and Iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-1 37, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological Impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation.

Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are In the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 Is of cosmogenic origin and potassium-40 is a naturally-occurring Isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.

These isotopes are released In small quantities by nuclear power plants, but to date their major source of Injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

3

Program Design and Data Interpretation (continued)

Other means of distinguishing sources of environmental radiation are employed in interpreting the data.

Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the Plant's Monitoring Program can be related to those obtained In other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation In the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used In Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the plant site. To assure that sampling is carried out In a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision).

Maps of sampling locations are Included In Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly.

Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, MA, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: fourteen In an Inner ring in the general area of the site boundary, sixteen In the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly. An emergency set of TLDs Is placed in the field along side of the regular set. The emergency TLDs are returned to EIML quarterly for annealing and repackaging.

Milk samples are collected monthly from three farms (two indicator and one control). There are currently only two milk producers within the indicator area. Milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture. All samples are analyzed for iodine-131 and gamma-emitting Isotopes.

Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for Iodine-131. Corn and potatoes are collected annually only if the field Is irrigated by water in which liquid radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.

The terrestrial environment is also monitored by the quarterly collections of well water from four locations. Samples are analyzed for tritium and gamma-emitting Isotopes.

River water Is collected weekly at two locations, one upstream of the plant and one downstream.

Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

4

Program Description (continued)

Drinking water is collected weekly from the City of Minneapolis water supply, which Is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting Isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments.

Shoreline sediment is also collected semi-annually from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.

3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:

(1)

A partial air particulate/air Iodine sample was obtained from location M-5 for the week ending 02-05-03. The timer was suspect.

(2)

Surface water samples could not be collected from M-08 (upstream) for the weeks ending 02-05-03 and 02-12-03. The shoreline was frozen.

(3)

No milk was available from M-10 (Goenner Farm) in April, 2003. Dairy operations were discontinued.

(4)

Milk samples were not available from M-28 (Hoglund Farm) June 4th through September 9th, 2003. Dairy operations were temporarily discontinued.

(5)

No air particulate/air iodine samples were available from location M-4 for the weeks ending 06-25-03 through 07-16-03. A power outage occurred during an electrical storm. A partial sample was obtained for the week ending 07-23-03, after power restoration.

(6)

TLD data was not available from location M-09A for the second quarter, 2003. The TLD was missing in the field.

(7) A partial air particulate/air Iodine sample was obtained from location M-1 for the week ending 09-17-03. Power was Interrupted due to an open fuse.

(8)

TLD data was not available from location M-01A for the third quarter, 2003. The TLD was missing In the field.

Deviations from the program are summarized in Table 5.3.

5

3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

Gamma-spectroscopic analysis Is performed using a high-purity germanium (HPGe) detector.

Levels of iodine-131 in cabbage and natural vegetation were determined by gamma spectroscopy.

Concentrations of airborne iodine-131 In charcoal samples were also determined by gamma spectroscopy.

Tritium was determined by a liquid scintillation technique.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation In Interlaboratory Comparison (crosscheck) Programs.

Results obtained in the crosscheck programs are presented in Appendix A.

3.5 Program Modifications The Goenner Farm (M-10) discontinued dairy operations in March, 2003. The Campbell Farm was added as a replacement in May, 2003.

3.6 Land Use Census In accordance with the Offsite Dose Calculation Manual, sec. 07.01, a land use census shall be conducted and shall Identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May I and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

The 2003 land use census was conducted between August 18 and September 26, 2003.

More accurate mapping by GPS in 2003 resulted in increased D/Q values by sector (> 20%) for four of the nearest residence and five nearest garden locations. Milk animal locations remained unchanged. The Trefethen garden was Identified as the highest D/Q value garden plot. The highest DIQ locations for nearest residence and nearest milk animal did not change from the 2002 census.

Details of the land use census are contained In the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

6

4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2003. The last reported test was made by the People's Republic of China on October 16,1980.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, to determine background levels expected In the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements In fallout averaged 20,600 pCi/m 2 in 1969 and 12,000 pCim 2 in 1970.

