Text

Annual Radiological Environmental Operating Rept for North Anna Power Station & ISFSI for Jan-Dec 1998. with
	ML20206B341
Person / Time
Site:	North Anna
Issue date:	12/31/1998
From:	Breedon J, Matthews W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	99-237, NUDOCS 9904290214
	Download: ML20206B341 (120)
	v • d • e

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Vincisir Esa:cTune ANi> Powo:n CON 1PANY RICII%10ND, YiRGINI A 2Mit April 23,1999 United States Nuclear Regulatory Commission Serial No.99-237 Attention: Document Control Desk NAPS /JHL Washington, D. C. 20555 Docket Nos.

50-338 50-339 72-16 License Nos. NPF-4 NPF-7 SNM-2507 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT North Anna Units 1 and 2 Technical Specifications 6.9.1.8 require the submittal of an Annual Radiological Environmental Operating Report. Accordingly, enclosed is the Annual Radiological Environmental Operating Report for North Anna Units 1 and 2 and North Anna Independent Spent Fuel Storage Installation for the reporting period of January 1,1998 through December 31,1998.

Ij, if you have any questions or require additional information, please contact us.

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Very truly yours, N/

k./Bk/ d W. R. Matthews Site Vice President Enclosure l

Commitments made by this letter: None

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U. S. Nuclear Regulatory Commission Region II l

Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 l

Atlanta, Georgia 30303 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station

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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POW.ER STATION Radiological Environinental Monitoring Program January 1,1998 to December 31, 1998 l

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Prepared by VIRGINIA ELECTRIC AND POWER COMPANY and TELEDYNE BROWN ENGINEERING O

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Annual Radiological Environmental Operating Report North Anna Power Station January 1,1998 to December 31, 1998 W

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Prepared by:

James B. Breeden, Supervisor Radiological Analysis and Material Control bME Reviewed by:

v Erich W. Dreyer Supervisor Health Physics Technical Services l

l'0 Approved by:

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H. 'tafford O

Superintendent adiological Protection l

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. Table Of Contents

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Section Title P_ age Preface..........................................................................................6 i

Executive S ummary........................................................................... 7 l

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I n trod uc t i o n.........................................................................

l II.

S ampling And Analysis Program............................

.....................12 III.

Program Exceptions......................................................................

IV.

Summary And Discussion Of 1998 Aaalytical Results................................. 29 l

A.

Airborne Ex posure Pathway....................................................... 29 i

1.

Air Iodine /Particulates.......................................................

2.

Preci pi tation................................................................... 3 3.

Soil.............................................................................32 B.

Waterborne Exposure Pathway..................................................... 32 l

1.

Ground /Well Water......................................................... l

)

2.

Ri ver Wat e r...............................................................

3.

S urface Water..............................................................

C.

Aquatic Exposure Pathway.......................................................... 35 1.

Sedime nt/S ilt............................................................

2.

S horeli ne S0il...........................................................

1 D.

I ngestion Ex posure Pathway.......................................................

1.

Milk............................................................................38 2.

Fish.............................................................................38 3.

Food /Ve ge tation...............................................................

E.

Direct Radiation Exposure Pathway................................................ 40 1.

TLD Dosi met en s.......................................................

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Co n c l u si on..............................................................

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r Table Of Contents (Continued) l t

Seetlon Ihlt hute VI.

Re fere n ce s.................................................................................. 4 5 l

VII.

A ppe n dice s................................................................................ 4 6 Appendix A - Radiological Environmental Monitoring............................... 46 Program Annual Summary Tables - 1998 Appendix B - Data Tables................................................................. 53 Appendix C - Land Use Census - 199 8................................................. 7 6 Appendix D - Synopsis of Analytical Procedures...................................... 79 Appendix E - Interlaboratory Comparison Program................................... 90 List of Trending Graphs 1.

Gross Beta in Air Particulates............................................................. 30 1

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Tritiu m in River Wate r...................................................................... 30 3.

Tritium in Surface Water................................................................. 34 4.

Cobalt-58 in Sediment S ilt................................................................. 34 5.

Cobalt-60 in Sedime nt S ilt................................................................. 3 6 6.

Cesium-134 in Sediment Silt............................................................... 36 7.

Cesium-137 in Sediment S ilt.............................................................. 37 l

8.

Ce sium-134 i n Fish........................................................................ 3 7 l

9.

Ce si u m-13 7 in Fish......................................................................... 3

' 10.

Environmental Rsdiation - TLDs.......................................................... 39 lf3 J

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Y List of Tables l

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Radiological Sampling Station Distance and Direction j

i from Unit 1................................................................................. 1 3

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2.

North Anna Power Station Sample Analysis Program................................ 25 3.

REMP Exceptions for Scheduled Sampling and Analysis During 1998....................................................................28 1

l Appendix B Tables j

B-1 Iodine-131 Concentration in Filtered Air................................................ 53 l

B-2 Concentrations of Gross Beta in Air Particulates....................................... 55 l

B-3 Gamma Emitter, Strontium 89, and Strontium 90 Concentrations in Air Particulates........................................................ 59 l

. B-4 Gamma Emitter and Tritium Concentration in Precipitation........................... 62 1

B-5 Gamma Emitter Concentration in Soil.................................................. 63 i

B-6 Gamma Emitter, Strontium, and Tritium Concentrations O

ia orouaa aaa weii water................................................................ 64 l

B-7.

Gamma Emitter, Strontium, and Tritium Concentrations in l

River Water................................................................................. 64 B-8 Gamma Emitter, Strontium, and Tritium Concentrations i n S urface Water............................................................................ 65 B-9 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water State-Split Samples.................................................... 66 B-10 Gamma Emitter Concentrations in Sediment Silt....................................... 67 B-11 Gamma Emitter Concentrations in Shoreline Soi1...................................... 67 l

B-12 Gamma Emitter Concentrations in Milk................................................. 68 l

i B-13 Gamma Emitter Concentrations in Fish................................................ 70 B-14 Gamma Emitter Concentrations in Food / Vegetation................................... 71 B-15 Diiect Radiation Measurements Quanerly Annual TLD Results.......................................................... 73 B-16 Direct Radiation Measurements Sector Quanerly TLD Results............................................................ 74 3

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e-Preface l

This report is submitted in acconiance with North Anna Unit I and 2 Technical Specification 6.9.1.8 and North Anna Independent Spent Fuel Storage Installation (ISFSI)

Technical Specification 5.5.2b.

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Executive Summary

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This document is a detailed repoit on the 1998 North Anna Nuclear Power Station j

l Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 l

' through December 31,1998 in water, silt, shoreline sediment, milk, aquatic biota, food products, I

vegetation, and dimet exposure pathways have been analyzed, evaluated, and summarized. The REMP is designed to ensure that radiological effluent releases am As Low As is Reasonably Achievable (ALARA), no undue environmental effects occur, and the health and safety of the public is protected. The program also detects any unexpected environmental processes which could allow radiation accumulations in the environment or food pathway chains.

Radiation and radioactivity in the environment is constantly monitored within a 25 mile radius of the station. Virginia Power also collects samples within this area. A number of sampling locations for each medium were selected using available meteorological, land use, and water use j

data. Two types of samples are obtained. The first type, control samples, are collected from amas that am beyond the measurable influence of North Anna Nuclear Power Station or any other nuclear facility. These samples are used as mference data. Normal background radiation levels, or radiation present due to causes other than North Anna Power Station, can thus be compared to the i

environment surrounding the nuclear power station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the plant.

Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration.

l Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a " pre-operational baseline."

Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, other causes such as the Chemobyl accident, or natural variation.

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i Teledyne Brown Engineering provides sample analyses for various radioisotopes as j

appropriate for each sample media. Participation in an interlaboratory comparison pmgram

- provides an independent check of sample measurement pmcision and accuracy. Typically, radioactivity levels in the environment am so low that analysis values fmquently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requims that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLD). This 7

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r ensures that analyses are as accurate as possible. Samples with extremely low levels of radiation

'Q which cannot be detected are therefore reported as being below the LLD. The NRC also mandates a " reporting level." Licensed nuclear facilities must report any releases equal to or greater than this l

reponing level. Environmental radiation levels are sometimes referred to as a percent of the reponing level.

L Analytical results are divided into five categories based on exposure pathways: Airborne, I

waterborne, aquatic, ingestion, and direct radiation. Each of these pathways is described below:

The airborne exposure pathway includes airborne iodine, airborne particulate, l

l-precipitation, and soil samples. The overall 1998 airborne results were very similar to previous years and to preoperationallevels. No increase was noted and there were no -

detections of fission products cr other man-made isotopes in the airborne paniculate media during 1998.

The waterborne exposure pathway includes ground /well water, river water, and surface water samples. No man-made or natural isotopes were detected in Lake Anna surface l'

water except for tritium. The average tritium activity in 1998 was 13.4% of the NRC reporting level. This has essentially remained unchanged from 1995 levels.

The aquatic exposure pathway includes sediment / silt and shoreline samples. North Anna sediment contained some cesium-137. During the preoperational )eriod, cesium-137 was detected. Sediment contamination, however, does not provice a direct dose

,Q pathway to man. In shoreline soil, which may provide a direct dose pathway, only cesium-137 was detected. Cesium-137 levels were 276 pCi/kg in 1998.

l The ingestion exposure pathway includes milk, fish, and food / vegetation samples.

l Iodine-131 was not detected in any 1998 milk samples. Although cesium-137 has been detected in the past, it was not detected in 1998 milk samples. Strontium-90 was l

detected at leve;s comparable to 1989, and lower than preoperational years. Both i

strontium-90 and cesium-137 are attributable to atmospheric nuclear weapons testing in the past. Naturally occurring potassium-40 was detected at normal environmental levels.

Fish samples during -1998 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator repairs and better liquid waste processing, however, have reduced these activity levels from previous years. Vegetation samples were statistically similar to both control and preoperational levels.

The direct radiation exposure pathway measures environmental radiation doses by use i

of thermoluminescent dosimeters (TLDs). TLD results have remained essentially the l

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same since the preoperational period in 1977.

During 1998, as in previous years, operation of the North Anna Nuclear Power Station created'no adverse environmental affects or health hazards. The maximum total body dose f

calculated for a hypothetical individual at the Nonh Anna Power Station site boundary due to liquid and gaseous effluents released from the site during 1998 would be approximately 0.58 millirem.

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1 For reference, this dose may be compared to the 360 millirem average annual exposure to every l

person the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1% These results demonstrate not only compliance with federal and state regulations, but i

also demonstrate the adequacy of radioactive effluent control at the North Anna Nuclear Power Station.

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m VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM l

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INTRODUCTION l

The operational radiological environmental monitoring program conducted for 1998 for the North Anna Power Station is provided in this report. The results of measurements and analyses of data obtained from samples collected from January 1,1998 through December 31,1998 are summarized.

A. The North Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles south west of Fredericksburg, Virginia.

The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply systems and turbine generator furnished by Westinghouse Electric Corporation.

Each unit is designed with a gross electrical output of 979 megawatts electric (MWe). Unit I achieved commercial operation on June 6,1978, and Unit 2 on December 14,1980. An independent spent fuel storage facility was licensed for dry cask storage of spent fuel in 1998.

l B. The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria am met, the operating license for North Anna Power Station includes l

Technical Specifications which address the release of mdioactive effluents.

Inplant i

monitoring is used to ensure release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also i

included in North Anna Power Station Offsite Dose Calculation Manual (ODCM).

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l C. ' Virginia Electric and Power Company is responsible for collecting the various indicator and control envimmnental samples. Teledyne Brown Engineering is responsible for sample analysis and submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with control levels, which vary with time due to such extemal events as O

< '=ic < v 6 -6 rd -e=t *e e " te>t r >> "t "a 8e"8 " > v><ietie"e r t"<=iir occuning isotopes. Data collected prior to the plant operation is used to indicate the degree j

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of natural variation to be expected. This preoperational data is compared with data collected duwing the operational phase to assist in evaluating the radiological impact of the plant operation.

D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and North Anna's ODCM. These concentrations an:

based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of"As Low As Is Reasonably Achievable".

E.

This report documents the results of the Radiological Environmental Monitoring Program for 1998 and satisfies the following objectives of the program:

1 1.

Provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation I

exposure of the maximum exposed members of the public resulting from tlw station operation.

h 2.

Supplements the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.

3.

Identifies radioactivity changes in the environment.

4.

Verifies that the plant operations have no detrimental effect on the health and safety of the public.

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II. SAMPLING AND ANALYSIS PROGRAM O

II.

SAMPLING AND ANALYSIS PROGRAM O

A.

Sampling Program 1.

Table I summarizes the sampling program for North Anna Power Station during 1998. Figure 1 indicates the locations of the environmental monitoring stations.

2.

For routine TLD measurements, two dosimeters made of CaSO4:Dy in a teflon card are deployed at each sampling location. Several TLDs are co-located with NRC and Commonwealth of Virginia direct radiation recording devices.

3.

In addition to the Radiological Enviranmental Monitoring Program required by North Anna Technical Specifications, Virginia Electric and Power Company (VEPCO) splits samples with the Commonwealth of Virginia.* All samples listed in Table 1 am shipped to Teledyne Brown Engineering located in Westwood, New Jersey.

4.

All samples listed in Table 1 am taken at indicator locations except those labeled

" control".

O Routine splitting of samples with the Commonwealth of Virginia has been discontinued. Samples am only split if requested by the Commonwealth of Virginia.

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i I

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B.

Analysis Program O

1.

Table 2 summarizes the analysis program conducted by Teledyne Brown Engineering for North Anna Power Station during 1998.

O oV 24

T TABLE 2 (Page 1 of 3) h NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM FAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mRi2mR mR/std. month D:simetry (TLD)

(84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month 3

Airborne Weekly I-131 0.07 pCi/m R:diolodine 3

Airborne Weekly Gross Beta 0.01 pCi/m Prrliculate 3

Quarterly (a)

Gamma Isotopic pCi/m Cs-134 0.05 Cs-137 0.06 Annually Sr-89 (c) pCi/m3 (2nd Quarter Sr-90 (c)

Composite)

Q Surface Water Monthly I-131 1(b) pCi/l Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58 15 Co-60 15 i

Zn-65 30 Zr~95 30 Eb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)

Tritium (H-3) 2000 pCi/l 2nd Quarterly Sr-89 (c) pCi/l Composite Sr-90 (c)

LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.

3b' Quarterly Composites of each location's samples are used for the required analysis.

/

(a)

(b)

LLD for non-drinking water is 10 pCi/ liter.

(c)

There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

f l

25 t

m TABLE 2 (Page 2 of 3)

O "onT" ^""^ eowen sr^Tio" SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY A N A LYSIS LLD*

REPORT UNITS River Water Monthly I-131 1(b) pCi/l Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 i

Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)

Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 (c) pCi/l Sample Sr-90 (c)

Ground Water Quanctly(a)

Gamma Isotopic pCi/l (Well Water) 2nd Quarter Mn-54 15 i

Composite Fe-59 30

(

Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 I-131 1(b)

Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)

Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 (c)

Composite Sr-90 (c)

Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry)

Sediment Cs-134 150 Cs-137 180 Annually Sr-89 (c) pCi/kg (dry)

Sr-90 (c)

Precipitation Monthly Gross Beta pCi/l Semi-Annual Gamma Isotopic pCi/l Composite LLD's indicate those levels that the environme,tal samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Acbal analysis of the samples by Teledyne Brown Engineering may be lower than those listed.