These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 pCim 3.

Present day levels have stabilized at around 0.025 pCim 3. Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCVL.

Soybean crop measurements in 1969 averaged 35.5 pCi/g-for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured In soil averaged 51.7 pCl/g. Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCVL In upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCVL for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels In 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCig for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured In 1969 and 1970, averaged 0.044 pCI/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCI/g respectively.

7

4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

Ambient Radiation (TLD's)

Ambient radiation was measured In the general area of the site boundary, at an outer ring 4 - 5 mi.

distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (15.6 and 15.0 mRem/91 days, respectively). The mean for special locations was 14.6 mRem/91 days. The mean for control locations was 15.9 mRem/91 days. Dose rates measured at the Inner and outer ring locations were similar to those observed from 1988 through 2002 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Rin Outer Ring Dose rate (mRemI91 days) 1988 14.8 14.7 1989 15.0 15.4 1990 16.1 16.2 1991 15.2 15.8 1992 15.1 15.1 1993 15.6 15.9 1994 14.6 14.0 1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8

Airborne Particulates The average annual gross beta concentrations In airborne particulates were identical at indicator and control locations (0.027 pCVm ) and were similar to levels observed from 1988 through 2002.

The results are tabulated below.

Year Indicators Control 3

Concentration (DCifM 1988 0.030 0.030 1989 0.027 0.026 1990 0.023 0.023 1991 0.024 0.024 1992 0.023 0.023 1993 0.024 0.023 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 0.023 0.023 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 Average annual gross beta concentrations in airborne particulates.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al.,

1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983.

The highest averages usually occur during the months of January and December, and the first and fourth quarters, as seen in 1988 through 2003.

Two pieces of evidence indicate conclusively that the elevated activity observed during the first and fourth quarters was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an Identical pattern was observed at the Prairie Island Nuclear Generating Plant, about 100 miles distant from the Monticello Nuclear Generating Plant (XCEL Energy Corp., 2003b).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955) was detected in all samples, with an average activity of 0.060 pCim for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCim3 in all samples.

9

Milk lodine-131 activity measured below the detection limit of 1.0 pCVL in all samples. Cesium-137 results were below the LLD level of 15 pCVL in all samples.

No other gamma-emitting Isotopes except naturally-occurring potassium-40, were detected in milk samples. This is consistent with the finding of the National Center for Radiological Health (1968) that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine.

In summary, the milk data for 2003 show no radiological effects of the plant operation.

River Water and Drinkinq Water Tritium activity measured below the LLD of 330 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 3.0 pCVL and was similar to average levels observed from 1988 through 2002. Gross beta averages are tabulated below.

Year Gross Beta Year (pCi/L) 1988 2.7 1989 2.6 1990 2.2 1991 2.9 1992 2.1 1993

=

2.6 1994 2.0 1995 2.3 1996 2.1 1997 2.3 1998 2.4 1999 2.2 2000 2.5 2001 2.5 2002 2.9 2003 3.0 Average annual concentrations; Gross beta in drinking water.

Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected in 1975, 1976, 1977, and 1978 Indicate that concentrations of these nuclides are remaining fairly constant and are consistent with drinking water levels in other parts of the country. Gamma-emitting isotopes were below detection limits in all surface water samples.

There was no Indication of a plant effect.

Well Water Tritium measured below the LLD level of 330 pCUL in all samples. All gamma isotopic results were below detection limits. There was no indication of a plant effect.

10

Crops Cabbage and broccoli were collected in September from three locations and analyzed for Iodine-131. Levels of 1-131 measured below 0.020 pCig wet weight in both samples. There was no indication of a plant effect. There were no crops irrigated from the Mississippi River within 5 miles of the plant In 2003; therefore, no corn or potato samples were collected for analysis from irrigated fields.