,hs -

(a)

Quarterly Composites of each location's samples are used for the required analysis.

(b)

LLD for non-drinking water is 10 pCi/ liter.

(c)

There are no required LLD's for strontium-89% LLD's are those achieved by Teledyne Brown Engineering.

26 7

L.

L 1

I i

TABLE 2 l

l (Page 3 of 3)

O soarn AssA eowea SrArios SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD*

REPORT UNITS Shoreline Soll Semi-Annual Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Annually Sr-89 (a)

Sr-90 (a)

Soll Once per 3 yrs.

Gamma Isotopic pCi/kg (dry)

Cs-134 150 Cs-137 180 Once per 3 yrs.

Sr-89 (a) pCi/kg (dry)

Sr-90 (a)

Milk Monthly I-131 1

pCi/l Monthly Gamma Isotopic pCi/l Cs-134 15 s

Cs-137 18 Ba-140 60 La-140 15 Quarterly Sr-89 (a) pCi/l Sr-90 (a) l Fish Semi-Annual Gamma Isotopic pCi/kg (wet)

Mn-54 130 1

Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 4

Food Products Monthly if Gamma Isotopic pCi/kg (wet) l (Broadicaf available or Vegetation) at harvest Cs-134 60 Cs-137 80 1-131 60 pCi/kg (wet)

Note:

This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identinable, together with the above nuclides, shall also be identined and reported.

,O LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.

(a)

There are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.

27 l

O i

1 l

i III. PROGRAM EXCEPTIONS O

'O

I' 1

Appendix B REMP Exceptions For Scheduled

>0 Sampling And Analysis During 1998 - North Anna i

Location Description Date of Sampling Reason (s) for Loss / Exception STA-01,02, Air Iodine 12/02-12/09 Samples did not meet spec due to delay of 03,04 delivery at lab (20 days).

STA-05 Air Particulates 10/14-10/21 Low sample volume due to malfunction.

ENE-8 TLD's Fourth Quarter TLD missing.

ENE-40 10/07/98-01/13/99 l

)

I 0

28 n

i O

I i

IV.

SUMMARY

AND DISCUSSION OF 1998 ANALYTICAL RESULTS lQ l

l i

iv l

I V.

Summary And Discussion of 1998 Analytical Results 9

Data from the radiological analyses of environmental media collected during 1998 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance Manual and are explained in the Teledyne Brown Engineering Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed.

The results of the EPA Interlaboratory Comparison are provided in Appendix E.

Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC I

Branch Technical Position, Radiological Monitoring Acceptable Program (November 1979, Revision 1) and the ODCM.

The following is a discussion and summary of the results of the environmental measurements taken during the 1998 reporting period.

A.

Airborne Exposure Pathway 1.

Air Iodine /Particulates Charcoal cartridges used to collect airborne iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. The results are presented in Table B-1. All results were below the required lower limit of detection. For air particnlates, gross beta activity was observed in all fifty-two control samples with an averge concentration of 0.019 pCi/m3 and a range of 0.009 to 0.035 pCi/m3. The average measurement for the indicator locations was 0.018 pCi/m3 with a range of 0.007 to 0.037 pCi/m3. The results of the gross beta activities are presented in Table B-2. The gross beta activities for 1998 were comparable to levels measured in the 1982-1997 period. Prior to that period the gross beta I

activities were higher due to atmospheric nuclear weapons testing performed in other 29

TRENDMG CRAPH-1: CROSS BETA IN AIR PARTICULATES 1.

O f0.1.

W.

I i

1 0.01+ - - - - - - - - - - - - - - - - -

0 0.001 1986 1988 1990 1992 1994 1996 1998

--e--

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+ Indicator

--e Average Pre op

-+- Required LLD's i

O TRENDING GRAPH 2: TRmuM IN RIVER WATER-STATION 11 10000-y"

,,......................=--.......y g 1000-1 100-10-s 1

i i

i 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 During the preoperational period, tritium was not detected in the samples analyzed.

O Tritium

- + - Required LLD's 30

l countries. During the preoperational period of July 1,1974 through March 31,1978 gross O

beta activitics ranged from a low of 0.005 pCi/m to a high of 0.75 pCi/m3, 3

Air particulate filters were composited by locations on a quarterly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measure <1 in all 48 composite samples. The average measurement for the control location was 0.092 pCi/m with a range of 0.074 to 0.122 pCi/m3. The indicator locations had an average 3

3 concentration of 0.093 pCi/m3 and a range of 0.067 to 0.145 pCi/m.

During the preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Naturally occurring potassium-40 was not detected in the control samples.

Potassium-40 was detected in eight indicator samples with an average concentration of 3

0.006 pCi/m3 and a range of 0.003 to 0.015 pCi/m. A.ll other gamma emitters were below the detection limits. During the preoperational period gamma ray spectroscopy measured several fission products in nun.erous air particulate filters. All isotopes were attributed to atmospheric nuclear weapons testing conducted before the preoperational period. Among the isotopes measured were zirconium-95, ruthenium-103, ruthenium-106, cesium-137, cerium-141 and cerium-144.

The second quarter composites of air particulate filters from all twelve stations were analyzed for strontium-89 and 90. There was no detection of these fission products at any of the eleven indicator stations nor at the control station.

2.

Precipitation A sample of rain water was collected monthly at station Ol A, on site,0.75 miles,138 degrees SE and analyzed for gross beta activity. The results are presented in Table B-4.

The avemge gross beta activity for 1998 in the twelve samples was 3.8 pCi/ liter with a range from 1.2 to 16 pCi/ liter. Semi-annual composites were prepared and analyzed for g'amma emitting isotopes and tritium. Beryllium-7 was not detected during 1998. All other gamma emitters were below their detection limits. Tritium was not detected in the semi-annual composite samples. These results were comparable to or lower than those measured in 1986 thru 1997. During the preoperational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface. thus a direct comparison can not be made to the 1998 period. During the preoperational od, tritium was measured in over half of the few quarterly composites made. The trinum activity ranged from 100 to

'O 33o Pci'iiter-

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31 l

I 3.

Soil

)

G Soil samples which are collected every three years from twelve stations, were collected in July and analyzed by gamma ray spectroscopy. The results are presented in Table B-5.

Naturally occurring potassium-40 was detected in all twelve samples with an average activity of 11288 pCi&g (dry weight) and a range of 3610 to 22600 pCi&g (dry weight).

Beryllium-7 was measured in four samples with an average activity of 658 pCiAg (dry weight) and a range of 566 to 804 pCi/kg (dry weight). The terrestrial nuclide radium-226 was monitored in ten samples with an average activity of 2104 peiAg (dry weight) and a range of 1320 to 4170 pCi/kg (dry weight). The fission product cesium-137 was detected in eleven of the twelve samples with an average activity of 336 pCiAg (dry weight) and a range of 127 to 962 pCi/kg (dry weight). The cesium-137 is attributed to past atmospheric nuclear weapons testing.

The twelve soil samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89. Strontium-90 was detected in one sample with an activity of 370 pCi/kg (dry weight). This was most likely due to fallout from past nuclear j

weapons testing.

(3 U

B.

Waterborne Exposure Pathway 1.

Ground /Well Water Water was sampled quanerly from the on site well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The results are presented in Table B-6. No gamma emitting isotopes were detected during 1998. The second quarter l

sample was analyzed for strontium-89 and strontium-90. There were no detections of these isotopes above the detection level The four well water samples were analyzed for tritium.

There were no detections of tritium during 1998. No gamma emitting isotopes were detected during the preoperational period. Tritium was measured in most of the samples during that period with concentrations between 80 and 370 pCi/ liter.

2.

River Water A sample of water from the North Anna River was collected monthly at station 11, 5.8 miles downstream from the discharge lagoon,128 degrees SSE. The results are presented

)

in Table B-7. The samples were analyzed by gamma spectroscopy monthly. The samples 32

were analyzed for tritium quarterly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.

Potassium-40 was not detected during 1998 and all other gamma emitters were below the detection level. No detections of strontium-89 or strontium-90 occurred. Tritium was measured in all four samples with an average level of 2600 pCi/ liter and a range of 1900 to 3100 pCi/ liter. This is slightly lower than the average level measured in 1997 of 2650 pCi/ liter and a range of 2300 to 3000 pCi/ liter. No river water samples were collected during the preoperational period.

3.

Surface Water Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09A is located 12.9 miles WNW. The samples were analyzed for iodine-131 by radiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Table B-8.

The samples were also analyzed by gamma ray spectrometry. No gamma emitters were above their detection level at either sampling station.

'N A quanerly composite from each station was prepared and analyzed for tritium. The tritium activity at station 08 for the quanerly composites was at an average level of 2675 pCi/ liter with a range of 1900 to 3200 pCi/ liter. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCi/ liter. However, during 1993 the results were within the same range as those measured in 1986 thru 1997. During the preoperational period tritium was measured in several samples with concentrations between l

90 and 250 pCi/ liter. Tritium was not detected at station 09A.

Samples of surface water were collected by the Commonwealth of Virginia from two i

stations. Station W-33 is located at the discharge lagoon while station W-27 is located on the North Anna River at the RT. 208 Bridge, which is upstream of the site. They were collected monthly from Janucy thru June when they were discontinued. Twelve samples were collected and analyzed by gamma ray spectroscopy. The results are presented in Table B-9. All gamma emitters were below their detection levels.

Two samples from each station were analyzed for tritium during 1998. The average activity at station W-33 in all samples was 3200 pCi/ liter with a range of 2300 to 4100 0

33

TRENDING GRAPH - 3: TRITIUM IN SURFACE WATER - STA 08 10000,

O a

l l

.y.....

1000--

1

________________j 100,.;....,,,.,.,,.,.,...,,.,..,,,.,,.........

1/77 1/79 1/81 143 145 147 149 141 143 1/95

.1/97

--*-- Truium

-+

Required LLD's

--A Average Pre-op h

TRENDING GRAPH -4: COBALT-58 IN SEDIMENT SILT 1000.

l 100 -

R

/

-D

/

3 10 :

A 1

0345 0348 0447 0348 0449 03/90 03S1 0342 03S3 1043 06S4 8/95 8/98 8/97 8/98 During the preoperational penod, cobalt-58 was not detected in the samples analyzed.

Control Sta-09A

--+- Station-11 Stat 6on-8

- *-- Station 49 O

34

pCi/ liter. This is slightly higher than the 2650 pCi/ liter measured during 1997 at this

. station. Tritium was not measured at station W-27.

C.

. Aquatic Exposure Pathway

1..

Sediment / Silt Sediment samples were collected during February and August from each of three locations and were analyzed by gamma spectrometry. The results are presented in Table B-10. One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in two samples with an average activity of 211 pCi/kg (dry weight) and a range of 106 to 316 pCi/kg (dry weight).

Naturally occurring potassium-40 was observed in all six samples with an average activity of 14100 pCi/kg (dry weight) and a range from 12400 to 17200 pCi/kg (dry weight).

)

. Radium-226 was measured in all six samples with an average concentration of 1885 pCi/kg (dry weight) and a range of 1390 to 2210 pCi/kg (dry weight). Also naturally occurring, thorium-228 was observed in all six samples with an average concentration of 1460 pCi/kg l

(dry weight) and a range of 757 to 2440 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89 or 1

'O

. strontium-90 in a9uatic sedimeni/siit.

l L

During the preoperational period sediment. samples were analyzed by gamma ray spectroscopy, Cesium-137 was measured in most of the sampli; with concentrations between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight). Strontium-89 was not measured.- Potassium-40, radium-226, and thorium-228, all naturally occurring, were measured at background levels, l

l 2.

Shoreline Soil A sample of shoreline sediment was collected in February and August from station 08. The samples were analyzed by gamma ray spectrometry. The results are presented in Table B-

11. The naturally occurring nuclide potassium-40 was measured in both samples with an average activity cf 1536 pCi/kg (dry weight) and a range of 672 to 2400 pCi/kg (dry weight). Cosmogenic beryllium-7 was not measured during 1998. Thorium-228 was measumd in both samples at an average of 204 pCi/kg (dry weight) and a range of 101 to 308 pCi/x' g (dry weight). Radium-226 was measured in one sample with a concentration O

35

TRENDING C RAPH - 5: COBALT-60 IN SEDIMENT SILT 1000

'3 O

100

^

0

' h[^_

}_{[^

^

~

e v

g 10-I j

sa 1

03/85 03/86 03/87 03S8 04/89 03/90 03/91 03/92 03/93 10S3 08/94 08/95 08/96 06/97 08/98 During the preoperational period, cobalt-60 was not detected in the samples analyzed. Station-8

-e--

Station-09

-* Control-Sta-09A

-+- Station-11

(')

TRENDING GRAPH - 6: CESsUM-134 IN SEDIMENT SILT v

r, A

k:

k g

g --- # v 1

. t

'N,,

i 10 :

1 iiii ie i i i i i 03/85 03/86 03/87 03/88 04/89 03/90 03/91 03/92 03/93 10/93 08/94 08/95 08/96 08/97 8/98 During the preoperational period, cesium-134 was not detected in the samples analyzed.

Control-Sta49A Statbn-11 -+- Required LLD's Station 4

--o-Station 49 O

36

TRENDING G n APH - 7: CESIUM-137 IN SEDIMENT SILT 10000 a

l h

1000 1

i g

I h

100-

/

p g

s E*

10:

1 i i i i i i i i i i i i i i i i i i i i i i i i i i i i 3/85 3/86 3/87 348 3/89 3/90 3/91 3/92 3/93 10S3 8S4 08/95 08/96 08/97 08/98

--G- - Station-8

--- Control-Sta-09t>

--A Average Pre-Op

--+--- Station-09

--+-- Station-11 TRENDING GRAPH - 8: CESIUM-134 IN FISH 1000 O

+

.____...___...______...._4 it

\\

s

\\/

N.

i n.s.s.&

O

.--a g

(;

d'

!.10 :

Y i

j i

a 1

iiii,e i,,iiiii...

iiiie i iiii 4/80 4/83 4/85 10/06 847 3/88 12/88 8/89 10/90 4/92 10/93 03/95 08/96 02/98 During the preoperational period, cesium-134 was not detected in the samples analyzed.

Station 25 replaced station 09.

Control-Sta 25

-+

Required LLD's

--e-Station @

--+-- Station-09 37

of 960 pCi/kg (dry weight). Cesium-137, a fission product, was monitored in both samples with an average level of 276 pCi/kg (dry weight) and a range of 153 to 399 pCi/kg (dry weight).

l l

- The August sample was analyzed for strontium and there were no detections of strontium-l 89 or strontium-90.

I j

D.

Ingestion Exposure Pathway 1.

Milk The results of the iodine-131 analysis of milk samples are presented in Table B-12. A sample was collected monthly from two stations. A total of 24 samples were analyzed during 1998. There were no measurements of iodine-131 above the detection limits. The l

milk samples were also analyzed by gamma ray spectroscopy and the results are also presented in Table B-12. ' A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all samples with an avcrage of 1261 pCi/ liter and a range of l

1090 to 1410 pCi/ liter. The fission product cesium-137 has been detected sporadically in mcent years and the activity has been attributed to global fallout from past atmospheric

. weapons testing. However, cesium-137 was not detected at levels above LLD in any milk M-samples during 1998. All other gamma emitters were below their detection levels. A i

quarterly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontium-89 was not detected at levels above LLD in any of the samples monitored. Strontium-90 was detected in the eight samples monitored with an average level of 1.00 pCi/ liter and a range of 0.72 to 1.5 pCi/ liter. This is similar to l

activities determined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/ liter.

2.

Fish

~ Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment

- j because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-13. Eight samples of fish were collected E

during 1998. These samples were analyzed by gamma ray spectroscopy and the naturally -

l occurring isotope potassium-40 was found in all samples at an average of 2166 pCi/kg (wet weight) with a range of 1210 to 5390 pCi/kg (wet weight). The fission product cesium-134 was not measumd during 1998. The fission product cesium-137 was measured in h

three samples with an average activity of 31.1 pCi/kg (wet weight) and a range of 25.3 to 38 1

I

TRENDING CRAPH - 9: CESIUM-137 IN FISH 10000 0

1000; E

E

' +.

..............+

100; q

_A i

s / \\,_ _. _

\\

I

,/

g 10;

/

V 1

1 5/80 543 4/85 8/06 7/87 4/88 12/88 10/89 10/90 10/91 4/93 8S4 03/96 08/97 Station 25 replaced station 09.

-e-Station-08 --*- Station-09 -- Station-25 -A Average Pre-op -+

Required LLD O

TRENDING GRAPH - 10: ENVIRONMENTAL RADIATON -TLD's 10 I

^^:.

Jn l

1 1/06 1046 7/87 4/88 1/89 10/89 7/90 4/91 1/92 10/92 7/93 4S4 1/95 10/95 07/96 4/97 1/98 10/98

-G--

Environmental TLD's

-*- Sector TLD's

-A Average Preg 39

F 39.3 pCi/kg (wet weight). During the preoperational period cesium-137 was measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weight). All other gamma emitters were below their detection levels.

3.

Food / Vegetation Thiny-five food samples were collected from five locations and analyzed by gamma spectrometry. The results are presented in Table B-14. Naturally occurring potassium-40 was monitored in all 35 samples with an average activity level of 19822 pCi/kg (wet weight) and a range of 8060 to 48100 pCi/kg (wet weight). Cosmogenic beryllium-7 was detected in 34 of the 35 samples with an average concentration of 1615 pCi/kg (wet weight) l and a range of 280 to 6890 pCi/kg (wet weight). The terrestrial nuclide thorium-228 was l

detected in one sample at a level of 176 pCi/kg (wet weight).

l l

Cesium-134, a fission product, was not detected at levels above LLD during 192 ;.

Cesium-137 has been detected in some samples at low-levels in previous years and was detected in one sample at 56.6 pCi/kg (wet weight) during 1998.

Cesium-137 was measured in broadleaf garden vegetation during the preoperational period with concentratious between 53 and 98 pCi/kg (wet weight).

/

E.

Direct Radiation Exposure Pathway 1.

TLD Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table B-15. Individual measurements of external radiation levels in

' the environs of the North Anna site had an average dose of 6.8 mR/ standard month with a range of 4.8 to 12.7 mR/ standard month. This is comparable to the preoperational range.

The control station, No. 24, had an average reading of 6.5 mR/ standard month with a range of 5.8 to 7.4 mR/ standard month.

l l

Sector TLDs are deployed quarterly at thiny-two locations in the environs of the North Anna site. Two badges are placed at each location. The results am presented in Table B-

16. The' average ' level of the 32 locations (two badges at each location) was 7.2 mR/ standard month with a range of 4.2 to 13.0 mR/ standard month. The eight control TLDs,' collected. quarterly from four locations, showed an average reading of 6.3 mR/ standard _ month with a range of 4.7 to 8.4 mR/ standard month.

During the 40

i l

l L

preoperational period (staning in 1977), when the calculation of the TLD dose included a I

\\

{_

correction for the in-transit dose, the doses were measured between 4.3 and 8.8

)

mR/ standard month.

i i

I i

l I

i 1

lO l

I t

i l

l i

'O 41

O i

v concussions O

O

p l

V. Conclusions

'O The results of the 1998 Radiological Environmental Monitoring Program for the North Anna Nuclear Power Station and ISFSI have been presented. The following sections discuss exh

_ pathway individually followed by a program summary.

l Airborne Exposure Pathway Air particulate gross beta concentrations of all the indicator locations for 1998 followed the gross beta concentrations at the control location. The gross beta concentrations were comparable to l

levels observed since 1982 except for a five week period in 1987 which was influenced by the Chernobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/ cum, due to occasional atmospheric nuclear weapons tests.

Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There were no detections above the LLD for fission products nor cther man-made isotopes in the paniculate media during 1998. Iodine-131 was not detected in the charcoal filters analyzed during 1998.

i A precipitation sample was collected monthly during 1998 and analyzed for gross beta O

activity. Aii the gross beta activities were comparabie to those measured in grevious years. ourins l

the preoperational period the average gross beta activity was 0.92 pCi/ liter. Semi-annual composites were analyzed for gamma emitting isotopes and tritium. All gamma emitters were below their detection limits. Tritium was not observed above the LLD during this reporting period in 1998.. During the preoperational period the average tritium activity was 165 pCi/ liter.

Waterborne Exposure Pathway No man-made or natural isotopes 'wre monitored in the surface water of Lake Anna except tritium. The average tritium activity during 1998 at the waste heat tmatment facility was 2675 pCi/ liter whichis 13.4% of the reponing level for a water sample. In 1997 the tritium level was I

3100 pCi/ liter. The preoperationallevel was 150 pCi/ liter and has risen since 1977, though it has remained mlatively consistant since 1986.

l The samples of surface water collected by the Commonwealth of Virginia at the waste heat tmatment facility had similar tritium results with a measurement of 3200 pCi/ liter as compared to 2650_ pCi/ liter for 1997. The upstream location had no measurements of tritium during 1998.

O l

42 i.

There were two measurements of tritium during 1997 at an average activity of 1600 pCi/ liter. No gamma emitting isotopes were detected.

River water collected from the North Anna River,5.8 miles downstream of the site had an average tritium level of 2600 pCi/ liter. The average tritium in 1997 had been 2650 pCi/ liter. No gamma emitters were detected.

Ground water from the environmental well on site contained no gamma emitters. There were also no detections of tritium in ground /well water during 1998.

Aquatic Pathway Sediment / silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna envimnmental samples indicated that one man-made isotope was present. Cesium-137 was detected in two samples at the control location. During the pmoperational period, cesium-137 was measured in samples of aquatic sediment.

Sediment contamination does not provide a direct dose pathway to man.

The samples of shoreline soil monitored downstream of the site contained no measurement of cesium-134. Cesium-137 was measured in both samples at an average level of 276 pCi/kg.

O-Cesium-137 was measured during 1997 at an average of 159 pCi/kg.

Ingestion Pathway Iodine-131 was not detected in any of the twenty four milk samples using the radiochemical separation method. Although cesium-137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there were no detections during 1998. Strontium-90 was measured in all eight milk samples. Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in ar.y of the milk samples.

Naturally occurring potassium-40 was measumd in all the milk samples at normal environmental levels.

l Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 1998 showed the presence of one man-made isotope, cesium-137.

This isotope was at an activity level somewhat higher than preoperational levels but statistically similar to levels in-1987 through 1997.

Only cesium-137 was measured in preoperational environmental fish samples. Due to primary and secondary steam generator problems experienced at Nonh Anna during 1984/1985, a build up in activity levels both in effluents and fish did occur.

l-43

F Repairs to the steam generators and better liquid waste processing have reduced these activity

' levels in effluents and thus decreased activity levels are now being observed in the fish. The average level of activity during 1998 of cesium-137 was 1.6% of the reporting level.

One vegetation sample contained cesium-137 at a level of 56.5 pCi/kg. Cesium-137 has been measured in the past and in preoperational samples.

l~

l Direct Exposure Pathway The direct exposure pathway as measumd in the environment of the North Anna site by thermoluminescent dosimetry has remained essentially the same since the pmoperational period in 1977 at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels which.are less than the estimated whole bor e due to natural terrestrial and cosmic radiation and the intemal dose from natural

- radionuclina Program Conclusions The results were as expected for normal euvironmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes.

These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence.

As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compamd to the Reporting Level Concentrations listed in the Offsite Dose Calculation Manual. These concentrations am based upon 25% of the annual dose commitment recommended by 10CFR50, Appendix 1, to meet the criterion "As Low as is Reasonably Achievable." Based upon the evidence of the enviror. mental monitoring program the station is operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the North Anna Nuclear Power Station during 1998.

l I

l-

!o m

I 44' I

O Q

VI. REFERENCES O

i VI.

References O

1.

Virginia Electric and Power Company, North Anna Power Station Technical Specifications, Units 1 and 2.

l 2.

Virginia Electric and Power Company, Station Administrative Procedure, VPAP-2103, "Offsite Dose Calculation Manual.

3.

Title 10 Code of Federal Regulation, Part 50 (10CFR50), " Domestic Licensing of Production and Utilization Facilities."

)

4.

United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1,

" Calculation of Annual Doses to Man from Routine Releas s of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," October,1977.

5.

United States Nuclear Regulatory Commission, Regulatory Guide 4.8 " Environmental Technical Specifications for Nuclear Power Plants," December,1975.

6.

USNRC Branch Technical Position, " Acceptable Radiological Environmental Monitoring Program," Rev.1, November 1979.

7.

NUREG 0472, " Radiological Effluent Technical Specifications for PWRs," Rev. 3, March 1982.

O i

45

O

^ """"" ' x ^

O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

TABLES - 1998 O

F i

l

[

l l

RADIOLOGICAL ENVIRONAfENTAL A10N1TORING PROGRAAf SUAfMARY l

Q North Anna Nuclear Power Station, Louisa County, Virginia - 1998 Docket No. 50-338/339 Page 1 of 7 Allindicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean h4easure-(Unit)

Type No.

Range Direction Range Range ments Air lodine 1131 624 0.04 (0/572)

N/A N/A (0/52) 0 3

(pCi/m )

Airborne Gross 624 5

18.2(572-572) 06 4.70 mi ESE 19.5(52/52) 19.3(52/52) 0 j

Particulates Beta (7.0-37)

(8.7-35)

(8.5-35) j 3

(1E-03 pCl/m )

Gamma 48 Be-7 48 10 92.9(44/44) 06 0.20 mi NE 106(4/4) 91.9(4/4) 0 (67.1 145)

(78.1 145)

(74.1 122) 1 K-40 48 10 5.73(8/44) 05A 3.20 mi N 14.6(1/4)

(0/4) 0 (2.5-14.6)

O Sr-89 12 3

(0/11)

N/A N/A (0/1)

O Sr-90 12 0.4 (0/11)

N/A N/A (0/1) 0 Ground Gamma 4

Well Water K-40 4

60 (0/4)

N/A N/A (0/0) 0 (pCi/ liter)

Tritium 4 2000 (0/4)

N/A N/A (0/0) 0 Sr-89 1

3 (0/1)

N/A N/A (0/0) 0 Sr-90 1

0.4 (0/1)

N/A N/A (0/0) 0 1

LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

46

l I

i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Q North Anna Nuclear Power Station, Louisa County, Virginia - 1998 Docket No. 50-338/339 Page 2 of 7 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range ments River Gamma 12 Water (pCi/ liter)

K 40 12 200 (0/12)

N/A N/A (0/0) 0 Tritium 4 2000 2600(4/4) 11 5.8 mi.SSE 2600(4/4)

(0/0) 0 (1900-3100)

(1900-3100)

Sr-89 1

3 (0/1)

N/A N/A (0/0) 0 Sr-90 1

0.4 (0/1)

N/A N/A (0/0) 0 0

Precipitation Monthly (pCi/ liter)

Gross 12 4

3.82(12/12) 01 A 0.2 mi.

3.82(12/12)

(0/0)

O Beta (1.2 16)

NE (1.2 16) l Gamma 2

(Semi-Annually)

Tritium 2 2000 (0/2)

N/A N/A (0/0) 0 I

Surface 1-131 24 0.5 (0/12)

N/A N/A (0/12) 0 l

Water I

(pCl/ liter)

Regular Gamma 24 j

Monthlies i

K-40 24 200 (0/12)

N/A N/A (0/12) 0 l

Tritium 8 2000 2675(4/4) 08 1.10 mi 2675(4/4)

(0/4) 0 (1900-3200)

SSE (1900-3200) 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an i

Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

i 47 l

I l

l RADIOLOGICAL ENVIRONhfENTAL Af0NITORING PROGRAAf 0

SUninfARY North Anna Nuclear Power Station, Louisa County, Virginia - 1998 Docket No. 50-338/339 Page 3 of 7 All Indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Nieasure-(Unit)

Type No.

Range Direction Range Range m ents Surface Sr-89 1

(0/1)

N/A N/A (0/1) 0 Water (pCl/ liter)

Regular Sr90 1

(0/1)

N/A N/A (0/1)

O Monthlies Surface Gamma 12 Water (pCl/ liter)

K-40 12 200 (0/24)

N/A N/A (0/0) 0 State Splits

w Tritium 4 2000 3200(2/4)

W33 3200(2/2)

(0/0) 0

s (2300-4100)

(2300-4100)

Sediment Gamma 6

Silt (pCi/kg Be-7 6

(0/4)

NA (0/2) 0 (dry))

K-40 6

200 14925(4/4) 11 5.8 mi 15200(2/2) 12450(2/2) 0 (13200 17200) SSE (13200-17200)

(12400-12500)

Cs-137 6

194 (0/4) 09A 2.20 mi 211(2/2) 211(2/2) 0 NW (106-316)

(106-316)

Ra-226 6

100 1968(4/4) 081.10 mi 2170(2/2) 1720(2/2) 0 (1390-2210)

SSE (2130-2210)

(1540-1900)

Th-228 6

30 1763(4/4) 11 5.8 mi.

1795(2/2) 854(2/2) 0 (1150-2440)

SSE (1150-2440)

(757 950)

Sr-89 3

4.0 (0/2)

N/A N/A (0/1) 0 (Annually)

Sr-90 3

0.8 (0/2)

N/A N/A (0/1)

O n

(Annually) 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

i 48

F l

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

(iO North Anna Nucieer Power station, touise county, vireinie -,998 Docket No. 50-338/339 Page 4 of 7 AllIndicator Control Non-Medium or AN/Alysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported l

Sampled Total Mean Name Distance Mean Mean Wieasure-l (Unit)

Type No.

Range Direction Range Range m ents j

l Soil Gamma 12 (pCi/kg l

(dry))

Be-7 12 609(3/11) 24 22 mi NW 804(1/1) 804(1/1) 0 (566-647) l K-40 12 11286(11/11) 23 0.93 mi SSE 22600(1/1) 11300(1/1) 0 l

(3610-22600)

Cs-134 12 100 (0/11)

N/A N/A (0/1) 0 Cs 137 12 180 350(10/11) 02 5.30 mi 962(1/1) 197(1/1) 0 l

(127-962)

SSW s

Ra-226 12 100 2116(9/11) 01 0.20 mi NE 4170(1/1) 2000(1/1) 0 (1320-4170)

Th-228 12 30 1194(10/11) 01 0.20 mi NE 2410(1/1) 1440(1/1) 0 (501 2410) l Sr-89 12 200 (0/11)

N/A N/A (0/1) 0 (Annually)

Sr-90 12 40 370(1/11) 01 0.20 mi NE 370(1/1)

(0/1) 0 (Annually) l l

f) 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an U

Acceptable Radiological Environmental Monitoring Program, Revision 1. November 1979.