Fish Fish samples were collected in May and October. Flesh was separated from the bones and gamma-scanned. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (3.57 and 3.50 pCig wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of any plant effect.

Invertebrates Samples were collected in May and October. The samples were analyzed for gamma-emitting isotopes. With the exception of naturally-occurring potassium-40, all gamma-emitting isotopes were below detection limits. There was no indication of any plant effect.

Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and October and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in all samples collected, averaging 0.051 pCig dry weight in downstream samples and 0.035 pCig dry weight in two control samples, indicating the influence of fallout deposition.

Similar levels of activities and distribution have been observed since 1978. The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

11

5.0 FIGURES AND TABLES 12

Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No.

Codes (and Typer Frequencyb Frequencyc Ambient radiation (TLDs)

Airborne Particulates 40 M-01A-M-14A M-01B - M-16B M-01S - M-06S M-01C - M-04C CIQ Ambient gamma GB, GS (QC of each location) 5 M-1(C), M-2, M-3, MA, M-5 C/W Airborne Iodine 5

M-1(C), M-2, M-3, M4, M-5 C/W 1-131 1-131, GS Milk 3

M-10 (C), M-24, M-28 G/Md Surface water 2

M-8(C), M-9 GS(MC), H-3(QC)

Drinking water I

M-14 GN1 GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

H-3, GS Well water 4

M-1O(C), M-11, M-12, M-27 GIQ Edible cultivated crops -

corn Leafy Vegetable Potatoes" Fish (one species, edible portion) 1 M-19 2

M-27, St. Cloud Farmer's Mkt. (C)

I M-21 2

M-8(C), M-9 GIA GIA GS 1-131 GS GS GIA G/SA Periphyton or invertebrates Shoreline sediment 2

M-8(C), M-9 3

M-8(C), M-9, M-15 GISA GS GS GISA Location codes are defined in Table 5.2. Control stations are Indicated by (C). All other stations are indicators.

b Collection type Is coded as follows: Cl = continuous, GI = grab. Collection frequency is coded as follows:

W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.

c Analysis type Is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =

iodine 131. Analysis frequency Is coded as follows: MC = monthly composite, QC = quarterly composite.

d Milk is collected biweekly during the grazing season (May - October), if milch animals are on pasture.

eCollected only if the plant discharges radioactive effluent Into the river, then only from river irrigated fields.

13

Table 5.2. Sampling locations, Monticello Nuctear Generating Plant.

Distance and Direction from Code Types Collection Site Sample Typeb Reactor M-1 M-2 M-3 M-4 M-5 M-8 C

Air Station M-1 Air Station M-2 Air Station M-3 Air Station M4 Air Station M-5 Upstream of Plant Downstream of Plant AP, Al AP, Al AP, Al AP, Al AP, Al SW, SS, BO, F SW, SS, BO, F C

M-9 M10d M-10 M-11 M-12 M-14 M-15 M-19 M-21 M-24 M-27 C

C Goenner Farm M, WW Campbell Farm M, WW City of Monticello WW Plant Well #1 WW City of Minneapolis DW Montissippi Park SS River Irrigated Corn Fleldc River Irrigated Potato Fieldc Weinand Farm M

Wise residence VE, WW

a. Available Producer VE Hoglund Farm M

Trefethen residence (Highest DIQ Garde VE 11.0 mi @ 307@/NW 0.9 mi @ 1370/SE 0.7 mi @ 104'/ESE 0.9 mi @ 146°/SSE 2.7 mi @ 1341/SE

< 1000' upstream of Plant Intake

< 1000' downstream of Plant Discharge 12.4 ml @ 322°/NW 10.6 mi @ 357/N 3.4 mi @ 1261/SE 0.2 ml @ 232°/SW 37.0 ml @ 132°/SE 1.4 mi @ 114°/ESE 4.8 mi @ 178°/S 0.6 mi @ 198°/SSW

> 10.0 mi.