1 49 I

I l

t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

i

'(3 lV North Anna Nuclear Power Station, Louisa County, Virginia - 1998 Docket No. 50-338/339 Page 5 of 7

{

l I

(

All Indicator Control Non-Medium or AN/Alpais Locations Location with Highest Mean Location routine l

Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range m ents Shoreline Gamma 2

Soil (pCi/kg Be-7 2

(0/2)

N/A N/A (0/0) 0 (dry))

K-40 2

200 1536(2/2) 8 1.10 mi SSE 1536(2/2)

(0/0) 0 (672-2400)

(672-2400)

Cs 137 2

40 276(2/2) 8 1.10 mi SSE 276(2/2)

(0/0) 0 (153-399)

(153-399)

Ra-226 2

100 960(1/2) 8 1.10 mi SSE 960(1/2)

(0/0) 0 Th-228 2

30 204(2/2) 8 1.10 mi SSE 204(2/2)

(0/0) 0 (101 308)

(101-308)

Sr-89 1

4.0 (0/1)

N/A N/A (0/0) 0 (Annually)

Sr-90 1

0.8 (0/1)

N/A N/A (0/0) 0 (Annually)

Milk l-131 24 0.5 (0/24)

N/A N/A (0/0) 0 (pCi/ liter)

Gamma 24 K-40 24 100 1261(24/24) 12 8.3 ml. NW 1301(12/12)

(0/0) 0 (1090-1410)

(1180-1410)

Sr-89 8

5 (0/8)N/A N/A (0/0) 0 (Ouarterly)

Sr-90 8

0.8 1.00(8/8) 13 5.60 mi 1.22(4/4)

(0/0) 0 (Quarterly)

(0.72 1.5)

SSW (0.86-1.5 )

1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1079.

50

)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1998 Docket No. 50 338/339 Page 6 of 7 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported 4

i Sampled Total Mean Name Distance Mean Mean Measure-(Unit)

Type No.

Range Direction Range Range ments Fish Gamma 8

pCi/kg (wet)

K-40 8

200 2548(4/4) 08 1.10 mi SSE 2548(4/4) 1785(4/4) 0 (1210-5390)

(1210-5390)

(1440-2090)

Cs-137 8

40 31.1(3/4) 08 1.10 mi.SSE 31.1(3/4)

(0/4) 0 (25.3-39.3)

(25.3-39.3)

Food Gamma 35 Vegetation Dose (pCi/kg Be-7 35 1574(27/28) 16 12.6 mi NW 1776(79) 1776(7/7) 0 (wet))

(280-5820)

(541-6890)

(541 6890) 20714(28/28) 14 1.20 mi 23871(7/7) 16254(7#)

O K 40 35 h,

(9190-48100)

NE (14800-48100) (8060-31200)

Cs-137 35 80 56.5(1/28) 15 1.20 mi NE 56.5(1/7)

(0/7) 0 176(1/28) 15 1.20 mi NE 176(1/7)

(0/7) 0 Th-228 35 l

1 i'

1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

51

r RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 0

SUMMARY

North Anna Nuclear Power Station, Louisa County, Virginia - 1998 Docket No. 50-338/339 Page 7 of 7 l

AllIndicator Control Non-l Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*

Reported Sampled Total Mean Name Distance Mean Mean h4easure-(Unit)

Type No.

Range Direction Range Range m onts Direct Gamma 48 0.2 6.86(44/44) 23 0.93 ml. SSE 9.20(4/4) 6.45(4/4) 0 Radiation Dose (4.8 12.7)

(7.5 12.7)

(5.8-7.4)

(mR/std. month)

(Regular TLDs) l Direct Gamma 12 0.2 5.95(11/11) 01 0.2 mi. NE 8.0(1/1) 5.7(1/1) 0 Radiation Dose (4.5-8.0) l (mR/std. Month)

(Annual TLDs) 1 i

Direct Gamma 286 0.2 7.32(254/254) 17/49 0.22 mi.S 10.0(8/8) 6.31(32/32) 0 l

l.

Radiation Dose (4.2 13.0)

(8.2-11.5)

(4.7-8.4)

(mR/std. Month)

(Sector TLDs) 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

52 l

i

)

O O

AerExoix B DATA TABLES i

i O

L

l l

1 TABLE-B-1: IODINE-131 CONCENTRATIONS IN FILTERED AIR O

North Anna F ower Station, Louisa County, Virginia - 1998 3

pCl/m i2 Signa Page 1 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JANMABY 12/31-01/07

<.01

<.009 s.02

<.02

<.008

<.01

<.007 01/07-01/14

<.02

<.008

<.02

<.01

<.01 01/14-01/21

<.01

<.007

<.t.1

<.01

<.008

<.01

<.01 01/21-01/28

<.01

<.007

<.0i

<.01

<.009

<.006

<.006 01/28-02/04

<.007

<.007 <.007

<.005

<.003

<.006

<.007

<.005

<.01

<.01 FEBRUARY 02/04-02/11

<.01

<.009

<.006

<.01

<.01 02/11-02/18

<.02

<.008

<.02

<.01

<.01-

<.009

<.007 j

02/18-02/25

<.008

<.006

<.007

<.005

<.01

<.01 02/25-03/04

<.01

<.007

<.01

<.008

<.01

<.01 blARCH i

03/04-03/11

<.01

<.007

<.008

<.008.<.008

<.006

<.01

<.007 03/11-03/18

<.009

<.009 <.009

<.006

<.008

<.006

<.01

<.01 4

03/18-03/26

<.01

< 01

<.006

<.007

<.005

<.01

(

03/26-04/02

<.008

<.009

<.009 <.009

<.006

<.01

<.009

<.01

<.01 APRIL 04/02-04/08

<.02

<.01

<.007

<.009

<.008

<.006

<.01

< 01 04/08-04/15

<.01

<.007

<.02

<,02

<.02

<.01

<.008

<.008 04/15-04/22

<.009

<.008 <.008

<.006

<.008

<.006

<.01

<.01 04/22-04/29

<.01

<.006

<.01

<.008

<.01

<.01 l

MAY 04/29-05/06

<.01

<.007

.008

<.008

<.008 <.008

<.006

<.008

<.008 05/06-05/13

<.01

<.006

<.008

<.006

<.008

<.008 05/13-05/20

<.008

<.006

<.008

<.007

<.006

<.01

<.01 05/20-05C7

<.01

<.007

<.009

<.008

<.008 05/27-06/03

<.008

<.006

<.008

<.005

<.006

<.005 JUNE 06/03-06/11

<.01

<.006

<.004

<.009

<.007 06/11-06/17

<.01

<.008

<.009

<.007

<.02

<.02 06/17-06/24

<.01

<.009

<.01

<.009

<.009 06/24-07/01

<.009

<.009 <.009

<.007

<.008

<.006

<.01

<.01 l

I

>O 53 L.

TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR D(.)

North Anna Power Station, Louisa County, Virginia - 1998 3

pC1/m i2 Sigma Page 2 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JULY 07/01-07/08

<.01

<.006

<.007

<.005

<.01

<.01 07/08-07/15

<.01

<.02

<.01

<.007

<.009

<.008

<.007

<.008

<.008 07/15-07/23

<.01

<.006

<.007

<.005

<.006 <.005 07/23-07/29

<.01

<.02

<.01

<.007

<.02

<.01

<.02

<.02 AU.GVSI 07/29-08/05

<.01

<.006

<.01

<.009

<.01

<.01 08/05-08/12

<.01

<.006

<.01

<.009

<.01

<.01 08/12-08/19

<.009

<.007

<.008

<.006

<.01

<.01 08/19-08/26

<.01

<.007

<.008

<.006

<.008

<.008 08/26-09/02

<.01

<.008

<.009

<.007

<.008

<.006 SEPTEMBER 09/02-09/09

<.007

<.005

<.01

<.007

<.008 <.008 09/09-09/16

<.008

<.006

<.008

<.006

<.01

<.01 p,

09/16-09/23

<.007

<.005

<.007

<.005

<.02

<.02 V

09/23-09/30

<.01

<.007

<.01

<.009

<.01

<.01 QCInBE8 09/30-10/07

<.008

<.006

<.008

<.009

<.02

<.01

<.01 10/07 10/14

<.008

<.006

<.008

<.006

<.01

<.01 10/14 10/21

<.01

<.007

<.008

<.005

<.01

<.01 10/21-10/28

<.01

<.01-

<.01

<.006

<.01

<.008

<.01

<.01 NOVEMBER 10/28-11/04

<.01

<.007

<.01

<.007

<.01

<.01 11/04-11/12

<.01

<.006

<.007

<.006

<.007 11/12-11/19

<.01

<.006

<.008

<.005

<.007

<.007 11/19-11/25

<.02

<.03

<.01

<.02

<.01

<.02

<.02 11/25-12/02

<.007

<.008

<.007

<.006

<.005

<.01

<.01 DECEMBER 12/02-12/09 (a) <.08

<.08

<.05

<.04

<.03

<.04

<.04 12/09-12/16

<.007

< 007

<.006

<.007

<.005

<.007

<.007 12/16-12/23

<.02

<.01

<.02

<.01

<.02

<.02 12/23-12/30

<.009

<.007

<.008

<.006

<.01

<.01 i

a(')

Several samples did not meet spec due to the delay of delivery at lab. Carrier mishandled delivery (a) and retumed samples to the station. They were again shipped to lab.

54

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C / A//

O

/ ///

////

u n

)

9000 01 111 2222 a

Q1 Ai D

C O

01 11 N

(

1111 11111 m*

E i

i l

TABLE B-3: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN AIR l

PARTICULATES O

North Anna Power Station, Louisa County, Virginia - 1998 3

1.0 E-03 pCl/m i2 Sigma Page 1 of 3 First -

Second Third Fourth Quarter Quarter -

Quarter Quarter Average Station -

Nuclide 12/31-04/01 04/01-07/01 07/01-09/30 09/30-12/30 i 2 s.d.

STA-01 Sr-89 (a)

< 0.7 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

Be-7 136 i 14 79.1 i 7.9 99.3 i 9.9 71.2 i 7.1 96.4 i 57.9 K-40

<5 3.72 i 1.97

<5

< 10 3.72 i 1.97 Co-60

< 0.3

< 0.3 Ru 103

< 0.7

< 0.4

< 0.4 Cs-134

< 0.2

< 0.3

< 0.3 Cs 137

< 0.2

< 0.3

< 0.3 Th-228

< 0.4

< 0.5

< 0.4 STA-02 Sr-89 (a)

< 0.7 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

Be-7 107 i 11 75.7 i 7.6 88.318.8 74.8 i 7.5 86.5 i 30.0 K-40

<4

<7

<4

. Co-60

< 0.2

< 0.3

< 0.3 Ru-103

< 0.6

< 0.3

< 0.2 Cs-134

< 0.2

< 0.3

< 0.2 Cs-137

< 0.2

< 0.3

< 0.2 O

Th-228

< 0.3

< 0.4

< 0.4 STA-03 Sr-89 (a)

< 0.7 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

Be-7 114 i 11 75.1 7.5 90.1 i 9.0 67.6 i 6.8 86.7 i 40.9 K 40

<4

< 10 5.26 2.29

<6 5.26 i 2.29 Co-60

< 0.2

< 0.3

< 0.2 Ru-103

< 0.6

< 0.4

< 0.3 Cs-134

< 0.2

< 0.3

< 0.2 Cs-137

< 0.3

< 0.2

< 0.3

< 0.2 Th-228

< 0.3

< 0.4

< 0.3 STA-04 Sr-89 (a)

<1 (a)

(a)

Sr 90 (a)

< 0.2 (a)

(a)

Be-7 127 i 13 90.2 i 9.0 105 i 10 89.9 i 9.0 103 i 35 K-40

<7

<4

<4 Co-60

< 0.3

< 0.2

< 0.3 Ru-103

< 0.9

< 0.3

< 0.3 Cs 134

< 0.3

< 0.2

< 0.3 Cs-137

< 0.3

< 0.2

< 0.3 Th-228

< 0.5

< 0.4

< 0.5 O

All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter samples.

59

f-1 I

t TABLE B-3: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN AIR i

PARTICULATES lO NoMnna Power Station, Louisa County, Virginia - 1998 i

1.0 E-03 pCi/m3 i2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/31-04/01 04/01-07/01 07/01-09/30 09/30-12/40 i 2 s.d.

j STA-05 Sr-89 (a)

<1 (a)

(a)

Sr-90 (a)

< 0.2 (a)

(a)

Be-7 120 i 12 75.3 i 7.5 87.5 i 8.8 69.7 i 7.0 88.1 i 45.0 K-40

<5

<6 3.72 i 1.78

< 10 3.72 i 1.78 Co-60

< 0.3

< 0.2

< 0.3 Ru 103

< 0.7

< 0.3

< 0.4 Cs-134

< 0.3

< 0.2

< 0.3 Cs 137

< 0.2

< 0.3 Th-228

< 0.5

< 0.3

< 0.4

< 0.4 STA 05A Sr-89 (a)

< 0.8 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

Be-7 104 i 10 91.0 i 9.1 109 i 11 86.9 i 8.7 97.7 i 20.9 K-40 14.6 i 2.9

<5

<4

<4 14.6 i 2.9 Co-60

< 0.3

< 0.2

< 0.2 Ru-103

< 0.8

< 0.3

< 0.4

< 0.3 Cs-134

< 0.3

< 0.2

< 0.3

< 0.2 Cs-137

< 0.3

< 0.2

< 0.3

< 0.2 Th-228

< 0.4

< 0.5

< 0.4 STA-06 Sr-89 (a)

< 0.7 (a)

(a)

Sr-90 (a)

< 0.1 (a)

(a)

Be-7 145 i 14 91.8 i 9.2 109 i 11 78.1 i 7.8 106i 58 K-40 4.491 1.87

<5

<5 4.49 i 1.87 Co-60

< 0.2

< 0.3

< 0.2

< 0.2 Ru-103

< 0.7

< 0.3

< 0.3 Cs 134

< 0.2

< 0.2 Cs-137

< 0.2

< 0.3

< 0.2 Th-228

< 0.5

< 0.4

< 0.5

< 0.3 STA-07 Sr-89 (a)

< 0.7 (a)

(a)

Sr 90 (a)

< 0.1 (a)

(a)

Be-7 112i 11 67.1 i 6.7 85.7 i 8.6 84.6 i 8.5 87.4 i 37.0 K-40 7.66 i 3.10 2.5011.14

<7

<4 5.08 i 7.30 Co-60

< 0.3

< 0.2

< 0.3

< 0.3 Ru-103

< 0.8

< 0.2

< 0.3

< 0.3 Cs 134

< 0.3

< 0.2

< 0.3 Cs 137

< 0.3

< 0.2

< 0.3

< 0.2 Th-228

< 0.4

< 0.4 I

l OG All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter samples.

60

I TABLE B-3: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN AIR

\\

PARTICULATES

]

North Anna Power Station, Louisa County, Virginia - 1998 3

I 1.0 E-03 pCi/m i 2 Sigma Page 3 of 3 First Second Third Fourth l

Quarter Quarter Quarter Quarter Average i

Stati:n Nuclide 12/31-04/01 04/01-07/01 07/01-09/30 09/30-12/30 i 2 s.d.

STA 21 Sr-89 (a)

< 0.7 (a)

(a)

Sr-90 (a)

< 0.08 (a)

(a)

Be-7 116 i 12 75.4 i 7.5 100110 67.6 i 6.8 89.8 i 44.9 K 40

<4

<7

<5

<3 Co-60

< 0.3

< 0.2 Ru-103

< 0.6

< 0.3

< 0.2 Cs-134

< 0.2

]

Cs 137

< 0.2

< 0.3

< 0.2

< 0.2 i

Th-228

< 0.3

< 0.5

< 0.4 STA-22 Sr-89 (a)

< 0.7 (a)

(a)

Sr-90 (a)

< 0.2 (a)

(a)

Be-7 104 i 10 76.5 i 7.6 84.6 i 8.5 69.2 i 6.9 83.6 i 30.0 K-40

<4

<5

<4

<4 Co-60

< 0.2

< 0.3

< 0.2

< 0.2 Ru-103

< 0.5

< 0.3

< 0.2

< 0.3 Cs 134

< 0.2

< 0.3 Cs-137

< 0.2

< 0.3

< 0.2

< 0.3 Q

Th-228

< 0.3

< 0.4

< 0.3

< 0.4

)

STA-23 Sr89 (a)

<1 (a)

(a)

Sr-90 (a)

< 0.2 (a)

(a)

Be-7 142i 14 83.1 i 8.3 92.0 i 9.2 69.9 i 7.0 96.8 i 63.0 K-40

<7

<5 3.9012.28

<4 3.901 2.28 j

Co-60

< 0.2

< 0.3

< 0.2 Ru-103

< 0.7

< 0.3

< 0.4

< 0.3 Cs-134

< 0.3

< 0.2

< 0.3

< 0.2 Cs 137

< 0.3

< 0.2

< 0.3

< '3 Th-228

< 0.4

<03

< 0.4

< 0.3 STA-24 Sr-89 (a)

<1 (a)

(a)

Sr-90 (a)

< 0.2 (a)

(a)

Be-7 122 i 12 80.3 i 8.0 91.3 i 9.1 74.117.4 91.9 i 42.6 K-40

<7

<4

<6

< 10 Co-60

< 0.3

< 0.2

< 0.3 Ru-103

< 0.8

< 0.3

< 0.4 Cs 134

< 0.3

< 0.2

< 0.3

< 0.3 Cs-137

< 0.3

< 0.2

< 0.3 Th-228

< 0.4

< 0.3

< 0.4

< 0.S l

l B

l All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter samples.

I l

61 t

1 TABLE B-4: GROSS BETA, TRITIUM AND GAMMA EMITTER

CONCENTRATIONS IN PRECIPITATION Station 01A -(On Site)

North Anna Power Station, Louisa County, Virginia - 1998 pCl/li 2 Sigma Page 1 of 1 Collection Dates Gross Beta Rainfall (inches) i 12/31/97-01/28/98 2.0 i 0.6 5.86 j

01/28/98-02/25/98 1.2 i 0.5 8.76 02/25/98-03/26/98 2.2 i 0.6 6.30 03/26/98-04/29/98 1.9 i 0.6 5.26 04/29/98-05/27/98 1.610.6 4.62 05/27/98-OfV24/98 3.110.6 5.81 07/01/98-07/29/98 2.4 i 0.6 0.92 07/29/98-08/26/98 16 t 1 3.25 08/26/98-09/30/98 5.0 i 1.2 1.12 l

09/30/98-10/28/98 2.0 i 0.6 1.02 10/28/98 11/25/98 3.6 1 1.1 0.80 11/25/98-12/30/98 4.8 i 0.8 2.59 Average i 2 s.d.

3.8 i 8.1 l

l l

SEMI.4NNUAL PRECIPITATION COMPOSITES 12/31/97-06/24/98 07/01/98-12/30/98 Be-7 = < 40 Be-7 = < 30 H-3 = < 100 H-3

< 200

=

1 All gamma emitters other than those listed were <LLD.

62

4 6

0 0

0 0 0 0

I 1

5 3

6 9

2 2

0 1

i 4

8 4

0 I

1 1

2 2

5 6

7 1

8 9

2 2

1 i 1 i i i 0 i i 0

l 3

5 0

9 2

6 0 0 0 0 7

h 0

g o

1 4

5 5

8 4

4 0

4 1

1 T

4 S

6 7

3 8

< 9 2

2 0

41 2

2 1

1 1

2 1

2 0

0 0 0 0 0 0 0 0 0 9 8

6 6

2 7

41 3

8 8

8 4

3 0

4 1

5 4

5 6 0 5

6 6

5 2

0 0

1 1

0 i 1 1 1 i 0 i 1 1 1 a

9 1

0 0

0 0 0 0 0

0 0 0 4

R 7

2 0

5 7

8 0

1 4

0 0

0 1

1 3

4 8

6 6

5 3

I 2

2 2

3 4

1 1

2 3

9 6 4

9 4

6 7

8 9

%2 4

3 3

4 3

3 3

4 7

5 3

05 i 1 1 i i i 1 1 1 1 1 i

1 2

2 7

5 7

2 2

6 7

1 7

2 2

0 2

6 0

3 1

7 9

6 8

%5 s

3 4

3 1

1 2

4 C

1 1

3 L

I 4

O 3

0 0 0 0

0 0 0 0 0 0 0 0 S

1 5

4 3

4 5

4 7

6 4 5

5 4

s N

I C

SR ET 8

I 0

9 M

2 0

0 0

0 9

E a 0

0 0 0

0 0 0 0 0 0 0 0 5

1 m

6 4

8 0

5 2

3 4

3 7

3 1

1 5

- A D A M ig 1

9 4 5

1 8

9 5

1 1

2 1

1 0

S 4

1 i 1 i i 1 1 1 i i 1 i i

N M 2

UUE N A i K

0 0

1 0

0 0 0 0

0 0

0 8

L A G g

2 3

8 8

3 1

2 6

9 1

2 1

2 0

8 0

0 8

7 1

6 3

8 Fd 6

9 4

4 5

8 9 3 2 7

1 A D O iC 1

1 1

1 2

1 1

T 1

R S

p O N N O 69 IT 1

7 1

1 6

3 3

2 A

1 R

7 0

3 2

0 3

0 0 0 0 0

0 3

0 0 0

0 0 0 i

0 i 1 0 i

4 6

5 4 4

4 1

T e

4 4

4 8

N R

7 6

4 4

6 0

5 E

1 6

5 6

8 6

CN O

C 9

1 0

2 2

0 0 0 0 0

0 0 0 0 0 0 1

09 0

0 0

0 0 0 0 0 0

1 1

3 2

2 4

4 4

2 2

3 2

2 0

0 r

7 S

7 3

3

.D 0

0 0

L 9

0 0

0 0 0

0 0

0 0 9 0 0

L 8

10 0

0 0

9 8

6 5

1 9

6 7

1 1

1 e

r r

S ew s

r e

t it m

e S

8 8

a LE 9

S 6 9

S 6 8 S S S 9

S m

/

LT 5

5 5

1 5

5 5

m OA I

/ / / / / / / / / / /

a 1

1 1

1

/

CD 7

7 7

7 g

0 0 0 0 0 0 0 0 0 0 0 0 re h

N o

t U

O e

lA g.

l IT a d.

rs A

e A

v2 T

1 2

3 4

5 5

6 7

1 2

3 4

S 0 0 0 0 0 0 0 0 2

2 2

2 A1 m

l

)

i TABLE B-6: GAMMA EMITTER *, STRONTIUM AND TRITIUM

^

CONCENTRA TIONS b

IN GROUND AND WELL WATER l

North Anna Power Station, Louisa County, Virginia - 1998 pCl/l i 2 Sigma Page 1 of 1 Cellection Dstes Sr-89 Sr 90 H-3 B e-7 K-40 1-131 B a-14 0 Th-228 STATION Q1A 04/02/98 (a)

(a)

< 100

< 30

< 40

< 0.2

<5

<6 06/24/98

< 0.8

< 0.3

< 200

< 30

,:70

< 0.3

<5

<6 09/30/98 (a)

(a)

< 200

< 30

< 50

<7

<6

<6 12/30/98 (a)

(a)

< 300

< 30

< 50

< 0.2

<5

<6 All gamma emitters other than those listed were <LLD.

(a) Strontium-89/90 analyses performed only on second quarter sample.

)

TABLE B-7: GAMMA EMITTER *, STRONTIUM AND TRITIUM

}

CONCENTRA TIONS IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1998 pCl/l i 2 Sigma Page 1 of 1 C:llection Dates Sr-89 S r-90 H-3 Be 7 K-40 1131 Cs-137 Ba-140Ra-226 Th 228 STATION - 11 01/14/98 (a)

(a) 3000 i 200

< 20

< 4C

< 0.2

<4

< 60

<5 02/16/98 (a)

(a)

(b)

< 30

< 50

< 0.3

<4

<6

< 80

<7 03/19/98 (a)

(a)

(b)

< 30

< 80

< 0.3

<3

<4

< 50

<5 04/16/98 <3

< 0.3 1900 i 200

< 30

< 50

< 0.2

<4

<5

< 80

<7 05/12/98 (a)

(a)

(b)

< 30

< 80

< 0.3

<3

<4

< 60

<5 06/17/98 (a)

(a)

(b)

< 30

< 80

< 0.6

<3

<5

< 60

<5 07/14/98 (a)

(a) 2400 1 200

< 30

< 90

< 0.2

<4

<6

< 60

<6 08/17/98 (a)

(a)

(b)

< 30

< 90

< 0.4

<4

<6

< 70

<6 09/17/58 (a)

(a)

(b)

< 50

< 100

< 10

<5

<9

< 80

<7 l

10/16/93 - (a)

(a) 3100 i 200

< 40

< 90

<9

<4

<7

< 70

<6 11/13/98 (a)

(a)

(b)

< 30

< 90

< 0.6

<4

<6

< 70

<7 12/16/98 (a)

(a)

(b)

< 40

< 100

< 0.3

<5

<6

< 80

<8 Average i 2 s.d.

2600 i 1120 All gamma emitters other than those listed were <LLD, (I)

Sr 89/90 analyses performed only on second quarter samples.

'(b)

Tritium analysis performed on quarterly composite.

64 l

l l

TABLE B-8: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS IN SURFACE WATER North Anna Power Station, Louisa County, Virginia - 1998 pCl/l i 2 Sigma Page 1 of 1 C:llection Dctes Sr-89 Sr-90 H3 B e-7 K 40 1-131" Cs 137 Ba-140 Ra-226 Th 228 STATION - 08 01/14 (a)

(a) 2600 i 200 < 30

< 50

< 0.2

<4

<5

< 70

<6 02/16 (a)

(a)

(b)

< 30

< 60

< 0.3

<4

<6

< 80

<7 03/19 (a)

(a)

(b)

< 30

< 70

< 0.3

<3

<7

< 60

<5 04/16

<4

< 0.4 1900 i 200

< 30

< 50

< 0.2

<3

<5

< 70

<7 05/12 (a)

(a)

(b)

< 20

< 40

< 0.2

<3

<4

< 50

<4 06/17 (a)

(a)

(b)

< 30

< 40

< 0.5

<3

<5

< 70

<6 07/14 (a)

(a) 3200 i 200

< 30

< 50

< 0.2

<3

<5

< 80

<6 08/17 (a)

(a)

(b)

< 30

< 90

< 0.3

<4

<7

< 70

<6 09/17 (a)

(a)

(b)

< 30

< 60

< 10

<4

<7

< 60

<5 10/16 (a)

(a) 3000i200

< 30

< 50

< 10

<3

<7

< 80

<7 11/13 (a)

(a)

(b)

< 30

< 50

< 0.6

<4

<6

< 80

<7 12/16 (a)

(a)

(b)

< 30

< 50

< 0.3

<4

<5

< 70

<7 f3 Avg.

2675 i 1147 k/

i 2. s.d.

STATION - 09A 01/14 (a)

(a)

< 100

< 30

< 60

< 0.2

<4

<5

< 60

<5 02/16 (a)

(a)

(b)

< 30

< 70

< 0.3

<3

<5

< 60

<5 03/19 (a)

(a)

(b)

< 30

< 50

< 0.3

<3

<5

< 50

<4 04/16

<4

< 0.3

< 200

< 30

< 70

< 0.3

<4

< 60

<6 05/12 (a)

(a)

(b)

< 20

< 50

< 0.3

<3

<4

< 70

<6 06/17 (a)

(a)

(b)

< 20

< 40

< 0.5

<3

<4

< 60

<5 07/14 (a)

(a)

< 300

< 30

< 40

< 0.3

<3

<4

< 70

<6 08/17 (a)

(a)

(b)

< 30

< 60

< 0.4

<3

<6

< 60

<6 09/17 (a)

(a)

(b)

< 30

< 50

<8

<4

<6

< 70

<6 10/16 (a)

(a)

< 200

< 30

< 60

< 10

<4

<8

< 80

<8 11/13 (a)

(a)

(b)

< 30

< 50

< 0.5

<3

<5

< 70

<6 12/16 (a)

(a)

(b)

< 30

< 50

< 0.3

<4

< 60

<5 All gamma emitters other than those listed were <LLD.

l 131 by radiochemistry

(;) Analysis performed only with second quarter.

(b) Analysis performed quarterly.

l 65 I

l TABLE B-9: GAMMA EMITTER

AND TRITIUM CONCENTRATIONS IN SURFACE WATER lf}

l State-Spilt Samples l

North Anna Power Station, Louisa County, Virginia - 1998 pCl/l i 2 Sigma Page 1 of 1 l

Collection Dates H-3 B e-7 K-40 1-131 Cs-137 B a-14 0 Ra-226 Th 228 STATION - W-2Z 01/31

< 200

< 40

< 50

<4

<5

< 10

< 70

<6 02/28 (a)

< 40

< 50

<2

<4

<8

< 80

<7 03/31 (a)

< 30

< 50

< 0.5

<3

<6

< 70

<6 04/30

< 100

< 40

< 50

<7

<4

< 20

< 70

<7 05/31 (a)

< 30

< 70

<2

<3

<8

< 60

<5 06/30 (a)

< 30

< 50

<3

<4

<9

< 70

<5 07/31 (b)

Avg.

i 2 s.d.

l STATION - W-33 01/31 4100i200

< 40

< 60

<5

<4

< 10

< 60

<5 02/28 (a)

< 40

< 90

<2

<4

<9

< 70

<6 03/31 (a)

< 30

< 100

< 0.5

<4

<7

< 70

<6 04/30 2300i200

< 40

< 50

<9

<3

< 20

< 70

<7 05/31 (a)

< 30

< 50

<1

<3

<8

< 70

<6 06/30 (a)

< 40

< 60

<3

< 10

< 60

<5 07/31 (b) l Avg.

3200 i 2546 i 2 s.d.