3.6 mi @ 300I/WNW 1.1 mi @ 143/SE M-28 M-29 General Area of the Site Boundary M-01A M-02A M-03A M-04A M-05A M-06A M-07A M-08A M-09A M-10A M-1 IA M-12A M-13A M-14A Sherburne Ave. So.

Sherbume Ave. So.

Biology Station Road Biology Station Road Biology Station Road County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 North Boundary Road North Boundary Road TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.7 mi @ 01lN 0.8 mi @ 31°/NNE 1.3 mi @ 55°/NE 0.6 mi@91°1E 0.6 mi @ 118°/ESE 0.7 mi @ 130°/SE 0.6 mi @ 148°/SSE 0.6 mi @ 170°/S 0.6 mi @ 192°/SSW 0.5 mi @ 218°/SW 0.4 mi @ 2401WSW 0.4 mi @ 260°/W 0.8 mi @ 324°/NW 0.7 mi @ 340°/NNW 14

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, (continued).

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor ADproximatelv 4 to 5 miles Distant from the Plant M-011B M-02B M-03B M-04B M-05B M-06B M-07B M-08B M-09B M-IOB3 M-IIB3 M-12B M-13B M-14B M-15B M-16B Sherco #1 Air Station County Road 11 County Road 73 & 81 County Road 73 (196th St.)

City of Big Lake County Road 14 and 196th St.

Monte Industrial Drive Residence, Hwy 25 & Davidson Ave.

Weinand Farm Reisewitz Farm, Acacia Ave.

Vanlith Farm, 97th Ave.

Lake Maria State Park Bridgewater Station Anderson Residence, Cty Rd. 111 Red Oak Wild Bird Farm Sand Plain Research-Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD.

4.6 ml @ 03°/N 4.4 ml @ 20°/NNE 4.3 ml @ 53°/NE 4.3 ml @ 68°/ENE 4.4 mi @ 90°/E 4.4 mi @ 117°/ESE 4.4 ml @ 136°/SE 4.7 ml @ 161°lSSE 4.8 ml @ 178/S 4.2 ml @ 204°/SSW 4.0 ml @ 226°/SW 4.2 ml @ 254°NWSW 4.0 ml @ 270°W 4.3 ml @ 289°/WNW 4.3 ml @ 309°/NW 4.3 ml @ 341°/NNW Special Interest Locations M-01S M-02Sd M-02S M-03S M-04S M-05S M-06S M-01C C

M-02C C

M-03C C

M-04C C

Osowski Fun Market Edgar Klucas Residence Krone Residence Big Oaks Park Pinewood School Rivercrest Christian Academy Monte Public Works Kirchenbauer Farm County Roads 4 and 15 County Rd 19 and Jason Ave.

Maple Lake Water Tower TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.6 ml @ 234/SW 1.1 ml @ 143°/SE 0.5 ml @ 223/SW 1.6 mi@ 102°/E 2.4 ml @ 129/SE 3.1 ml @ 118°/ESE 2.7 ml @ 134°1SE 11.5 ml @ 323°/NW 11.2 ml @ 47/NE 13.0 ml @ 100°/E 10.3 ml @ 226°/ SW

' C denotes control location. All other locations are Indicators.

b Sample Codes:

AP Airbome particulates Al Airbome Iodine BS Bottom (river) sediments BO Bottom organisms DW Drinking Water F

Fish M

RW SS TLD VE WW Milk River Water Shoreline Sediments Thermoluminescent Dosimeter Vegetation / vegetables Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river Irrigated fields.

d Goenner Farm replaced by Campbell In 2nd Qtr. of 2003.

15

Table 5.3. Missed collections and analyses at the Monticello Nuclear Generating Plant.

All required samples were collected and analyzed as scheduled with the following exceptions:

Plans for Preventing Recurrence AP/Al

Beta, M-05 02-05-03 Low volume due to bad timer Replaced timer.

1-131 or Interrupted flow.

SW Gamma M-08 02-05-03 Shoreline frozen None required.