1 All gamma emitters other than those listed were <LLD.

(a) Tritium analysis performed on the first monthly composite of each quarter, j

O (b) State sampling discontinued in third quarter 1998, a

1 66 l

l

)

f 1

I TABLE B-10: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN n

SEDIMENT SILT v

l North Anna Power Station, Louisa County, Virginia - 1998 1

pCl/kg i 2 Sigma Page 1 of 1 STA-08 STA-09A STA-11 STA-08 STA-09A STA-11 Average Nuclide 02/16 02/16 02/16 08/28 08/28 08/28 i 2 Sigma Sr-89 (a)

(a)

< 400

< 300 Sr-90 (a)

(a)

< 100

< 1 CO Be-7

< 400

< 300

< 500

< 400 K-40 13400 1300 12500 1 1300 17200 i 1700 159001 1600 12400i 1200 132001 1300 14100 1 3960 Mn-54

< 40

< 30

< 40

< 50

< 40 l

Co-58

( 40

< 30

< 60

< 40 Co-60

< 40

< 30

< 50

< 30 Cs-134

< 50

< 40

< 60

< 50 Cs-137

< 50 1061 32

< 30

< 40 d16152

< 40 2111 297 Ra-226 2130 1 780 1540 1 510 21401 500 2210 i 550 19001 620 13901 530 1885i 690 Th-228 1710i 170 757 i 76 1150i 120 17501 170 9501 95 2440t 240 1460 1 1251 1

All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

l l

TABLE B-11: GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 1998 pCl/kg i 2 Sigma Page 1 of 1 Station-08 Station-08 Average Nuclide 02/16/98 08/28/98 2 Sigma l

1 l

Sr-89 (a)

< 400 l

Sr-90 (a)

< 100 l

Be-7

< 200

< 300 K-40 672e 212 2400 i 310 1536 i 2444 Mn-54

< 20

< 20 Co-58

< 20

< 30 Co-60

< 20

< 30 Cs-134

< 20

< 30 Cs-137 1531 28 399 i 40 276 i 348 Ra-226

< 500 960i 346 960 i 346 Th-228 101 i 28 308.:. 31 204i 293 k

All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed annually.

67

TABLE B-12:

GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN MILK 9

North Anna Power Station, Louisa County, Virginia - 1998 pCl/l i 2 Sigma Page 1 of 2 MONTH NUCLIDE STATION-12 STATION-13 JANUARY Sr-89 (a)

(a)

Sr-90 (a)

(a)

K 40 1300 130 1130 i 110 Cs-137

<3

<5 l-131

< 0.3

< 0.3 FEBRUARY Sr-89 (a)

(a)

Sr-90 (a)

(a)

K-40 1370 i 140 1320 i 130 Cs-137

<4

<5 l-131

< 0.3

< 0.3 MAPCH Sr 89

<3

<5 Sr90 0.7210.21 1.5 0.3 K 40 12601 130 1130 110 Cs-137

<3

<3 1-131

< 0.3

< 0.3 APRIL Sr89 (a)

(a)

Sr-90 (a)

(a)

K-40 1340 i 130 1090 i 110 Cs 137

<4

<5 l131

< 0.2

< 0.3 MAY Sr-89 (a)

(a)

Sr90 (a)

(a)

K-40 1200 i 120 1220 i 120 Cs-137

<4

<4 l-131

< 0.3

< 0.2 JUNE Sr-89

<3

<2 Sr 90 0.7510.23 1.3 i 0.2 K-40 1280 i 130 1140 i 110 Cs-137

<4

<4 l-131

< 0.4

< 0.5 All gamma emitters other than those listed were <LLD.

(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.

68 2

TABLE B-12:

GAMMA EMITTER

AND STRONTIUM CONCENTRATIONS IN MILK North Anna Power Station, Louisa County, Virginia - 1998 pCi/l i 2 Sigma Page 2 of 2 MONTH NUCLIDE STATlON-12 STATlON-13 JULY Sr89 (a)

(a)

Sr 90 (a)

(a)

K 40 1330 1 130 1250 i 120 Cs 137

<4

<4 l-131

< 0.3

< 0.3 AUGUST Sr-89 (a)

(a)

Sr-90 (a)

(a)

K 40 12701 130 1310 i 130 Cs-137

<4

<3 1131

< 0.3

< 0.3 SEPTEMBER St-89

<2

<3 Sr-90 0.8610.20 1.2 i 0.3 K-40 1410 1 140 1280 1 130 Cs-137

<5

<4 I131

< 0.5

< 0.6 OCTOBER St89 (a)

(a)

Sr-90 (c)

(a)

K-40 1270i 130 1240 1 120 Cs 137

<4

<4 l131

< 0.2

< 0.4 NOVEMBER Sr89 (a)

(a)

Sr-90 (a)

(a)

K 40 1400i 140 1200 1 120 Cs 137

<3

<4 l-131

< 0.3

< 0.4 DECEMBER Sr-89

<3

<1 Sr90 0.78 i 0.30 0.86 i 0.16 K-40 1180 1 120 1340 i 130 Cs-137

<4

<3 1-131

< 0.2

< 0.3 Average Sr-89 2 s.d.

Sr-90 0.78 i 0.12 1.22 i 0.54 K-40 1301 i 145 1221 i168 Cs-137 l-131 OQ All gamma emitters other than those listed were <LLD.

(I) Strontium 89/90 analyses performed on the last monthly sample of each quarter.

69 l

i

TABLE B 13: GAMMA EMITTER

CONCENTRATIONSIN FISH Q

North Anna Power Station, Louisa County, Virginia - 1998 pCi/kgi2 SI ma Page 1 of 1 D

C:llection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 02/11 08 Fish (a) 5390 i 540

< 30

< 30 02/11 25 Fish (a) 1960 i 210

< 20

< 20 02/11 08 Catfish (b) 1720 i 200

< 20

< 20 39.3 i 17.1 02/11 25 Catfish (b) 1650 i 170

< 20

< 20 08/25 25 Catfish (b) 1440 i 170

< 20

< 20 08/26 08 Catfish (b) 18701 190

<10

< 10 25.319.0 08/25 25 Fish (a) 20901 230

< 20

< 20 09/01 08 Fish (a) 1210i 150

<10

< 10 28.8 i 12.7 Avg.

2166i 2666 31.1 i 14.6 i 2 s.d.

All gamma emitters other than those listed were <LLD.

(t) Non-bottom dwelling species of gamefish.

i (b) Bottom dwelling species of fish.

l 70 L

l TABLE B-14: GAMMA EMITTER

CONCENTRATIONS IN FOODNEGETATION G

North Anna Power Station, Louisa County, Virginia - 1998 0

pCl/kg i 2 Sigma Page 1 of 2 Collection Date Be-7 K-40 1131 Ru-103 Cs-134 Cs-137 Ra 226 Th-228 STATION 14 04/15 5820 i 580 29200 i 2000

< 60

< 20

< 30

< 400

< 40 05/20 1500 i 440 220001 2200

< 30

< 70

< 60

< 1000

< 90 06/17 1340 i 440 48100 1 4800

< 60

< 80

< 60

< 900

< 90 07/15

< 90 14800 i 1500

< 10

<9

< 200

< 10 08/20 280 i 73 19200i 1500

< 30

< 10

< 200

< 20 09/16 5271 117 17200 i 1700

< 60

<10

< 10

< 300

< 20 10/21 1080i 160 16600 i 1700

< 10

< 20

< 400

< 30 STATION 15 04/15 3640 1 360 22300 i 2200

< 60

< 30

< 30 56.5128.4

< 500 176 i 43 05/20 2740 i 420 158001 1600

< 60

< 50

< 800 e 80 06/17 1950 i 310 30300 i 3000

< 60

< 50

< 40

< 600

< 50 07/15 349 i 117 17900 i 1800

<10

< 20

< 300

< 20 A

08/20 759i 111 268001 2700

< 30

< 10

< 200

< 20 j

09/16 324 i 96 16700i 1700

< 60

< 20

< 10

< 200

< 20 10G1 1280 i 380 114001 1100

< 10

< 60

< 50

< 900

< 80 STATION 16 04/15 1880 230 31200 i 3100

< 30

< 500

< 40 05/20 752 i 243 8620 i 860

< 50

< 40

< 30

< 600

< 50 06/17 6890 i 690 11600 1200

< 60

< 40

< 800

< 70 07/15 618 i 162 18500 i 1900

< 10

< 20

< 300

< 30 08/20 826 139 20000 i 2000

< 30

< 20

< 300

< 30 09/16 541 i 120 15800i 1600

< 60

< 20

< 10

< 200

< 20 10/21 925 i 436 80C9 810

<10

< 70

< 60

< 1000

< 90 l

f]

All gamma emitters other than those listed were <LLD.

Samples for Jan, Feb, Mar, Nov, and Dec not collected due to seasonal unavailability.

i 71 l

L

D TABLE B-14: GAMMA EMITTEW CONCENTRATION IN FOODNEGETATION U

North Anna Power Station, Louisa County, Virginia - 1998 pCi/kg 12 Sigma Page 2 of 2 Collection Date Be 7 K-40 b131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 STATION 21 04/15 2870 i 290 17300 i 1700

< 30

< 20

< 400

< 30 05/20 39901 400 21000 i 2100

< 60

< 30

< 600

< 50 06/17 1340 i 140 31700 i 3200

< 50

< 20

< 300

< 20 07/15 304i 103 16700i 1700

< 40

< 20

< 10

< 200

< 20 08G0 592 i 84 13800 i 1400

< 30

< 10

< 200

< 20 09/16 425 i 91 153001 1500

< 50

< 10

< 200

< 20 10/21 1310 i 320 21800i 2200

<10

< 40

< 600

< 60 STATION 23 04/15 2590 260 13200 1 1300

< 30

< 20

< 300

< 30 f-05/20 2800 i 310 9190 i 920

< 50

< 40

< 30

< 600

< 50

.\\

06/17 1850 i 250 41700 i 4200

< 50

< 40

< 30

< 400

< 40 07/15 432i 155 229001 2300

< 50

< 20

< 300

< 30 08/20 318 i 95 14800 i 1500

< 40

<10

< 10

< 200

< 20 09/16 527 121 19500 1900

< 60

< 20

< 300

< 20 10/21 1550 i 430 12800 i 1300

< 20

< 60

< 900

< 90 Average 1615i 3129 19822 i 17550 56.5 28.4 176 i 43 i 2 s.d.

l f%)

All gamma emitters other than those listed were <LLD.

t,,'

Samples for Jan, Feb, Mar, Nov, and Dec not collected due to seasonal unavailability.

72

r I

l I

TABLE B-15: DIRECT RADIATION MEASUREMENTS -- QUARTERLY AND ANNUAL TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1998 mR/Std. Month (30.4 days)i 2 Sigma Page 1 of 1

)

l l

Station First Qtr Second Qtr Third Qtr Fourth Otr Quarterly Annual TLD l

Number 01/07/98 04/02/98 07/01/98 10/07/98 Average 06/02/97 04/02/98 07/01/98 10/07/98 01/13/99 06/01/98 01 8.5 1 0.2 8.8 i 0.2 7.9 i 0.1 9.5 1 0.1 8.7 i 1.3 8.0 i 0.1 l

02 5.0 0.0 5.5 i 0.1 5.2 i 0.2 6.5 i 0.2 5.6 1 1.3 4.9 i 0.3 03 4.8 i 0.2 5.2 i 0.1 5.1 i 0.2 6.5 1 0.1 5.4 i 1.5 4.5 i 0.1 l

i 04 5.1 i 0.1 5.6 i 0.2 5.2 i 0.1 6.5 i 0.2 5.6 i 1.3 4.8 i 0.1 05 6.0 i 0.1 6.6 i 0.1 6.5 i 0.2 7.9 i 0.2 6.8 i 1.6 6.0 1 0.2 l

05A 5.6 i 0.0 6.0 1 0.2 5.6 i 0.1 7.2 i 0.2 6.1 i 1.5 5.2 1 0.1 06 7.3 i 0.2 7.7 i 0.1 7.8 i 0.2 8.9 i 0.3 7.9 i 1.4 7.1 i 0.8 l

07 5.8 i 0.1 6.6 1 0.2 6.1 i 0.2 7.3 1 0.1 6.2 i 1.7 5.6 i 0.2 21 5.5 0.3 5.9 i 0.0 6.0 1 0.1 7.4 i 0.1 6.2 i 1.7 5.5 1 0.2 22 7.0 i 0.2 7.7 i 0.2 7.2 i 0.1 8.5 i 0.1 7.6 i 1.3 6.5 i 0.3 23 7.5 i 0.2 8.3 i 0.1 8.3 1 0.3 12.7 i 0.3 9.2 i 4.7 7.3 1 0.2 24 5.8 i 0.1 6.4 1 0.1 6.2 1 0.1 7.4 i 0.2 6.5 i 1.4 5.7 i 0.1 Average 6.2 2.3 6.7 i 2.3 6.4 i 2.3 8.0 i 3.5 6.8 i 3.0 5.9 i 2.2 i 2 s.d.

l O

73

r TABLE B-16: DIRECT RADIATION MEASUREMENTS -

a SECTOR QUARTERLY TLD RESULTS i

')

North Anna Power Station, Louisa County, Virginia - 1998 mR/Std. Month (30.4 days) i 2 Sigma Page 1 of 2 Station First Qtr.

Second Qtr.

Third Qtr.

Fourth Qtr.

Average Number 01/07-04/02 04/02-07/01 07/01-10/07 10/07-01/13 i 2 s.d.

N-1 6.4 i 0.2 7.3 i 0.2 7.1 i 0.3 8.2 i 0.3 7.3 i 1.5 N2 5.1 2 0.2 5.9 i 0.1 5.9 i 0.1 7.0 i 0.2 6.0 i 1.6 NNE-3 8.810.3 9.4 i 0.3 9.6 i 0.2 10.5 i 0.3 9.6 i 1.4 NNE-4 5.6 i 0.1 6.5 i 0.0 6.8 i 0.3 7.8 1 0.1 6.7 1 1.8 NE 5 7.610.1 7.9 i 1.6 8.3 i 0.5 9.7 i 0.7 8.4 i 1.9 NE 6 5.3 1 0.1 6.110.4 6.410.1 7.2 i 0.1 6.3 i 1.6 ENE-7 6.6 i 0.3 7.5 i 0.2 7.6 i 0.3 8.8 i 0.1 7.6 i 1.8 ENE-8 5.3 i 0.1 6.110.1 6.0 i 0.2 (a) 5.8 i 0.9 l

E-9 6.8 i 0.3 7.5 i 0.3 8.3 i 0.2 9.1 i 0.3 7.9 i 2.0 E 10 5.9 1 0.2 6.8 i 0.1 7.0 1 0.4 11.210.4 7.7 i 4.7 ESE 11 6.0 i 0.2 6.9 i 0.2 7.1 i 0.1 7.9 1 0.3 7.0 i 1.6 ESE 12 6.510.2 7.310.1 8.0 i 0.3 9.0 i 0.1 7.7 i 2.1 SE 13 6.3 i 0.2 7.2 i 0.2 7.2 1 0.2 8.1 i 0.2 7.2 i 1.5 SE-14 8.5 i 0.1 9.5 i 0.3 9.4 i 0.3 10.6 i 0.3 9.5 i 1.7 SSE 15 6.8 i 0.1 7.810.1 8.110.5 8.9 1 0.2 7.9 i 1.7 SSE 16 5.110.0 6.1 i 0.1 6.1 i 0.2 6.9 i 0.2 6.1 i 1.5 S-17 8.210.3 10.1 i 0.1 10.6 i 0.4 11.1 i 0.4 10.0 2.5 S 18 4.5 i 0.2 5.1 i 0.1 5.310.1 6.1 1 0.1 5.3 i 1.3 m

'J SSW 19 7.3 i 0.3 8.510.3 9.110.5 9.7 1 0.3 8.7 i 2.0 SSW-20 4.210.1 5.1 i 0.2 5.1 1 0.1 6.0 i 0.2 5.1 i 1.5 SW 21 5.4 1 0.3 6.210.1 6.3 i 0.3 7.3 i 0.2 6.3 i 1.6 SW 22 6.310.2 7.3 i 0.3 7.7 i 0.3 8.3 1 0.1 7.4 i 1.7 WSW 23 7.7 i 0.2 8.7 0.1 8.4 i 0.2 9.3 1 0.2 8.5 i 1.3 WSW-24 6.0 i 0.6 7.210.3 7.1 i 0.1 8.2 i 0.4 7.1 i 1.8 W 25 7.9 i 0.1 8.9 i 0.2 9.1 i 0.3 9.9 i 0.2 9.0 i 1.6 W 26 5.010.1 5.8 i 0.1 5.8 1 0.5 6.8 i 0.3 5.9 t 1.5 WNW-27 5.2 i 0.2 6.010.2 6.1 i 0.1 7.2 i 0.4 6.1 i 1.6 WNW-28 5.1 i 0.1 6.1 i 0.2 6.1 i 0.2 7.4 i 0.3 6.2 i 1.9 NW-29 7.7 i 0.3 8.5 i 0.3 9.1 i 0.3 10.4 i 0.2 8.9 i 2.3 NW-30 4.8 i 0.2 5.5 i 0.2 5.6 1 0.2 6.6 1 0.0 5.6 i 1.5 NNW-31 5.6 i 0.1 6.5 i 0.1 6.310.1 7.7 1 0.2 6.5 i 1.7 NNW-32 5.7 i 0.1 6.5 i 0.4 6.6 i 0.3 8.0 1 0.2 6.7 i 1.9 1

N-33 6.7 i 0.3 7.3 i 0.1 7.4 i 0.3 8.4 i 0.2 7.5 i 1.4 N 34 5.310.2 6.0 i 0.1 5.9 0.1 6.9 i 0.3 6.0 i 1.3 NNE 35 8.9 i 0.3 9.3 i 0.2 9.3 i 0.5 11.0 i 0.3 9.6 i 1.9 NNE 36 5.9 i 0.1 6.7 i 0.2 6.9 i 0.2 8.0 i 0.2 6.9 1 1.7 NE 37 7.710.2 8.4 i 0.2 8.5 i 0.4 9.7 i 0.4 8.6 i 1.7 NE 38 5.410.2 6.1 i 0.1 6.3 i 0.1 7.6 i 0.1 6.4 1.8 ENE 39 7.0 i 0.2 7.7 i 0.1 7.9 i 0.2 8.9 i 0.2 7.9 i 1.6 ENE-40 5.5 i 0.1 6.4 i 0.1 6.0 i 0.1 (a) 6.0 1 0.9 j

E-41 7.110.2 7.8 i 0.1 8.1 i 0.3 9.3 1 0.3 8.1 1 1.8 E-42 6.4 i 0.5 7.0 0.1 7.3 i 0.5 8.4 1 0.8 7.3 1 1.7 l

ESE-43 6.2 i 0.2 7.0 i 0.2 2.9 i 0.1 8.2 i 0.2 7.1 1.7

}

ESE-44 6.8 i 0.1 7.6 0.2 8.1 i 0.3 9.110.4 7.9 1 1.9

(

SE-45 6.8 i 0.2 7.5 i 0.2 7.5 i 0.1 8.8 i 0.1 7.7 i 1.7 Q~)

I

(:) TLD missing.

74 i

i

r TABLE B-16:

DIRECT RADIATION MEASUREMENTS SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1998 mR/Std. Month (30.4 days) i 2 Sigma Page 2 of 2 Station First Qtr Second Qtr Third Qtr Fourth Qtr Average Number 01/07 04/02 04/02-07/01 07/01-10/07 10/07-01/13 i 2 S.d.

SE-46 8.7 i 0.2 9.6 i 0.3 9.6 1 0.3 10.9 i 0.2 9.7 i 1.8 SSE 47 7.210.4 7.5 0.2 8.4 i 0.3 9.1 i 0.3 8.1 i 1.7 SSE-48 5.510.2 6.0 i 0.1 6.5 1 0.2 7.4 i 0.2 6.4 i 1.6 i

S-49 8.3 i 0.5 10.4 i 0.2 10.7 i 0.4 11.5 i 0.4 10.212.7 S 50 4.6 i 0.5 5.1 i 0.1 5.4 i 0.1 6.4 0.1 5.4 i 1.5 SSW 51 7.810.5 8.7 i 0.2 9.5 i 1.0 10.411,0 9.1 i 2.2 SSW-52 4.510.2 5.4 i 0.1 5.4 i 0.2 6.4 i 0.1 5.4 1.6 SW 53 5.5 i 0.1 6.210.1 6.2 1 0.2 7.3 i 0.G 6.3 i 1.5 SW-54 6.6 i 0.2 7.3 i 0.2 7.6 i 0.2 8.6 1 0.2 7.5 i 1.7 WSW 55 7.6 i 0.2 8.7 i 0.2 8.5 1 0.3 13.010.3 9.5 i 4.8 WSW-56 6.3 i 0.3 7.2 i 0.1 7.2 i 0.1 8.2 i 0.3 7.2 i 1.6 W-57 8.4 i 0.3 9.1 0.2 9.1 0.1 10.010.2 9.2 i 1.3 W-58 4.9 i 0.1 5.8 i 0.1 5.7 i 0.2 6.8 i 0.2 5.8 1 1.6 WNW-59 5.0 i 0.1 5.7 i 0.2 5.8 i 0.2 6.6 i 0.2 5.8 i 1.3 WNW-60 5.4 i 0.1 6.110.1 6.1 i 0.1 7.2 i 0.3 6.2 i 1.5 NW-61 7.610.2 8.9 1 0.3 9.2 i 0.2 10.010.4 8.9 i 2.0 NW-62 4.710.0 5.6 i 0.1 5.3 i 0.1 6.4 i 0.1 5.5 i 1.4 s

NNW 63 5.9 i 0.1 6.4 i 0.1 6.3 i 0.1 7.4 i 0.1 6.5 i 1.3 CJ, NNW 64 5.8 i 0.3 6.8 i 0.2 6.6 1 0.2 7.7 i 0.1 6.7 i 1.6 C-1 5.7 1 0.1 6.4 i 0.2 6.0 i 0.2 7.110.2 6.3 i 1.2 C-2 5.6 i 0.1 6.0 i 0.2 6.1 i 0.1 7.2 1 0.2 6.2 i 1.4 C-3 5.710.1 6.1 i 0.1 6.1 i 0.3 7.3 i 0.1 6.3 i 1.4 C-4 5.810.1 6.4 i 0.1 6.0 i 0.1 7.2 i 0.2 6.4 i 1.2 C-5 4.8 0.1 5.0 i 0.1 5.1 i 0.2 6.3 i 0.1 5.3 i 1.4 C-6 4.7 i 0.1 5.1 i 0.1 5.2 i 0.2 6.4 i 0.1 5.4 i 1.5 C-7 6.8 i 0.1 7.2 i 0.2 6.9 i 0.2 8.1 i 0.1 7.3 i 1.2 C-8 7.1 i 0.1 7.1 i 0.1 7.0 1 0.1 8.4 i 0.1 7.4 i 1.3 Ayerage 6.3 i 2.4 7.1 i 2.6 7.2 i 2.8 8.4 i 3.1 7.2 3.1

)o 75 j

lO 4

1 l

l l

l lO AeresDix C LAND USE CENSUS - 1998 l

l i

I l

I i

O

VIRGINIA POWER I

NORTH ANNA POWER STATION C)

A....i Rooioio ic.i E. viro.me..i t.a use ce.s., o.. re,1998 July (1-31)

Nearest Nearest Site Milch

Meat Milch

Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq Ft.

KM KM KM KM KM KM N

2.4 1.4 3.5 3.2 NNE 1.4 1.4 2.3 2.5 NE 1.5 1.3 2.3 1.5 ENE 3.4 1.3 4.0 3.4 E

2.1 1.3 5.7 2.1 i

l ESE 2.7 1.4 7.7 5.3 SE 2.3 1.4 2.3 2.3 SSE 1.6 1.5 4.5 1.6 O

S 1.7 1.5 2.4 2.1 SSW l.9 1.6 3.1 4.8 l

SW 5.0 1.7 NONE 5.0 WSW 2.7 1.8 2.7 2.7 W

2.4 1.7 7.I 8.0 WNW l.8 1.6 6.5 4.2 NW l.7 1.6 NONE 1.9 NNW l.6 1.4 3.2 1.9 i

(

O)

U

Note:

No milch cow or goats within a five mile radius of North Anna Power Station KM = Kilometer i

l 76

p l

l l

VIRGINIA POWER NORTH ANNA POWER STATION mV Annual Radiological Environmental Land Use Census Data for 1998 July (1-31)

Nearest Nearest Site Milch

Meat Milch

Veg. Garden l

l Sector Resident Boundary Cow Animal Goat 500 Sq Ft.

l M

M M

M N

1.5 0.9 2.2 2.0 l

NNE 0.9 0.9 1.5 1.5 NE 0.9 0.8 1.4 0.9 ENE 2.1 0.8 2.5 2.1 E

1.3 0.8 3.5 1.3 ESE 1.7 0.9 4.8 3.3 l

SE 1.4 0.9 1.4 1.4 SSE 1.0 0.9 2.8 1.0 O

S 1.1 0.9 1.5 1.3 SSW l.2 1.0 2.0 3.0 i

SW 3.1 1.1 NONE 3.1 WSW l.7 1.1 1.7 1.7 W

l.5 1.1 4.4 5.0 WNW l.1 1.0 4.1 2.6 NW l.0 1.0 NONE 1.2 NNW l.0 0.9 2.0 1.2 I

i f\\

U

Note:

No milch cow or goats within a five mile radius of North Anna Power Station M = Mile j

I 77

p i

l VIRGINIA POWER

)

l NORTH ANNA POWER STATION l

COMPARISON OF TIIE 1998 TO 1997 LAND USE CENSUS I. Changes in the nearest resident status as compared to previous year are as follows:

l l

a.

SSW Sector 2.30 kM (1997) to 1.9 kM (1998) b.

NNW Sector 1.72 kM (1997) to 1.6 kM (1998)

II. No changes were observed in the nearest site boundary distances.

III. No changes were observed in the nearest milch cow / goat status.

IV. Changes in the nearest vegetable garden as compared to the previous year are as follows:

a.

SSE Sector 2.30 kM (1997) to 1.6 kM (1998) b.

SSW Sect r 2.20 kM (1997) to 4.8 kM (1998)

O c.

W Sector 3.20 kM (1997) to 8.0 kM (1998) d.

NW Sector 1.77 kM (1997) to 1.9 kM (1998)

V. Changes to the nearest meat animal status as compared to the previous year are as follows:

a.

NNE Sector 4.22 kM (1997) to 2.3 kM (1998) b.

E Sector None(1997) to 5.7 kM (1998) c.

SSW Sector 6.61 kM (1997) to 3.1 kM (1998) d.

W Sector None (1997) to 7.1 kM (1998)

O l

78

)

1 f

o l

i AerExoix o O

SYNOPSIS OF ANALYTICAL PROCEoURES l

I l

O i

F ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed on samples collected for j

i l

the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Brown Engineering and include those recommended by the USNRC Branch Technical Position, Rev.1, November 1979.

l ANALYSIS TITLE

]M,fd l

t G ross Beta Analysis of Samples........................................................................ 80 i

Airborne Particul ates............................................................................ 80 l

\\

l Water.............................................................................................81 1

Analysis of S amples for Tritium (Liquid Scintillation)............................................... 82 Analysis of S amples for Strontium-89 and -90....................................................... 83 Total Wate r....................................................................................... 8 3 I

l Milk................................................................................................83 Soil and Sedi ment............................................................................... 8 3 Organic Solids.................................................................................... 84 li, Air Particu lates................................................................................... 84 Analysis of Samples for Iodine-131.................................................................... 86 M ilk or Wate r..................................................................................... 8 6 l

1 l

Gamma Spectrometry of S amples'...................................................................... 87 Milk and Water................................................................................... 8 7 Dried Solids other than Soils and Sediment................................................. 87 l

Fish...............................................................................................87 i

L l

Soils and Sedime nt s............................................................................ 8 7 Charcoal Cartridges (Air Iodine)............................................................... 87 l

l Airbome Particulates............................................................................ 87 Environ mental Dosi metry................................................................................ 8 9 LO 79

GROSS BETA ANALYSIS OF SAMPLES O

Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by the customer, is counted as the blank.

Calculations of the results, the two sigma error and the lower limit of detection (LLD):

3

((S/r)-(B/t))/(2.22 V E)

RESULT (pCi/m )

=

2((S/T ) + (B/t ))l/2 (2.22 V E) 2 2

/

TWO SIGMA ERROR (pCi/m3)

=

4.66 (BM)/(2.22 V E t)

LLD (pCi/m3)

=

where:

Gross counts of sample including blank S

=

Counts of blank B

=

Counting efficiency E

=

Number of minutes sample was counted T

=

O number of minutes biank was counted t

=

Sample aliquot size (cubic meters)

V

=

l l

OV 80 i

i DETERMINATION OF GROSS BETA ACTIVITY

(

O

'IN WATER SAMPLES lV l

Introduction The procedures described in this section are used to measure the overall redioactivity of water samples without identifying the radioactive species present.

No chemical separation l

techniques are involved.

l One lite of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has t gnificant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 fiiter paper before evaporation, removing particles greater than 30 microns in size.

After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchette which i; stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.

Residue mass is determined by weighing the planchette before and after mounting the l

sample. The planchette is counted for beta activity on an automatic oroportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass.

lO rv Detection Capability

- Detection capability depends upon the sample volume actually represented on the planchette, 1

the background and the efficiency of the counting instrument, and upon self-absorption of beta l

I particles by the mounted sample. Because the radioactive species an: not identified, no decay corrections are made and the reported activity refers to the counting time.

The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter j

for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 sigma level), assuming that I liter of I

sample is used and that 7 gram of sample residue is mounted on the planchette. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.

The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta' counting efficiency of 0.38.