02-12-03 Ml

Gamma, M-10 4/9/2003 Goenner Farm out of Replaced by Campbell Farm In 1-131 dairy business.

May, 2003.

Ml

Gamma, M-28 6/4/2003 Hoglund Dairy temporarily Hoglund will Inform the MNGP 1-131 through out of dairy business.

upon resumption of operation.

9/9/2003 Resumed 09-24-03.

AP/AI

Beta, M-04 6/25/2003 Power unavailable to sampler Collections will resume upon 1-131 through after electrical storm.

restoration of power.

7/16/2003 Power restored 07-18-03.

AP/AI

Beta, M-04 7/2312003 Partial sample collected.

Collection resumed upon restoration 1-131 of power to the sampler site.

Power restored 07-18-03.

TLD Ambient M-09A 7/3/2003 TLD run over by tractor.

Replaced TLD and TLD holder, Gamma moved further from edge of field.

AP/AI

Beta, M-01 9/17/2003 Open fuse, Electrician checked sampler and 1-131 Partial sample collected.

replaced fuse.

TLD Ambient M-01A 10/3/2003 TLD missing In the field due to Replaced TLD and TLD holder.

Gamma road construction.

16

Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

-l-Inner Ring

-D-Outer Ring 20-19:

It 1 8 -

-r n

n z

a S

I nN 1 2 16 -*

10 co I 40 ~

C'J Cl) 0 )

(

~0

(

co c0C

0)

0) 0

)

0)

)

0)

0) 0 0D

~

0D a)

0)

0) 0 0

CO 0O 17

Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.

indicators (M-2, 3, 4, 5)

I -- Control (M-1)

I n Aepc 0.0U3 0.033 0.031 0.029 0.027 0.025 X

0.023 0.

CL 0.021 0.019 0.017 0.015 r

i I -

I I

I PL.

&-4 I

I I

I 0

0 C¢ If CD t

0

0)

C' C

8 co n

0 0

0 a

0 0

C 0

0 C_

C_

_C 18

Table 5.4 Radiological Environmental Monitortng Program Summary Name of Facility Monticello Nuclear Location of Facility Wright, Minnesota Generating Plant Docket No.

50-263 Reporting Period January-December. 2003 (County. State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)e Mean (F)'

Mean (F)'

Routine (Units)

Analyses' Range' Locationd Range' Range' Results" TLD (Inner Ring, Gamma 54 3.0 15.6 (54154)

M-12A 17.6 (414)

(See Control 0

General Area at (14.3-18.3) 0.7 ml @ 273'W (17.0-18.3) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 64 3.0 15.0 (64/64)

M-09B. Weinand Farm 16.2 (4 /4)

(See Control 0

4-5 ml. distant)

(12.4-16.9) 4.7 ml @ 180I/S (15.9-16.4) below.)

mReml91 days)

TLD (Special Gamma 24 3.0 14.6 (24124)

M-06S, Mont. Pub. Wks.

16.8 (414)

(See Control 0

Interest Areas)

( 11.4-17.9) 2.7 mi @ 136/SE (16.3-17.9) below.)

mRem/91 days)

TLD (Control)

Gamma 16 3.0 None M-03C, County Rd.19 &

15.9 (414) 15.0 (16/16) 0 mRem/91 days)

Jason, 13.0 mi. @ 100'/E (15.0-17.0)

(13.2-17.0)

Airbome GB 254 0.005 0.027 (202/202)

M-4 0.028 (47147) 0.027 (52/52) 0 Particulates (0.011-0.053) 0.9 ml © 150'/SSE (0.014-0.048)

(0.011-0.048)

(pCVm3)

GS 20 Be-7 0.015 0.062 (16/16)

M4 0.068 (414) 0.055 (414) 0 (0.036-0.095) 0.9 ml @ 150'/SSE (0.041-0.095)

(0.036-0.071)

Mn-54 0.0011

L-MT-04-030, 2003 Annual Radiological Environmental Operating Report

Text

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

Navigation menu

Search