81 e

i

m ANALYSIS OF SAAfPLES FOR TRITIUni

O~

Water Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zine conversion column heated to 400* C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure, i

The propottional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays.

l I

Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/l:

I 2(3.234)T V (C - B)/(C V )

RESULT

=

g u o u s 2(3.234)Tg V (E)1/2 (C V )

)

/

TWO SIGMA ERROR

=

u y s 3.3 (3.234)T V (E)l/2 (C V )

/

LLD

=

y u y s l

where:

T

=

tritium units of the standard g

conversion factor changing tritium units to pCi/l 3.234

=

volume of the standard used to calibrate the efficiency of the detector in V

=

g f

psia volume of the sample loaded into the detector in psia V

=

s the net epm of the standard of volume VN Cu

=

the gross epm of the sample of volume VS Co

=

the background of the detector in epm B

=

counting time for the sample at

=

Sft 2 + B/t2 E

=

l O

82

f V

~ ANALYSIS OF SAMPLES

~ FOR STRONTIUM 89 AND -90

}

. Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO )2 using nitric acid. A barium scavenge and an 3

iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined I

by precipitating SiCO from the sample after yttrium separation. This precipitate is mounted on a I

3 L

nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

i Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN0 using fuming (90%) nitric acid. A barium chromate scavenge 3

l and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the l.

sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity, Strontium-89 is determined by precipitating SrC0 from the sample after yttrium separation. This pmcipitate 3

2 is mounted on a nylon planchette and is covered with an 80 mfgem aluminum absorber for low level beta counting.

i l

l Soil and Sediment l

The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier l

' is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO )2 using 3

('

fuming (90% nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then pmcipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by pmcipitating SrC0 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette 3

and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

f f

1 83

]

Organic Solids A wet portion of the sample is dried and then ashed in a mufne furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is Gltered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO ) using 3

fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then pre-cipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity.

Strontium-89 activity is determined by precipitating SrC03 fmm the sample after yttrium 2

separation. This precipitate is mounted on a nylon p%nchette and is covered with an 80 mg/cm aluminum absorber for low level beta counting.

Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric acid. A barium 3

scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is

]

performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer 3 rom the sample l

strontium-90 activity. Strontium-89 activity is determined by precipitating SrC0 f after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 2

mg/cm aluminum absorber for low level beta counting.

Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume or pCi/ mass:

= (N/Dt-B -B )/(2.22 V Y DFSR-89 ESR-89)

RESULT Sr-89 C A 3

l TWO SIGMA ERROR Sr-89

= 2((N/Dt+B +B )/At)l/2 (2.22 V Y DF ESR-89)

/

C A 3

SR-89

= 4.66((B +B )/At)l/2 (2.22 V YS DFSR-89 ESR.89)

C A

/

LLD Sr-89 RESULT Sr-90

= (N/At - B)/(2.22 V Yj Y DF IF E) 2 l

2((N/At+B)/At)l/2 (2.22 V Yj Y DF E IF))

/

2 TWO SIGMA ERROR Sr-90

=

= 4.66(B/At)I/2 (2.22 V Yj Y IF DF E) j

/

2 LLD Sr-90

("]

v 84

I' l

j WilERE:

N total counts from sample (counts)

=

(')

counting time for sample (min)

At

=

C background rate of counter (cpm) using absorber configuration B

=

dpm/pCi

)

2.22

=

V

=

volume or weight of sample analyzed background addition from Sr-90 and ingrowth of Y-90 B

=

A 0.016 (K) + (K) EY/ abs)(IG -90)

B

=

Y A

chemical yield of strontium Y

=

s SR-89 decay factor from the mid collection date to the counting DF

=

date for SR-89 SR-89 cfficiency of the counter for SR-89 with the 80 mg/cm.sq.

E

=

aluminum absorber (NAt - B )Y-90 (E -90IFy.90 DF -90 j )

Y Y K

=

C

/ Y the decay factor for Y-90 from the " milk" time to the mid DFY-90)

=

count time Y-90 efficiency of the counter for Y-90 E

=

ingrowth factor for Y-90 from scavenge time to milking time IF

=

Y-90 the ingrowth factor for Y-90 into the strontium mount from IG

=

Y-90 (v')

the " milk" time to the mid count time the efficiency of measuring SR-90 through a No. 6 absorber 0.016

=

the efficiency of counting Y-90 through a No. 6 absorber EY

=

/ abs background rate of counter (cpm)

B

=

chemical yield of yttrium Y

=

i chemical yield of strontium Y

=

2 decay factor of yttrium from the radiochemical milking time to DF

=

the mid count time efficiency of the counter for Y-90 E

=

ingrowth factor for Y 90 from scavenge time to the radio-IF

=

chemical milking time I

.rb V

85

ANALYSIS OF SAMPLES FOR 10 DINE-131

'O Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitat'ed as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.

Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/l:

l tN/At-B)/(2.22 E V Y DF)

RESULT

+

=

2((N/4t+B)/At)l/2 (2.22 E V Y DF)

/

TWO SIGMA ERROR

=

= 4.66(B/At)l/2 (2.22 E V Y DF) j

/

LLD

=

f total counts from sample (counts) 1

. where:

N

=

counting time for sample (min)

At

=

background rate of counter (cpm)

BL

=

dpm/pCi 2.22

=

volume or weight of sample analyzed V

=

chemical yield of the mount or sample counted Y

=

decay factor from the collection to the counting date DF

=

efficiency of the counter for 1-131, corrected for self E

=

absorption effects by the formula 1

l E

E,(exp-0.006iM)/(exp-0.006lM,)

=

efficiency of the counter determined from an I-131 E,

=

standard mount mass of Pdl on the standard mount, mg Ms-

=

2 mass of PDI on the sample mount, mg M.

=

2 O

1 l

1 86-l l

L

f l

GAMAfA SPECTR0hfETRY OF SAMPLES O

Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature, less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-j computer-based data acquisition system which performs pulse height analysis.

Fish As much as possible (up to the total sample) of the edible portion of tb ample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini <omputer-based data acquisition system which performs pulse height analysis.

Solls and Sediments Soils and sediments are dried at a low temperature, less than 100 C. The soil or sediment j

is loaded fully into a tared, standard 300 cc container and weighed. The sample is then coumed for 1

approximately six hours with a shielded Ge(Li) detector <:oupled to a mini-computer-based data acquisition system which performs pulse l'eight and analg Cnarcoal Cartridges (Air Iodine)

]

Chr.; coal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined (assuming no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulate j

The thirteen airborne particulate filters for a quarterly composite for each field station are JO iisaea o#e ia croet or eaother a#a the# eeu#ted for at ie i six nour, with a,nieidea oec'i>

\\

87

o detector coupled to a mini-computer-based data acquisition system which performs pulse height Q

analysis.

A mini-computer software program defines peaks by cenain changes in the slope of the spectrum. The program rJso compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the app opriate fractional gamma l

ray abundance, halflife, detector efficiency, and net counts in'the peak region. The calculation of l

- results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass:

(S-B)/(2.22 E V F DF)

RESULT

=

2(S+B)l/2 (2.22 t E V F DF)

/

TWO SIGMA ERROR

=

4.66(B)I/2 (2.22 t E V F DF)

/

LLD

=

Area, in counts, of sample peak and background

)

where:

S

=

(region of spectrum ofinterest)

Background area, in counts, under sample peak, B

=

determined by a linear interpolation of the representative backgrounds on either side of the peak l

t

=

length of time in minutes the sample was counted dpm/pCi l

2.22

=

detector efficiency for energy of interest E

=

and geometry of sampic sampic aliquot size (liters, cubic meters, kilograms, V

=

or grams)

F.

fractional gamma abundance (specific for each

=

emitted gamma)

DF decay factor from the mid-collection date to the

=

counting date I

mU 88

I l

l ENVIRONMENTAL DOSinfETRY

/

.g Teledyne Brown Engineering uses a CaSO :Dy thermoluminescent dosimeter (TLD) which i

4 the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.

Following the field exposure period the TLDs are placed in a Teledyne Brown Engineering Model 8300. One founh of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use.

The transit controls are read in the same manner.

Calculations of results and the two sigma error in net milliroentgen (mR):

RESULT D = (D +D +D +D )/4

=

y 2 3 4 2((D -D)2+(D -D)2+(9 9)2+(p o)2)f3)1c TWO SIGMA ERROR

=

g 2

3 g

WHERE:

D g the net mR of area 1 of the TLD, and similarly for D, D, and D4

=

2 3 I K/R; - A

=

Di l

g the instrument reading of the field dose in area 1 I

=

the kr.own exposure by the Cs-137 source K

=

j the instrument reading due to the Cs-137 dose on area 1 R

=

average dose in mR, calculated in similar manner as above, A

=

of the transit control TLDs the average net mR of all 4 areas of the TLD.

D

=

I I

l'n 89

O l

l l

' Q APPENDIX E INTERLABORATORY COMPARISON PROGRAM O

r Interlaboratory Comparison Program

,f~)

Teledyne Brown Engineering participates in the EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. Beginning with 1996 the EPA discontinued providing milk and air particulate filter samples. For replacements, we have purchased comparable spiked samples from Analytics,Inc.

I In this section the 1998 data summary tables are presented for isotopes in the various sample media applicable to the North Anna Power Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.

'v l

l nlU i

90

gn n io nit ra c W A

_ O

)

v (c 42 79 4

67 0 600667158 53623 78 03 5 2 e) 1 Dn 01 55 8

92 6 506242835 33497 05 02 66 9 w

0 00 0

00 000101000 01001 10 00 00 1

1 mo 1

rn oN (K 38 50 0

80 4

300655308 02885 51 08 48 0

75 69 0

50 7 702511505 05506 82 05 60 0 0 20 O

02 7 100611 110 12022 00 1

0 02 0 1

5

)b (s

ii i

i i1 1

i111iiii i1 1 11 i

1i 1

t lu 07 00 0

70 3 000077307 07370 73 03 37 0 ITs

0. 6 06 0

60 3 005.066306 0.6360 49 03 46 0 e

51 35 0

42 3

058241211 31275 41 1

6 54 0

R 3 3 3 3 51 0

2521 11333 2

1 1

0 1

8 1

1 0

9 1

6 9

1 1

M 00 60 5

43 0 633000000 00000 75 00 00 0 AR 55 75 0

28 8

322055555 50555 00 55 55 0

)a 1

4 1

1 1

G 0

(

O s

3 8

t 1

R Alu P

Ps 11 i

11 i ii1i111i it ii ii i 1 1i i Ee

0. 0 59 9

03 0 4 0 3.7 0.0 0 0 0 00000 91 00 28 0 AN R

NO 82 03 4

63 5

459468020 241 50 42 17 72 6 NS 3 3 0

3 5 51 9

1521 10334 2

1 9

1 I

1 1

1 AR) 9 2

2 7

A H Pf 1

T o

R M O O1 N C e OO g

Y a a

a a

RP e

ha 68 h68a 47 473 68 ha C O(

d pt 22 p2 2 e 9 0 0 3 3 05 333 22 90 e

t pt H

90 LAB 3

22 A22B8961 e

1 l

P l

E T 66111 22 89 AB c

89 1

3 3

V A a

rr rr 1

o s s-onssa aa rr rr aa raar rr R

N SS GG RR GRRGSSCCC CZCCB RR SS GG H 1

O I

1 BALRE a

i r

r r

T d

e e

e N

e t

t t

a a

a M

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W W

W PE s

t lu As 8

8 8

8 9

9 9

Pe 9

9 9

ER

/

5 5

9 5

8 5

8 4

8 ed 1

1 1

1 2

2 0

0 0

ta e

/

u Ds 6

6 6

0 9

9 3

1 3

0 0

0 1

0 0

0 s

I de li 8

8 8

a 9

9 9

Ms

/

t 7

7 7

0 4

1 7

7 5

1 4

IlTu 2

2 1

1 0

2 0

0 2

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s

/

ee 3

2 2

4 4

4 8

8 9

tR 0

0 0

a D

n O

o 8

8 8

it 9

9 9

Aa

/

Pr 6

0 6

2 3

1 5

2 7

4 7

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3 0

1 1

2 0

1 1

2 0

pe

/

r 1

1 2

2 3

4 6

6 7

7 8

P 0

0 0

gn n

)

io

)

ni d

d d

t

(

ra c W'A O

)

v. c 4

64 532639 89959

(

e)

Dn 1

92 321 421 52627 w

0 01 300002 01012 tao rn oN (K 5 65 435589 27032 5 43 651 157 59055 0 O0 711103 20212

)

1 b

(s 1 i iiiiii ii1i1 t

l Iu 3 30 733373 77033 Ts 9 57 63336.3 66033 e

5 16 488266 90356 R

71 2 5 3401 4 8

111 99 1

MA 0 34 000000 00000 R

2 01 055555 53566

)a 1

1 G

(

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A Em P

1 i

1 11 1i111 P

77 00000.0 0.0000 1

AN R

NO 6

15 498160 81516 NS 91 2 5 33015 I

111 A R )2 A

H Pf T

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g Y a O RP e

68 a

47 473 C O(

d t

22 e90033 05333 P

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3 22 B89611 6611 l

1

^

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1 aa r rross onssa R

N RR GSSCCC CZCCB 1

OB A

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a y

i r r r

r T

d e

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N e

t t

o a

a a

a h

M I

A W W W

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lb E

)

la n

s io iav t

t a

l a

u n

e As 9 9 9

9 Pe 9 9 9

9 i

b n

r l

ER

/ /

/

r l

i e

8 4

9 6

w t

ed 0 0 2

1 s

e t

d ae

/ /

/

lt u

Ds 3

3 3

I u

1 0 0 0

0 s

s a

. e r

I m

ig

, ;d

=

e s

t k

c d

(

I e

e u a n h

n i

li 8 8 8

8 m

io t

m a

9 9 9

9 s

n Ms

/ /

/

ig i o g

r s

c t

5 3 3

8 l

r f

i e

r Il a

n Tu 2

1 2

1 p

t s

/ /

/

n n e 1

1 1

n o i b y o ee 9

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w r

I tR 0

t s

a i

t t

a D

i a

v n

re r

o p

o e i x b d ta ig e a dt l

i n

d i e

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e e

o 8 8 8

8 g

t l-v it 9 9 9

9 a c r

e n

Ae

/ /

/

e p

. i P i.

1 8

0 1

v x

v n A E N A E

1 1

2 1

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/ /

/

7 9 9 0

1

)

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(

,ru

r-l l

l ANALYTICS CROSS CHECK COMPARISON PROGRAM 1998 O

Teledyne Brown Analytics l

Sample ID Media Nuclide Engineering Result (a)

Result Ratio (b)

E1346-396 Milk 1-131 87 i 9

82 i 4

1.06 TI#71657 Ce-141 66 1 7

70 i 4

0.94 03/12/98 Cr-51 220i 30 201 i 10 1.09 Cs-134 85 i 9

84 i 4

1.01 Cs-137 180i 20 161 i 8

1.12 Mn-54 130i 10 133 i 7

0.98 Fe-59 110 i 10 95 i 5

1.16

. Zn-65 160i 20 142i 7

1.13 Co-60 82 i 8

85 i 4

0.96 Footnotes:

I Teledyne Results - counting error is two standard deviations. Units are pCi/ liter for water O

(a) eed miix. rer gemma reseite. if two etenderd devietiees ere iess inen 10*. inen e 10* errer is reported. Units are total pCi for air particulate filters.

(b)

Ratio of Teledyne Brown Engineering to Analytics results.

i l

93

O 6

9 9

1 L.

5 i 9 9

o 1

4 9

9 o

1 3

9 f"i 9

1 2

9 9

1

)

1 1

9 f

9 a

M o

l m

1 A

o ig 1

0 S

R g

9 3

p 9

i G

(

1 6

A 9

O S

P 9

9 E

1 R

E 8

n P

T 9

is A

1 o

K L

o lep c

U 8

m OC C

8 a

E 9

s I

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